80_FR_12695 80 FR 12649 - Compliance With Phase 2 of Order EA-13-109

80 FR 12649 - Compliance With Phase 2 of Order EA-13-109

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 46 (March 10, 2015)

Page Range12649-12651
FR Document2015-05436

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment its Japan Lessons-Learned Division (JLD) draft interim staff guidance (ISG), ``Compliance with Phase 2 of Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions,'' (JLD- ISG-2015-01). This draft JLD-ISG would provide guidance and clarification to assist nuclear power reactor licensees identify measures needed to comply with Phase 2 requirements of the ``Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions,'' (Order EA-13- 109) to have either a vent path from the containment drywell or a strategy that makes it unlikely that venting would be needed from the drywell before alternate reliable containment heat removal and pressure control is reestablished.

Federal Register, Volume 80 Issue 46 (Tuesday, March 10, 2015)
[Federal Register Volume 80, Number 46 (Tuesday, March 10, 2015)]
[Notices]
[Pages 12649-12651]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-05436]


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NUCLEAR REGULATORY COMMISSION

[NRC-2015-0048]


Compliance With Phase 2 of Order EA-13-109

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft interim staff guidance; request for comment.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for 
public comment its Japan Lessons-Learned Division (JLD) draft interim 
staff guidance (ISG), ``Compliance with Phase 2 of Order EA-13-109, 
Order Modifying Licenses with Regard to Reliable Hardened Containment 
Vents Capable of Operation under Severe Accident Conditions,'' (JLD-
ISG-2015-01). This draft JLD-ISG would provide guidance and 
clarification to assist nuclear power reactor licensees identify 
measures needed to comply with Phase 2 requirements of the ``Order 
Modifying Licenses with Regard to Reliable Hardened Containment Vents 
Capable of Operation Under Severe Accident Conditions,'' (Order EA-13-
109) to have either a vent path from the containment drywell or a 
strategy that makes it unlikely that venting would be needed from the 
drywell before alternate reliable containment heat removal and pressure 
control is reestablished.

DATES: Submit comments by April 9, 2015. Comments received after this 
date will be considered, if it is practical to do so, but the 
Commission is able to ensure consideration only for comments received 
before this date.

ADDRESSES: You may submit comment by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0048. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Mail comments to: Cindy Bladey, Office of Administration, 
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Rajender Auluck, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-1025; email: Rajender.Auluck@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0048 when contacting the NRC 
about the availability of information regarding this document. You may 
obtain publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0048.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly-available documents online in the NRC 
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the 
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's 
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number 
for each document referenced in this notice (if that document is 
available in ADAMS) is provided the first time that a document is 
referenced. The draft JLD-ISG-2015-01 is available in ADAMS under 
Accession No. ML15051A143. The ISG for complying with Phase 1 
requirements of the order (JLD-ISG-2013-02) was issued on November 14, 
2013 (ADAMS Accession No. ML13304B836).
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.
     NRC's Interim Staff Guidance Web site: JLD-ISG documents 
are also available online under the ``Japan Lessons Learned'' heading 
at http://www.nrc.gov/reading-rm/doc-collections/isg/japan-lessons-learned.html.

B. Submitting Comments

    Please include Docket ID NRC-2015-0048 in the subject line of your 
comment submission, in order to ensure that the NRC is able to make 
your comment submission available to the public in this docket.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC posts all comment submissions at http://www.regulations.gov as well as entering the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment submissions into ADAMS.

II. Background

    The NRC developed draft JLD-ISG-2015-01 to provide guidance and 
clarification to assist nuclear power reactor licensees with the 
identification of methods needed to comply with Phase 2 requirements in 
Order EA-13-109, ``Order Modifying Licenses with Regard to Reliable 
Hardened Containment Vents Capable of Operation under Severe Accident 
Conditions'' (ADAMS Accession No. ML13130A067). The draft ISG would not 
be a substitute for the requirements in Order EA-13-109, and compliance 
with the ISG would not be a requirement. This ISG is being issued in 
draft form for public comment to involve the public in development of 
the implementing guidance.
    The accident at the Fukushima Dai-ichi nuclear power station 
reinforced the importance of reliable operation of containment vents 
for boiling-water reactor (BWR) plants with Mark I and Mark II 
containments. As part of its response to the lessons learned from the 
accident, on March 12, 2012, the NRC issued Order EA-12-050 (ADAMS 
Accession No. ML12056A043) requiring licensees to upgrade or install a 
reliable hardened containment venting system (HCVS) for Mark I and Mark 
II containments. The requirements in Order EA-12-050 for licensees with

[[Page 12650]]

BWR plants with Mark I and Mark II containments were intended to 
increase the reliability of containment venting to support decay heat 
removal from the reactor core and provide protection against over-
pressurization of the primary containments. While developing the 
requirements for Order EA-12-050, the NRC acknowledged that questions 
remained about maintaining containment integrity and limiting the 
release of radioactive materials if licensees used the venting systems 
during severe accident conditions.
    The NRC staff presented the Commission with options to address 
these issues in SECY-12-0157, ``Consideration of Additional 
Requirements for Containment Venting Systems for Boiling Water Reactors 
with Mark I and Mark II Containments'' (issued November 26, 2012, ADAMS 
Accession No. ML12325A704). The options presented in SECY-12-0157 
included continuing with the implementation of Order EA-12-050 for 
reliable hardened vents (Option 1); requiring licensees to upgrade or 
replace the reliable hardened vents required by EA-12-050 with a 
containment venting system designed and installed to remain functional 
during severe accident conditions (Option 2); requiring licensees with 
BWR Mark I and Mark II containments to install an engineered filtered 
containment venting system intended to prevent the release of 
significant amounts of radioactive material following the dominant 
severe accident sequences (Option 3); and pursuing development of 
requirements and technical acceptance criteria for performance-based 
confinement strategies (Option 4). The NRC staff provided an evaluation 
considering various quantitative analyses and qualitative factors 
related to the options and recommended the Commission approve Option 3 
to require the installation of an engineered filtering system. One 
issue not specifically addressed within SECY-12-0157 was the importance 
of water addition to cool core debris as part of severe accident 
management for BWR's with Mark I and II containments. The NRC staff 
acknowledged in SECY-12-0157 that in the longer-term rulemaking 
associated with any of the options presented, the NRC could consider 
adding requirements for the capability of core debris cooling during 
severe accident scenarios.
    In the staff requirements memorandum (SRM) for SECY-12-0157, dated 
March 19, 2013 (ADAMS Accession No. ML13078A017), the Commission 
directed the staff to: (1) Issue a modification to Order EA-12-050 
requiring BWR licensees with Mark I and Mark II containments to upgrade 
or replace the reliable hardened vents required by Order EA-12-050 with 
a containment venting system designed and installed to remain 
functional during severe accident conditions, and (2) develop a 
technical basis and rulemaking for filtering strategies with drywell 
filtration and severe accident management of BWR Mark I and II 
containments. The NRC subsequently issued Order EA-13-109 to define 
requirements and schedules for licensees for BWRs with Mark I and Mark 
II containments to install severe accident capable containment venting 
systems. The NRC staff also initiated development and evaluation of 
other possible regulatory actions identified in the Commission's SRM 
for SECY-12-0157, including the development of a technical basis in 
support of a Containment Protection and Release Reduction (CPRR) 
rulemaking.
    Order EA-13-109, in addition to requiring a reliable HCVS to assist 
in preventing core damage when heat removal capability is lost (the 
purpose of EA-12-050), will ensure that venting functions are also 
available during severe accident conditions. Severe accident conditions 
include the elevated temperatures, pressures, radiation levels, and 
combustible gas concentrations, such as hydrogen and carbon monoxide, 
associated with accidents involving extensive core damage, including 
accidents involving a breach of the reactor vessel by molten core 
debris. The safety improvements to Mark I and Mark II containment 
venting systems required by Order EA-13-109 increase confidence in 
licensees' ability to maintain the containment function following core 
damage events. Although venting the containment during severe accident 
conditions could result in the release of radioactive materials, 
venting could also prevent containment structural failures and gross 
penetration leakage due to overpressurization that would hamper 
accident management (e.g., continuing efforts to cool core debris) and 
ultimately result in larger, uncontrolled releases of radioactive 
material.
    In recognition of the relative importance of venting capabilities 
from the wetwell and drywell, a phased approach to implementation is 
being used to minimize delays in implementing the requirements 
originally imposed by Order EA-12-050. Phase 1 involves upgrading the 
venting capabilities from the containment wetwell to provide reliable, 
severe accident capable hardened vents to assist in preventing core 
damage and, if necessary, to provide venting capability during severe 
accident conditions. Phase 2 involves providing additional protection 
during severe accident conditions through installation of a reliable, 
severe accident capable drywell vent system or the development of a 
reliable containment venting strategy that makes it unlikely that a 
licensee would need to vent from the containment drywell during severe 
accident conditions. For implementation of Phase 1 order requirements, 
the NRC issued JLD-ISG-2013-02 on November 14, 2013 (78 FR 70356), 
which endorsed, with clarifications, the methodologies described in the 
industry guidance document Nuclear Energy Institute (NEI) 13-02, Rev. 0 
(ADAMS Accession No. ML13316A853). As required by the order, licensees 
submitted their site-specific overall integrated plans by June 30, 
2014. The NRC is currently reviewing these plans and expects to 
complete those reviews by June 2015.
    The focus of this ISG is to provide guidance for Phase 2 
requirements of the order. Some proposed approaches to implement Phase 
2 requirements of the order include the addition of water to the 
drywell during severe accident conditions. Evaluations performed by the 
NRC and industry in conjunction with the CPRR rulemaking show that 
water addition during severe accident conditions provides benefits that 
include reducing temperatures and cooling molten core debris. In SECY-
12-0157, the NRC discussed various risk assessments by the NRC and 
industry that have concluded that adding water to the drywell reduces 
the likelihood of release of radioactive materials for those severe 
accident scenarios that involve fuel melting through the reactor 
vessel. The water added to the drywell cools the molten fuel and can 
arrest the melting fuel's progression and reduce the likelihood of a 
loss of the containment function through liner melt-through, 
containment over-pressurization failure, and containment over-
temperature failure. In addition to the benefits associated with 
containment protection, recent technical evaluations performed by both 
the industry and the NRC indicate that including the capability of 
timely severe accident water addition (SAWA) results in a substantially 
lower drywell temperature for consideration in designing the drywell 
vent. Therefore, SAWA will facilitate implementation of Phase 2 of 
Order EA-13-109 by establishing the design conditions for a drywell 
vent and supporting severe accident water management (SAWM) for

[[Page 12651]]

licensees choosing to pursue that option as a strategy that makes it 
unlikely that a licensee would need to vent from the drywell.
    On December 10, 2014, NEI submitted NEI 13-02, ``Industry Guidance 
for Compliance with Order EA-13-109,'' Rev. 0E2 (ADAMS Accession No. 
ML1434A374) to assist nuclear power licensees with the identification 
of measures needed to comply with the requirements of Order EA-13-109 
regarding reliable hardened containment vents capable of operation 
under severe accident conditions. The NEI document includes guidance 
for implementing order requirements for both Phase 1 and Phase 2, 
including the industry's proposed approach to use the SAWA and SAWM 
strategies to control the water levels in the suppression pool and 
maintain capabilities to address over-pressure conditions without a 
severe accident drywell vent. As described in the draft ISG, some 
issues remain the subject of ongoing discussions as part of finalizing 
the guidance. These include: (1) Availability of power and functional 
requirements for the SAWA-related installed and portable equipment, (2) 
duration of time for preservation of the wetwell vent for the SAWM 
strategy, and (3) alternate control of containment conditions during 
recovery from the severe accident. The NRC intends to continue 
discussions with stakeholders prior to finalizing the ISG for Phase 2 
of the order and endorsing, with clarifications and exceptions if 
necessary, the methodologies described in the industry guidance 
document NEI 13-02, Rev. 0E2.

    Dated at Rockville, Maryland, this 2nd day of March 2015.

    For the Nuclear Regulatory Commission.
Jack R. Davis,
 Director, Japan Lessons-Learned Division, Office of Nuclear Reactor 
Regulation.
[FR Doc. 2015-05436 Filed 3-9-15; 8:45 am]
 BILLING CODE 7590-01-P



                                                                                Federal Register / Vol. 80, No. 46 / Tuesday, March 10, 2015 / Notices                                            12649

                                                  www.justice.gov/enrd/Consent_                             • Mail comments to: Cindy Bladey,                   B. Submitting Comments
                                                  Decrees.html.                                           Office of Administration, Mail Stop:                    Please include Docket ID NRC–2015–
                                                                                                          OWFN–12–H08, U.S. Nuclear                             0048 in the subject line of your
                                                  Cherie L. Rogers,
                                                                                                          Regulatory Commission, Washington,                    comment submission, in order to ensure
                                                  Assistant Section Chief, Environmental
                                                  Defense Section, Environment and Natural
                                                                                                          DC 20555–0001.                                        that the NRC is able to make your
                                                                                                            For additional direction on obtaining
                                                  Resources Division.                                                                                           comment submission available to the
                                                                                                          information and submitting comments,
                                                  [FR Doc. 2015–05493 Filed 3–9–15; 8:45 am]                                                                    public in this docket.
                                                                                                          see ‘‘Obtaining Information and                         The NRC cautions you not to include
                                                  BILLING CODE 4410–15–P
                                                                                                          Submitting Comments’’ in the                          identifying or contact information that
                                                                                                          SUPPLEMENTARY INFORMATION section of
                                                                                                                                                                you do not want to be publicly
                                                                                                          this document.                                        disclosed in your comment submission.
                                                  NUCLEAR REGULATORY
                                                                                                          FOR FURTHER INFORMATION CONTACT:                      The NRC posts all comment
                                                  COMMISSION
                                                                                                          Rajender Auluck, Office of Nuclear                    submissions at http://
                                                  [NRC–2015–0048]                                         Reactor Regulation, U.S. Nuclear                      www.regulations.gov as well as entering
                                                                                                          Regulatory Commission, Washington,                    the comment submissions into ADAMS.
                                                  Compliance With Phase 2 of Order EA–                    DC 20555–0001; telephone: 301–415–
                                                  13–109                                                                                                        The NRC does not routinely edit
                                                                                                          1025; email: Rajender.Auluck@nrc.gov.                 comment submissions to remove
                                                  AGENCY:  Nuclear Regulatory                             SUPPLEMENTARY INFORMATION:                            identifying or contact information.
                                                  Commission.                                             I. Obtaining Information and                            If you are requesting or aggregating
                                                  ACTION: Draft interim staff guidance;                   Submitting Comments                                   comments from other persons for
                                                  request for comment.                                                                                          submission to the NRC, then you should
                                                                                                          A. Obtaining Information                              inform those persons not to include
                                                  SUMMARY:   The U.S. Nuclear Regulatory                     Please refer to Docket ID NRC–2015–                identifying or contact information that
                                                  Commission (NRC) is issuing for public                  0048 when contacting the NRC about                    they do not want to be publicly
                                                  comment its Japan Lessons-Learned                       the availability of information regarding             disclosed in their comment submission.
                                                  Division (JLD) draft interim staff                      this document. You may obtain                         Your request should state that the NRC
                                                  guidance (ISG), ‘‘Compliance with                       publicly-available information related to             does not routinely edit comment
                                                  Phase 2 of Order EA–13–109, Order                       this action by the following methods:                 submissions to remove such information
                                                  Modifying Licenses with Regard to                          • Federal Rulemaking Web site: Go to               before making the comment
                                                  Reliable Hardened Containment Vents                     http://www.regulations.gov and search                 submissions available to the public or
                                                  Capable of Operation under Severe                       for Docket ID NRC–2015–0048.                          entering the comment submissions into
                                                  Accident Conditions,’’ (JLD–ISG–2015–                      • NRC’s Agencywide Documents                       ADAMS.
                                                  01). This draft JLD–ISG would provide                   Access and Management System
                                                  guidance and clarification to assist                                                                          II. Background
                                                                                                          (ADAMS): You may access publicly-
                                                  nuclear power reactor licensees identify                available documents online in the NRC                    The NRC developed draft JLD–ISG–
                                                  measures needed to comply with Phase                    Library at http://www.nrc.gov/reading-                2015–01 to provide guidance and
                                                  2 requirements of the ‘‘Order Modifying                 rm/adams.html. To begin the search,                   clarification to assist nuclear power
                                                  Licenses with Regard to Reliable                        select ‘‘ADAMS Public Documents’’ and                 reactor licensees with the identification
                                                  Hardened Containment Vents Capable                      then select ‘‘Begin Web-based ADAMS                   of methods needed to comply with
                                                  of Operation Under Severe Accident                      Search.’’ For problems with ADAMS,                    Phase 2 requirements in Order EA–13–
                                                  Conditions,’’ (Order EA–13–109) to have                 please contact the NRC’s Public                       109, ‘‘Order Modifying Licenses with
                                                  either a vent path from the containment                 Document Room (PDR) reference staff at                Regard to Reliable Hardened
                                                  drywell or a strategy that makes it                     1–800–397–4209, 301–415–4737, or by                   Containment Vents Capable of
                                                  unlikely that venting would be needed                   email to pdr.resource@nrc.gov. The                    Operation under Severe Accident
                                                  from the drywell before alternate                       ADAMS accession number for each                       Conditions’’ (ADAMS Accession No.
                                                  reliable containment heat removal and                   document referenced in this notice (if                ML13130A067). The draft ISG would
                                                  pressure control is reestablished.                      that document is available in ADAMS)                  not be a substitute for the requirements
                                                  DATES: Submit comments by April 9,                      is provided the first time that a                     in Order EA–13–109, and compliance
                                                  2015. Comments received after this date                 document is referenced. The draft JLD–                with the ISG would not be a
                                                  will be considered, if it is practical to do            ISG–2015–01 is available in ADAMS                     requirement. This ISG is being issued in
                                                  so, but the Commission is able to ensure                under Accession No. ML15051A143.                      draft form for public comment to
                                                  consideration only for comments                         The ISG for complying with Phase 1                    involve the public in development of
                                                  received before this date.                              requirements of the order (JLD–ISG–                   the implementing guidance.
                                                  ADDRESSES: You may submit comment                       2013–02) was issued on November 14,                      The accident at the Fukushima Dai-
                                                  by any of the following methods (unless                 2013 (ADAMS Accession No.                             ichi nuclear power station reinforced
                                                  this document describes a different                     ML13304B836).                                         the importance of reliable operation of
                                                  method for submitting comments on a                        • NRC’s PDR: You may examine and                   containment vents for boiling-water
                                                  specific subject):                                      purchase copies of public documents at                reactor (BWR) plants with Mark I and
                                                     • Federal Rulemaking Web site: Go to                 the NRC’s PDR, Room O1–F21, One                       Mark II containments. As part of its
                                                  http://www.regulations.gov and search                   White Flint North, 11555 Rockville                    response to the lessons learned from the
mstockstill on DSK4VPTVN1PROD with NOTICES




                                                  for Docket ID NRC–2015–0048. Address                    Pike, Rockville, Maryland 20852.                      accident, on March 12, 2012, the NRC
                                                  questions about NRC dockets to Carol                       • NRC’s Interim Staff Guidance Web                 issued Order EA–12–050 (ADAMS
                                                  Gallagher; telephone: 301–415–3463;                     site: JLD–ISG documents are also                      Accession No. ML12056A043) requiring
                                                  email: Carol.Gallagher@nrc.gov. For                     available online under the ‘‘Japan                    licensees to upgrade or install a reliable
                                                  technical questions, contact the                        Lessons Learned’’ heading at http://                  hardened containment venting system
                                                  individual listed in the FOR FURTHER                    www.nrc.gov/reading-rm/doc-                           (HCVS) for Mark I and Mark II
                                                  INFORMATION CONTACT section of this                     collections/isg/japan-lessons-                        containments. The requirements in
                                                  document.                                               learned.html.                                         Order EA–12–050 for licensees with


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                                                  12650                         Federal Register / Vol. 80, No. 46 / Tuesday, March 10, 2015 / Notices

                                                  BWR plants with Mark I and Mark II                      050 requiring BWR licensees with Mark                 core damage and, if necessary, to
                                                  containments were intended to increase                  I and Mark II containments to upgrade                 provide venting capability during severe
                                                  the reliability of containment venting to               or replace the reliable hardened vents                accident conditions. Phase 2 involves
                                                  support decay heat removal from the                     required by Order EA–12–050 with a                    providing additional protection during
                                                  reactor core and provide protection                     containment venting system designed                   severe accident conditions through
                                                  against over-pressurization of the                      and installed to remain functional                    installation of a reliable, severe accident
                                                  primary containments. While                             during severe accident conditions, and                capable drywell vent system or the
                                                  developing the requirements for Order                   (2) develop a technical basis and                     development of a reliable containment
                                                  EA–12–050, the NRC acknowledged that                    rulemaking for filtering strategies with              venting strategy that makes it unlikely
                                                  questions remained about maintaining                    drywell filtration and severe accident                that a licensee would need to vent from
                                                  containment integrity and limiting the                  management of BWR Mark I and II                       the containment drywell during severe
                                                  release of radioactive materials if                     containments. The NRC subsequently                    accident conditions. For
                                                  licensees used the venting systems                      issued Order EA–13–109 to define                      implementation of Phase 1 order
                                                  during severe accident conditions.                      requirements and schedules for                        requirements, the NRC issued JLD–ISG–
                                                     The NRC staff presented the                          licensees for BWRs with Mark I and                    2013–02 on November 14, 2013 (78 FR
                                                  Commission with options to address                      Mark II containments to install severe                70356), which endorsed, with
                                                  these issues in SECY–12–0157,                           accident capable containment venting                  clarifications, the methodologies
                                                  ‘‘Consideration of Additional                           systems. The NRC staff also initiated                 described in the industry guidance
                                                  Requirements for Containment Venting                    development and evaluation of other                   document Nuclear Energy Institute
                                                  Systems for Boiling Water Reactors with                 possible regulatory actions identified in             (NEI) 13–02, Rev. 0 (ADAMS Accession
                                                  Mark I and Mark II Containments’’                       the Commission’s SRM for SECY–12–                     No. ML13316A853). As required by the
                                                  (issued November 26, 2012, ADAMS                        0157, including the development of a                  order, licensees submitted their site-
                                                  Accession No. ML12325A704). The                         technical basis in support of a                       specific overall integrated plans by June
                                                  options presented in SECY–12–0157                       Containment Protection and Release                    30, 2014. The NRC is currently
                                                  included continuing with the                            Reduction (CPRR) rulemaking.                          reviewing these plans and expects to
                                                  implementation of Order EA–12–050 for                      Order EA–13–109, in addition to                    complete those reviews by June 2015.
                                                  reliable hardened vents (Option 1);                     requiring a reliable HCVS to assist in
                                                                                                                                                                   The focus of this ISG is to provide
                                                  requiring licensees to upgrade or replace               preventing core damage when heat
                                                                                                                                                                guidance for Phase 2 requirements of
                                                  the reliable hardened vents required by                 removal capability is lost (the purpose
                                                  EA–12–050 with a containment venting                    of EA–12–050), will ensure that venting               the order. Some proposed approaches to
                                                  system designed and installed to remain                 functions are also available during                   implement Phase 2 requirements of the
                                                  functional during severe accident                       severe accident conditions. Severe                    order include the addition of water to
                                                  conditions (Option 2); requiring                        accident conditions include the elevated              the drywell during severe accident
                                                  licensees with BWR Mark I and Mark II                   temperatures, pressures, radiation                    conditions. Evaluations performed by
                                                  containments to install an engineered                   levels, and combustible gas                           the NRC and industry in conjunction
                                                  filtered containment venting system                     concentrations, such as hydrogen and                  with the CPRR rulemaking show that
                                                  intended to prevent the release of                      carbon monoxide, associated with                      water addition during severe accident
                                                  significant amounts of radioactive                      accidents involving extensive core                    conditions provides benefits that
                                                  material following the dominant severe                  damage, including accidents involving a               include reducing temperatures and
                                                  accident sequences (Option 3); and                      breach of the reactor vessel by molten                cooling molten core debris. In SECY–
                                                  pursuing development of requirements                    core debris. The safety improvements to               12–0157, the NRC discussed various
                                                  and technical acceptance criteria for                   Mark I and Mark II containment venting                risk assessments by the NRC and
                                                  performance-based confinement                           systems required by Order EA–13–109                   industry that have concluded that
                                                  strategies (Option 4). The NRC staff                    increase confidence in licensees’ ability             adding water to the drywell reduces the
                                                  provided an evaluation considering                      to maintain the containment function                  likelihood of release of radioactive
                                                  various quantitative analyses and                       following core damage events. Although                materials for those severe accident
                                                  qualitative factors related to the options              venting the containment during severe                 scenarios that involve fuel melting
                                                  and recommended the Commission                          accident conditions could result in the               through the reactor vessel. The water
                                                  approve Option 3 to require the                         release of radioactive materials, venting             added to the drywell cools the molten
                                                  installation of an engineered filtering                 could also prevent containment                        fuel and can arrest the melting fuel’s
                                                  system. One issue not specifically                      structural failures and gross penetration             progression and reduce the likelihood of
                                                  addressed within SECY–12–0157 was                       leakage due to overpressurization that                a loss of the containment function
                                                  the importance of water addition to cool                would hamper accident management                      through liner melt-through, containment
                                                  core debris as part of severe accident                  (e.g., continuing efforts to cool core                over-pressurization failure, and
                                                  management for BWR’s with Mark I and                    debris) and ultimately result in larger,              containment over-temperature failure.
                                                  II containments. The NRC staff                          uncontrolled releases of radioactive                  In addition to the benefits associated
                                                  acknowledged in SECY–12–0157 that in                    material.                                             with containment protection, recent
                                                  the longer-term rulemaking associated                      In recognition of the relative                     technical evaluations performed by both
                                                  with any of the options presented, the                  importance of venting capabilities from               the industry and the NRC indicate that
                                                  NRC could consider adding                               the wetwell and drywell, a phased                     including the capability of timely severe
                                                  requirements for the capability of core                 approach to implementation is being                   accident water addition (SAWA) results
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                                                  debris cooling during severe accident                   used to minimize delays in                            in a substantially lower drywell
                                                  scenarios.                                              implementing the requirements                         temperature for consideration in
                                                     In the staff requirements                            originally imposed by Order EA–12–                    designing the drywell vent. Therefore,
                                                  memorandum (SRM) for SECY–12–                           050. Phase 1 involves upgrading the                   SAWA will facilitate implementation of
                                                  0157, dated March 19, 2013 (ADAMS                       venting capabilities from the                         Phase 2 of Order EA–13–109 by
                                                  Accession No. ML13078A017), the                         containment wetwell to provide                        establishing the design conditions for a
                                                  Commission directed the staff to: (1)                   reliable, severe accident capable                     drywell vent and supporting severe
                                                  Issue a modification to Order EA–12–                    hardened vents to assist in preventing                accident water management (SAWM) for


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                                                                                Federal Register / Vol. 80, No. 46 / Tuesday, March 10, 2015 / Notices                                                  12651

                                                  licensees choosing to pursue that option                SECURITIES AND EXCHANGE                               A. Self-Regulatory Organization’s
                                                  as a strategy that makes it unlikely that               COMMISSION                                            Statement of the Purpose of, and
                                                  a licensee would need to vent from the                                                                        Statutory Basis for, the Proposed Rule
                                                  drywell.                                                [Release No. 34–74436; File No. SR–                   Change
                                                     On December 10, 2014, NEI submitted                  NYSEARCA–2015–09]                                     1. Purpose
                                                  NEI 13–02, ‘‘Industry Guidance for                                                                               The purpose of this filing is to modify
                                                  Compliance with Order EA–13–109,’’                      Self-Regulatory Organizations; NYSE
                                                                                                                                                                the Exchange’s Limit on Fees on
                                                  Rev. 0E2 (ADAMS Accession No.                           Arca, Inc.; Notice of Filing and
                                                                                                                                                                Options Strategy Executions (‘‘Strategy
                                                  ML1434A374) to assist nuclear power                     Immediate Effectiveness of Proposed                   Cap’’). Currently, the Exchange imposes
                                                  licensees with the identification of                    Rule Change Amending the NYSE Arca                    a Strategy Cap of $750 on transaction
                                                  measures needed to comply with the                      Options Fee Schedule Relating to                      fees for certain Strategy Executions
                                                  requirements of Order EA–13–109                         Strategy Executions                                   executed in standard option contracts
                                                  regarding reliable hardened                             March 4, 2015.
                                                                                                                                                                on the same trading day in the same
                                                  containment vents capable of operation                                                                        option class. The Exchange is proposing
                                                  under severe accident conditions. The                      Pursuant to Section 19(b)(1) 1 of the              to lower the $750 Strategy Cap to $700.4
                                                  NEI document includes guidance for                      Securities Exchange Act of 1934 (the                  The Exchange proposes to implement
                                                  implementing order requirements for                     ‘‘Act’’) 2 and Rule 19b–4 thereunder,3                the $700 Strategy Cap on March 1, 2015.
                                                  both Phase 1 and Phase 2, including the                 notice is hereby given that, on February                 Strategy Executions that are eligible
                                                  industry’s proposed approach to use the                 24, 2015, NYSE Arca, Inc. (the                        for the Strategy Cap would continue to
                                                                                                          ‘‘Exchange’’ or ‘‘NYSE Arca’’) filed with             be (a) reversals and conversions, (b) box
                                                  SAWA and SAWM strategies to control
                                                                                                          the Securities and Exchange                           spreads, (c) short stock interest spreads,
                                                  the water levels in the suppression pool
                                                                                                          Commission (the ‘‘Commission’’) the                   (d) merger spreads, and (e) jelly rolls. As
                                                  and maintain capabilities to address                                                                          is the case today, Royalty fees associated
                                                  over-pressure conditions without a                      proposed rule change as described in
                                                                                                          Items I, II, and III below, which Items               with Strategy Executions on Index and
                                                  severe accident drywell vent. As                                                                              Exchange Traded Funds would not be
                                                  described in the draft ISG, some issues                 have been prepared by the self-
                                                                                                                                                                included in the calculation of the
                                                  remain the subject of ongoing                           regulatory organization. The
                                                                                                                                                                Strategy Cap, but would be passed
                                                  discussions as part of finalizing the                   Commission is publishing this notice to
                                                                                                                                                                through to trading participants on the
                                                  guidance. These include: (1)                            solicit comments on the proposed rule                 Strategy Executions on a pro-rata basis.
                                                  Availability of power and functional                    change from interested persons.                       Similarly, manual Broker Dealer and
                                                  requirements for the SAWA-related                       I. Self-Regulatory Organization’s                     Firm Proprietary Strategy trades that do
                                                  installed and portable equipment, (2)                   Statement of the Terms of Substance of                not reach the $700 Strategy Cap would
                                                  duration of time for preservation of the                the Proposed Rule Change                              continue to be billed at $0.25 per
                                                  wetwell vent for the SAWM strategy,                                                                           contract.
                                                  and (3) alternate control of containment                  The Exchange proposes to amend the                     The use of these Strategy Executions
                                                  conditions during recovery from the                     NYSE Arca Options Fee Schedule (‘‘Fee                 benefits all market participants by
                                                  severe accident. The NRC intends to                     Schedule’’) relating to Strategy                      increasing liquidity in general and
                                                  continue discussions with stakeholders                  Executions. The Exchange proposes to                  allowing significant and complex
                                                  prior to finalizing the ISG for Phase 2 of              implement the change on March 1,                      trading interest to be brought together to
                                                                                                          2015. The text of the proposed rule                   enhance liquidity. By encouraging this
                                                  the order and endorsing, with
                                                                                                          change is available on the Exchange’s                 type of business on the Exchange, the
                                                  clarifications and exceptions if                                                                              increased liquidity benefits all market
                                                  necessary, the methodologies described                  Web site at www.nyse.com, at the
                                                                                                                                                                participants. The Exchange believes the
                                                  in the industry guidance document NEI                   principal office of the Exchange, and at              proposed change would continue to
                                                  13–02, Rev. 0E2.                                        the Commission’s Public Reference                     incentivize market participants to trade
                                                                                                          Room.                                                 on the Exchange by capping option
                                                    Dated at Rockville, Maryland, this 2nd day
                                                  of March 2015.                                          II. Self-Regulatory Organization’s                    transaction charges related to various
                                                    For the Nuclear Regulatory Commission.                Statement of the Purpose of, and                      Strategy Executions.
                                                  Jack R. Davis,                                          Statutory Basis for, the Proposed Rule                2. Statutory Basis
                                                  Director, Japan Lessons-Learned Division,               Change                                                   The Exchange believes that the
                                                  Office of Nuclear Reactor Regulation.                                                                         proposed rule change is consistent with
                                                                                                            In its filing with the Commission, the
                                                  [FR Doc. 2015–05436 Filed 3–9–15; 8:45 am]
                                                                                                          self-regulatory organization included                 Section 6(b) of the Act,5 in general, and
                                                  BILLING CODE 7590–01–P
                                                                                                          statements concerning the purpose of,                 furthers the objectives of Sections
                                                                                                                                                                6(b)(4) and (5) of the Act,6 in particular,
                                                                                                          and basis for, the proposed rule change
                                                                                                                                                                because it would provide for the
                                                                                                          and discussed any comments it received
                                                                                                                                                                equitable allocation of reasonable dues,
                                                                                                          on the proposed rule change. The text                 fees, and other charges among its
                                                                                                          of those statements may be examined at                members, issuers and other persons
                                                                                                          the places specified in Item IV below.
                                                                                                          The Exchange has prepared summaries,                     4 Transaction fees on Strategy Executions are
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                                                                                                          set forth in sections A, B, and C below,              further capped at $25,000 per month per initiating
                                                                                                          of the most significant parts of such                 firm. The Exchange is not proposing to modify this
                                                                                                                                                                $25,000 monthly cap. Mini options are excluded
                                                                                                          statements.                                           from the Strategy Cap. See Fee Schedule, available
                                                                                                                                                                at, https://www.nyse.com/publicdocs/nyse/markets/
                                                                                                                                                                arca-options/NYSE_Arca_Options_Fee_
                                                                                                            1 15 U.S.C.78s(b)(1).                               Schedule.pdf.
                                                                                                            2 15 U.S.C. 78a.                                       5 15 U.S.C. 78f(b).
                                                                                                            3 17 CFR 240.19b–4.                                    6 15 U.S.C. 78f(b)(4) and (5).




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Document Created: 2018-02-21 09:35:01
Document Modified: 2018-02-21 09:35:01
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionDraft interim staff guidance; request for comment.
DatesSubmit comments by April 9, 2015. Comments received after this date will be considered, if it is practical to do so, but the Commission is able to ensure consideration only for comments received before this date.
ContactRajender Auluck, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1025; email: [email protected]
FR Citation80 FR 12649 

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