Source: https://www.federalregister.gov/documents/2013/12/26/2013-30843/applications-and-amendments-to-facility-operating-licenses-and-combined-licenses-involving-proposed
Timestamp: 2019-04-26 03:45:52
Document Index: 284911133

Matched Legal Cases: ['§\u20092', 'art 2', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50']

A Notice by the Nuclear Regulatory Commission on 12/26/2013
Comments must be filed by January 27, 2014. A request for a hearing or petition for leave to intervene must be filed by February 24, 2014. Any potential party, as defined in Sec. 2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who believes access to SUNSI is necessary to respond to this notice must request document access by January 6, 2014.
78 FR 78402
78402-78411 (10 pages)
NRC-2013-0272
2013-30843
Florida Power and Light Company, et al., Docket Nos. 50-335 and 50-389, St. Lucie Plant (PSL), Units 1 and 2, St. Lucie County, Florida
Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit 2, Darlington County, South Carolina
https://www.federalregister.gov/d/2013-30843 https://www.federalregister.gov/d/2013-30843
Comments must be filed by January 27, 2014. A request for a hearing or petition for leave to intervene must be filed by February 24, 2014. Any potential party, as defined in § 2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who believes access to SUNSI is necessary to respond to this notice must request document access by January 6, 2014.
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0272. Address questions about NRC dockets to Carol Gallagher; telephone: 301-287-3422; email: Carol.Gallagher@nrc.gov.
Please refer to Docket ID NRC-2013-0272 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods:
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 document (if that document is available in ADAMS) is provided the first time that a document is referenced.
Please include Docket ID NRC-2013-0272 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. Start Printed Page 78403The 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.
Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license or combined license. Requests for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's “Agency Rules of Practice and Procedure” in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The NRC's regulations are accessible electronically from the NRC Library on the NRC Web site at http://www.nrc.gov/​reading-rm/​doc-collections/​cfr/​. If a request for a hearing or petition for leave to intervene is filed within 60 days, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards Start Printed Page 78404consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, then any hearing held would take place before the issuance of any amendment.
Information about applying for a digital ID certificate is available on the NRC's public Web site at http://www.nrc.gov/​site-help/​e-submittals/​apply-certificates.html. System requirements for accessing the E-Submittal server are detailed in the NRC's “Guidance for Electronic Submission,” which is available on the agency's public Web site at http://www.nrc.gov/​site-help/​e-submittals.html. Participants may attempt to use other software not listed on the Web site, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC's Meta System Help Desk will not be able to offer assistance in using unlisted software.
Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC's guidance available on the NRC's public Web site at http://www.nrc.gov/​site-help/​e-submittals.html. A filing is considered complete at the time the documents are submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system.
Petitions for leave to intervene must be filed no later than 60 days from the date of publication of this notice. Requests for hearing, petitions for leave to intervene, and motions for leave to Start Printed Page 78405file new or amended contentions that are filed after the 60-day deadline will not be entertained absent a determination by the presiding officer that the filing demonstrates good cause by satisfying the three factors in 10 CFR 2.309(c)(1)(i)-(iii).
Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant (HBRSEP), Unit 2, Darlington County, South Carolina
Date of amendment request: September 16, 2013. A publicly available version is in ADAMS under Accession Nos. ML13267A211 and ML13267A212.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The license amendment request (LAR) proposes to transition the fire protection licensing basis from 10 CFR 50.48(b) and (c), National Fire Protection Association (NFPA) 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,” 2001 Edition. This LAR requests that the NRC review and approve for adoption of a new fire protection licensing basis that complies with the requirements in 10 CFR 50.48(a) and (c), the guidance in Regulatory Guide (RG) 1.205, Revision 1, “Risk-Informed Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants,” and NFPA 805. The LAR also follows the applicable guidance in Nuclear Energy Institute 04-02, Revision 2.
Operation of the HBRSEP in accordance with the proposed amendment does not result in a significant increase in the probability or consequences of accidents previously evaluated. The proposed amendment does not affect accident initiators or precursors as described in the HBRSEP Updated Final Safety Analysis Report (UFSAR), nor does it adversely alter design assumptions, conditions, or configurations of the facility, and it does not adversely impact the ability of structures, systems, or components (SSCs) to perform their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed changes do not affect the way in which safety-related systems perform their functions as required by the accident analysis. The SSCs required to safely shut down the reactor and to maintain it in a safe shutdown condition will remain capable of performing their design functions.
The purpose of this amendment is to permit HBRSEP to adopt a new risk-informed, performance-based fire protection licensing basis that complies with the requirements in 10 CFR 50.48(a) and (c), as well as the guidance contained in RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection requirements that are an acceptable alternative to the 10 CFR Part 50, Appendix R, fire protection features (69 FR 33536; June 16, 2004). Engineering analyses, which may include engineering evaluations, probabilistic risk assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based requirements of NFPA 805 have been met.
NFPA 805, taken as a whole, provides an acceptable alternative for satisfying General Design Criterion 3 (GDC 3) of Appendix A to 10 CFR Part 50, meets the underlying intent of the NRC's existing fire protection regulations and guidance, and achieves defense-in-depth along with the goals, performance objectives, and performance criteria specified in NFPA 805, Chapter 1. In addition, if there are any increases in core damage frequency (CDF) or risk as a result of the transition to NFPA 805, the increase will be small, governed by the delta risk requirements of NFPA 805, and consistent with the intent of the Commission's Safety Goal Policy.
Based on the above, the implementation of this amendment to transition the Fire Protection Plan at HBRSEP to one based on NFPA 805, in accordance with 10 CFR 50.48(c), does not result in a significant increase in the probability of any accident previously evaluated.
In addition, all equipment required to mitigate an accident remains capable of performing the assumed function. Therefore, the consequences of any accident previously evaluated are not significantly increased with the implementation of this amendment.
Operation of HBRSEP in accordance with the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. Any scenario or previously analyzed accident with offsite dose consequences was included in the evaluation of design basis accidents (DBA) documented in the UFSAR as a part of the transition to NFPA 805. The proposed amendment does not impact these accident analyses. The proposed change does not alter the requirements or functions for systems required during accident conditions, nor does it alter the required mitigation capability of the fire protection program, or its functioning during accident conditions as assumed in the licensing basis analyses and/or DBA radiological consequences evaluations.
The proposed amendment does not adversely affect accident initiators nor alter design assumptions, or conditions of the facility. The proposed amendment does not adversely affect the ability of SSCs to perform their design function. SSCs required to maintain the unit in a safe and stable condition remain capable of performing their design functions.
The purpose of the proposed amendment is to permit HBRSEP to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. As indicated in the Statements of Consideration, the NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR Part 50, Appendix R fire protection features.
The requirements in NFPA 805 address only fire protection and the impacts of fire effects on the plant have been evaluated. The proposed fire protection program changes do not involve new failure mechanisms or malfunctions that could initiate a new or different kind of accident beyond those already analyzed in the UFSAR. Based on this, as well as the discussion above, the implementation of this amendment to transition the Fire Protection Plan at HBRSEP to one based on NFPA 805, in accordance with 10 CFR 50.48(c), does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Operation of HBRSEP in accordance with the proposed amendment does not involve a significant reduction in a margin of safety. The transition to a new risk-informed, performance-based fire protection licensing basis that complies with the requirements in 10 CFR 50.48(a) and (c) does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed amendment does not adversely affect existing plant safety margins or the reliability of equipment assumed in the UFSAR to mitigate accidents. The proposed change does not adversely impact Start Printed Page 78406systems that respond to safely shut down the plant and maintain the plant in a safe shutdown condition. In addition, the proposed amendment will not result in plant operation in a configuration outside the design basis for an unacceptable period of time without implementation of appropriate compensatory measures. The purpose of the proposed amendment is to permit HBRSEP to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR Part 50, Appendix R required fire protection features (69 FR 33536, June 16, 2004).
The risk evaluations for plant changes, in part as they relate to the potential for reducing a safety margin, were measured quantitatively for acceptability using the delta risk guidance contained in RG 1.205. Engineering analyses, which may include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based methods of NFPA 805 do not result in a significant reduction in the margin of safety.
As such, the proposed changes are evaluated to ensure that risk and safety margins are kept within acceptable limits. Based on the above, the implementation of this amendment to transition the Fire Protection Plan at HBRSEP to one based on NFPA 805, in accordance with 10 CFR 50.48(c), will not significantly reduce a margin of safety.
Attorney for licensee: Lara S. Nichols, Deputy General Counsel, Duke Energy Corporation, 550 South Tyron Street, Mail Code DEC45A Charlotte NC 28202.
Date of application for amendments: June 10, 2013. A publicly available version is in ADAMS under Accession No. ML13175A109.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendments would revise the Technical Specifications (TSs) to: (1) Increase the allowable as-found safety relief valve (SRV) and safety valve (SV) lift setpoint tolerance from ±1% to ±3%; (2) increase the required number of operable SRVs and SVs from 11 to 12; and (3) increase the Standby Liquid Control (SLC) System pump discharge pressure from 1255 pounds per square inch gauge (psig) to 1275 psig.
The proposed changes: (1) Revise Technical Specification (TS) Surveillance Requirement (SR) 3.4.3.1 to increase the allowable as-found Safety Relief Valve (SRV) and Safety Valve (SV) lift setpoint tolerance from ±1% to ±3%; (2) revise TS Limiting Conditions for Operation (LCO) 3.4.3 to increase the required number of operable SRVs and SVs from 11 to 12; and; (3) revise TS SR 3.1.7.8 to increase the SLC System pump discharge pressure from 1255 psig to 1275 psig. As analyzed in Attachment 3 [to the application dated June 10, 2013] (“Peach Bottom Atomic Power Station Units 2 and 3 Safety Valve Setpoint Tolerance Increase Safety Analysis Report,” NEDC-33533P, Revision 1, dated May 2013), increasing the SRV/SV tolerance results in a change to the TS requirements for the number of SRVs/SVs required to be operable. However, this change does not alter the manner in which the valves are operated. Consistent with current TS requirements, the proposed change continues to require that the SRVs/SVs be adjusted to within ±1% of their nominal lift setpoints following testing. Since the proposed change does not alter the manner in which the valves are operated, there is no significant impact on reactor operation.
The proposed change does not involve a physical change to the valves, nor does it change the safety function of the valves. The proposed TS revision involves no significant changes to the operation of any systems or components in normal or accident operating conditions and no changes to existing structures, systems, or components, with the exception of the SLC System pump discharge pressure. The proposed change to increase the SLC System pump pressure will ensure that the requirements of 10 CFR 50.62, “Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants,” continue to be met. The SLC System is not an initiator to an accident; rather, the SLC System is used to mitigate an ATWS event.
Therefore, these changes will not increase the probability of an accident previously evaluated.
Generic considerations related to the change in setpoint tolerance were addressed in NEDC-31753P, “BWROG [Boiling Water Reactor Owners Group] In-Service Pressure Relief Technical Specification Revision Licensing Topical Report,” and were reviewed and approved by the USNRC in a safety evaluation dated March 8, 1993. General Electric Hitachi Nuclear Energy (GEH) has completed plant-specific analyses to assess the impact of the setpoint tolerance increase on Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The plant specific evaluations, required by the USNRC's safety evaluation and performed to support this proposed change, show that there is no change to the design core thermal limits and adequate margin to the reactor vessel pressure limits using a ±3% lift setpoint tolerance. These analyses also show that operation of Emergency Core Cooling Systems is not affected, and the containment response following a Loss-of-Coolant Accident (LOCA) is acceptable. The plant systems associated with these proposed changes are capable of meeting applicable design basis requirements and retain the capability to mitigate the consequences of accidents described in the Updated Final Safety Analysis Report (UFSAR).
The proposed changes: (1) Revise TS SR 3.4.3.1 to increase the allowable as-found SRV and SV lift setpoint tolerance from ±1% to ±3%; (2) revise TS Limiting Conditions for Operation (LCO) 3.4.3 to increase the required number of operable SRVs and SVs from 11 to 12; and; (3) revise TS SR 3.1.7.8 to increase the SLC System pump discharge pressure from 1255 psig to 1275 psig. The proposed change to increase the SLC System pump pressure will ensure that the requirements of 10 CFR 50.62 continue to be met. The proposed change to increase the SRV/SV tolerance was developed in accordance with the provisions contained in the USNRC safety evaluation for NEDC-31753P. Additionally, Attachment 3 [to the application dated June 10, 2013] analyzes the tolerance increase which results in the increase in the required number of SRVs/SVs necessary to remain operable. SRVs/SVs installed in the plant following testing or refurbishment will continue to meet the current tolerance acceptance criteria of ±1% of the nominal setpoint. The proposed change does not affect the manner in which the overpressure protection system is operated; therefore, there are no new failure mechanisms for the overpressure protection system.
The proposed change does not involve physical changes to the valves, nor does it change the safety function of the valves. There is no alteration to the parameters within which the plant is normally operated. As a result, no new failure modes are being introduced.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.Start Printed Page 78407
The margin of safety is established through the design of the plant structures, systems, and components, the parameters within which the plant is operated, and the establishment of the setpoints for the actuation of equipment relied upon to respond to an event. The proposed change does not modify the safety limits or setpoints at which protective actions are initiated, and does not change the requirements governing operation or availability of safety equipment assumed to operate to preserve the margin of safety. Additionally, this change will ensure that the reactor steam dome pressure shall be ≤1325 psig as discussed in Safety Limit [SL] 2.1.2 (“Reactor Coolant System Pressure SL”). The proposed change to increase the SLC System pump discharge pressure will ensure that the requirements of 10 CFR 50.62 continue to be met.
Date of amendment request: March 22, 2013, as supplemented by letter dated June 14, 2013. Publicly available versions are in ADAMS under Accession Nos. ML13088A173 and ML13170A156, respectively.
Operation of PSL in accordance with the proposed amendment does not increase the probability or consequences of accidents previously evaluated. The Updated Final Safety Analysis Report (UFSAR) documents the analyses of design basis accidents (DBAs) at PSL. The proposed amendment does not adversely affect accident initiators nor alter design assumptions, conditions, or configurations of the facility and does not adversely affect the ability of structures, systems, and components (SSCs) to perform their design function. SSCs required to safely shut down the reactor and to maintain it in a safe shutdown (SSD) condition will remain capable of performing their design functions.
The purpose of this amendment is to permit PSL to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. The NRC considers that National Fire Protection Association (NFPA) 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR Part 50, Appendix R fire protection features (69 FR 33536; June 16, 2004). Engineering analyses, in accordance with NFPA 805, have been performed to demonstrate that the risk-informed, performance-based (RI-PB) requirements per NFPA 805 have been met.
NFPA 805, taken as a whole, provides an acceptable alternative to 10 CFR 50.48(b) and satisfies 10 CFR 50.48(a) and General Design Criterion (GDC) 3 of Appendix A to 10 CFR Part 50 and meets the underlying intent of the NRC's existing fire protection regulations and guidance, achieves defense-in-depth (DID) and the goals, performance objectives, and performance criteria specified in Chapter 1 of the standard. The small increase in net change in core damage frequency associated with this License Amendment Request (LAR) submittal is consistent with the Commission's Safety Goal Policy. Additionally, 10 CFR 50.48(c) allows self-approval of fire protection program changes post-transition. If there are any increases post-transition in core damage frequency (CDF) or risk, the increase will be small and consistent with the intent of the Commission's Safety Goal Policy.
Therefore, the consequences of any accident previously evaluated are not significantly increased with the implementation of this amendment.
Operation of PSL in accordance with the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. Any scenario or previously analyzed accident with offsite dose was included in the evaluation of DBAs documented in the UFSAR. The proposed change does not alter the requirements or function for systems required during accident conditions. Implementation of the new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205 will not result in new or different accidents.
The purpose of this amendment is to permit PSL to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR Part 50, Appendix R fire protection features (69 FR 33536; June 16, 2004).
Operation of PSL in accordance with the proposed amendment does not involve a significant reduction in the margin of safety. The proposed amendment does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed amendment does not Start Printed Page 78408adversely affect existing plant safety margins or the reliability of equipment assumed to mitigate accidents in the UFSAR. The proposed amendment does not adversely affect the ability of SSCs to perform their design function. SSCs required to safely shut down the reactor and to maintain it in a safe shutdown condition remain capable of performing their design function.
The purpose of this amendment is to permit PSL to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR Part 50, Appendix R fire protection features (69 FR 33536; June 16, 2004). Engineering analyses, which may include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based methods do not result in a significant reduction in the margin of safety.
Based on this, the implementation of this amendment does not significantly reduce the margin of safety. The proposed changes are evaluated to ensure that the risk and safety margins are kept within acceptable limits. Therefore, the transition does not involve a significant reduction in the margin of safety.
NFPA 805 continues to protect public health and safety and the common defense and security because the overall approach of NFPA 805 is consistent with the key principles for evaluating license basis changes, as described in RG 1.174, is consistent with the defense-in-depth (DID) philosophy, and maintains sufficient safety margins.
Margins previously established for the PSL program in accordance with 10 CFR 50.48(b) and Appendix R to 10 CFR Part 50 are not significantly reduced.
Therefore, this LAR does not result in a reduction in a margin of safety.
Attorney for licensee: William S. Blair, Managing Attorney—Nuclear, Florida Power & Light, P.O. Box 14000, Juno Beach, Florida 33408-0420.
Date of amendment request: June 26, 2013, as supplemented by letter dated October 3, 2013. Publicly available versions are in ADAMS under Accession Nos. ML131960159 and ML13277A457, respectively.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI) (security-related). The amendment would permit the Pacific Gas and Electric Company (the licensee) to adopt a new fire protection licensing basis based on National Fire Protection Association (NFPA) Standard 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants,” 2001 Edition, at Diablo Canyon Power Plant, Units 1 and 2, that complies with the requirements of 10 CFR 50.48(a) and (c) and the guidance in Regulatory Guide (RG) 1.205, of Revision 1 “Risk Informed Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants,” December 2009.
1. Does the transition to NFPA 805 involve a significant increase in the probability or consequences of an accident previously evaluated?
Operation of Diablo Canyon Power Plant (DCPP) in accordance with the proposed amendment does not increase the probability or consequences of accidents previously evaluated. Engineering analyses, which may include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based requirements of NFPA 805 have been satisfied. The Updated Final Safety Analysis Report (UFSAR) documents the analyses of design basis accidents (DBA) at DCPP. The proposed amendment does not adversely affect accident initiators nor alter design assumptions, conditions, or configurations of the facility and does not adversely affect the ability of structures, systems, or components (SSCs) to perform their design functions. SSCs required to safely shutdown the reactor and to maintain it in a safe shutdown (SSD) condition have been identified and remain available to perform their design functions.
The purpose of the proposed amendment is to permit PG&E to adopt a new Fire Protection (FP) licensing basis which complies with the requirements of 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of Regulatory Guide (RG) 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify FP requirements that are an acceptable alternative to the 10 CFR Part 50, Appendix R required fire protection features (69 FR 33536; June 16, 2004). Engineering analyses, in accordance with NFPA 805, have been performed to demonstrate that the deterministic and/or risk-informed, performance based (RI-PB) requirements of NFPA 805 have been met.
NFPA 805, taken as a whole, provides an acceptable alternative for satisfying General Design Criterion 3 (GDC 3) of Appendix A to 10 CFR Part 50, meets the underlying intent of the NRC's existing FP regulations and guidance, and achieves defense-in-depth (DID) and safety margin, and the goals, performance objectives, and performance criteria specified in Chapter 1 of the standard and, if there are any increases in core damage frequency (CDF) or risk, the increase will be small and consistent with the intent of the Commission's Safety Goal Policy.
Based on this, the implementation of the proposed amendment does not increase the probability of any accident previously evaluated. Equipment required to mitigate an accident remains capable of performing the design function. The proposed amendment will not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of any accident previously evaluated. The applicable radiological dose criteria will continue to be met. The consequences of any accident previously evaluated are not increased with the implementation of the proposed amendment.
Therefore, the transition to NFPA 805 will not involve a significant increase in the probability or consequences of an accident previously evaluated.
2. Does the transition to NFPA 805 create the possibility of a new or different kind of accident from any kind of accident previously evaluated?
Operation of DCPP in accordance with the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. Any scenario or previously analyzed accident with off-site dose was included in the evaluation of DBAs documented in the UFSAR. The proposed change does not alter the requirements or function for systems required during accident conditions. Implementation of the new FP licensing basis which complies with the requirements of 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205 will not result in new or different accidents.
The proposed amendment does not adversely affect accident initiators nor alter design assumptions, conditions, or configurations of the facility. The proposed amendment does not adversely affect the ability of SSCs to perform their design function. SSCs required to safely shutdown the reactor and maintain it in a SSD condition remain capable of performing their design functions.
The purpose of the proposed amendment is to permit PG&E to adopt a new FP licensing basis which complies with the requirements of 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify FP requirements that are an acceptable alternative to the 10 CFR Part 50, Appendix R required FP features (69 FR 33536; June 16, 2004). Engineering analyses, which may Start Printed Page 78409include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance based requirements of NFPA 805 have been met.
The requirements of NFPA 805 address only FP and the impacts of fire on the plant that have previously been evaluated. Based on this, the implementation of the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this amendment. There will be no adverse effect or challenges imposed on any safety-related system as a result of this amendment. Therefore, the probability of a new or different kind of accident from those previously evaluated is not credible with the implementation of this amendment.
Therefore, the transition to NFPA 805 does not create the possibility of a new or different kind of accident from any kind of accident previously evaluated.
3. Does the transition to NFPA 805 involve a significant reduction in the margin of safety?
Operation of DCPP in accordance with the proposed amendment does not involve a significant reduction in the margin of safety. The risk evaluation of plant changes, as appropriate, were measured quantitatively for acceptability using the ΔCDF and ΔLERF [large early release frequency] criteria from Section 5.3.5 of NEI 04-02, Revision 2, and RG 1.205, Revision 1. The proposed amendment does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. The UFSAR acceptance criteria are not affected by this change. The proposed amendment does not adversely affect existing plant safety margins or the reliability of equipment assumed to mitigate accidents in the UFSAR. This amendment does not adversely affect the ability of SSCs to perform their design function. SSCs required to safely shutdown the reactor and to maintain it in a SSD condition remain capable of performing their design functions.
The purpose of the proposed amendment is to permit PG&E to adopt a new FP licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Revision 1 of RG 1.205. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify FP requirements that are an acceptable alternative to the 10 CFR Part 50, Appendix R required FP features (69 FR 33536; June 16, 2004). Engineering analyses, in accordance with NFPA 805, have been performed to demonstrate that the RI-PB requirements per NFPA 805 have been met.
Therefore, the transition to NFPA 805 does not involve a significant reduction in the margin of safety.
(3) The identity of the individual or entity requesting access to SUNSI and the requestor's basis for the need for the information in order to meaningfully participate in this adjudicatory proceeding. In particular, the request must explain why publicly-available versions of the information requested would not be sufficient to provide the basis and specificity for a proffered contention.
F. Filing of Contentions. Any contentions in these proceedings that are based upon the information received Start Printed Page 78410as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after the requestor is granted access to that information. However, if more than 25 days remain between the date the petitioner is granted access to the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline.
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