ML083470091
| ML083470091 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/03/2009 |
| From: | Kalyanam N Plant Licensing Branch IV |
| To: | Ridenoure R Southern California Edison Co |
| Kalyanam N, NRR/DORL/LPL4, 415-1480 | |
| References | |
| TAC MD9162, TAC MD9163, TSTF-487, Rev 1 | |
| Download: ML083470091 (26) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 3, 2009 Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 ISSUANCE OF AMENDMENTS RE: IMPROVEMENT TO ADOPT TSTF-487, REVISION 1, "RELOCATE DNB PARAMETERS TO THE COLR" (TAC NOS. MD9162 AND MD9163)
Dear Mr. Ridenoure:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 219 to Facility Operating License No. NPF-10 and Amendment No. 212 to Facility Operating License No. NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS, Units 2 and 3),
respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 27, 2008.
The amendments allow SONGS, Units 2 and 3 to replace the departure from nucleate boiling (DNB) numeric limits in the TSs with references to the core operating limits report (COLR). The changes are consistent with NRC-approved Industry Technical Specification Task Force (TSTF)
Standard Technical Specification Change Traveler, TSTF-487, Revision 1, "Relocate DNB Parameters to the COLR." The availability of this TS improvement was announced in the Federal Register on June 5, 2007 (72 FR 31108) as part of the consolidated line item improvement process.
R. T. Ridenoure
- 2 A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, ~~
V N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosures:
- 1. Amendment No. 219 to NPF-10
- 2. Amendment No. 212 to NPF-15
- 3. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No. NPF-10
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al.
(SCE or the licensee), dated June 27, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 219, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i ael T. Markley, Chief ant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-10 and Technical Specifications Date of Issuance:
February 3, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 219 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Facility Operating License No. NPF-10 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License REMOVE INSERT -3 Technical Specifications REMOVE INSERT 3.4-1 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 5.0-26 5.0-26 5.0-27 5.0-27
-3 (3)
SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
SCE, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 2 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is sUbject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 219,are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 219
3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits LCO 3.4.1 RCS parameters for pressurizer pressure. cold leg temperature. and RCS total flow rate shall be within the limits specified in the COLR.
APPLICABILITY:
MODE 1.
NOTE-----------------------
Pressurizer pressure limit does not apply during:
- a.
THERMAL POWER ramp> 5% RTP per minute; or
- b.
THERMAL POWER step> 10% RTP.
ACTIONS CONDITION REQU IRED ACTI ON COMPLETION TIME A.
Pressurizer pressure or Res flow rate not with-in l"imits.
A.1 Restore parameter(s) to within limit.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (continued)
SAN ONOFRE--UNIT 2 3.4-1 Amendment No. 219
3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action and associated Completion Time of Condition A not met.
B.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.
RCS cold leg tem~erature not wit in 1imits.
C.1 Restore cold leg tem~erature to wit in limits.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D.
Required Action and associated Completion Time of Condition C not met.
D.1 Reduce THERMAL POWER to
~ 30% RTP.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SR SR 3.4.1.1 3.4.1.2 SURVEILLANCE Verify pressurizer pressure is within the limits specified in the COLR.
Verify RCS cold leg temperature is within the limits specified in the COLR.
FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours (continued)
SAN ONOFRE--UNIT 2 3.4-2 Amendment No. 219
3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits ACTIONS (continued)
SURVEILLANCE
~-----~--------------------NOTE--------------------------
Required to be met in MODE 1 with all RCPs running.
SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to the limits specified in the COLR.
FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SAN ONOFRE--UNIT 2 3.4-3 Amendment No. 219
Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Deleted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1.
Specification 3.1.1, IISHUTDOWN MARGIN (SDM) - T
>2000F; II avg
- 2.
Specifi cati on 3.1.2, IISHUTDOWNMARGIN (SDM) - Tavg s200°F; "
- 3.
Specifi cati on 3.1.4, "Moderator Temperature Coefficient; II
- 4.
Specification 3.1.5, IIControl Element Assembly (CEA)
Alignment;II
- 5.
Specification 3.1.7, IIRegulating CEA Insertion Limits;"
- 6.
Specification 3.1.8, "Part Length Control Element Assembly Insertion Limits; II
- 7.
Specification 3.2.1, "Linear Heat Rate;~
- 8.
Specification 3.2.4, IIDeparture From Nucleate Boiling Ratio;1I
- 9.
Specification 3.2.5, "Axial Shape Index;1I
- 10.
Specification 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits;
- 11.
Specification 3.9.1, "Boron Concentration."
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
(continued)
SAN ONOFRE--UNIT 2 5.0-26 Amendment No. 219
Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)
(continued)
- 1.
CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"
- 2.
CENPD-137P. IICalculative Methods for the C-E Small Break LOCA Evaluation Model"
- 3.
CEN-356(V)-P-A. "Modified Statistical Combination of Uncertainties"
- 4.
SCE-9801-P-A. "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"
- 5.
CEN-635(S). "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodologyll
- 6.
Letter. dated May 16. 1986. G. W. Knighton (NRC) to K.
P. Baskin (SCE). JlIssuance of Amendment No. 47 to Facility Operating License NPF-I0 and Amendment No. 36 to Facility Operating License NPF-15." San Onofre Nuclear Generating Station Units 2 and 3 (Cycl~ 3 SER)
- 7.
Letter. dated January 9. 1985. G. W. Knighton (NRC) to K. P. Baskin. "Issuance of Amendment No. 30 to Facility Operating License NPF-IO and Amendment No. 19 to Facility Operating License NPF-15." San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)
- a.
"Implementation of ZIRLO' Cladding Material in CE Nuclear Power Fuel Assembly Designs.
1I CENPD-404-P-A
- c.
The core operating limits shall be determined assuming operation at RATED THERMAL POWER such that all applicable limits (e.g ** fuel thermal-mechanical limits. core thermal hydraulic limits. Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM. transient analysis limits. and accident analysis limits) of the safety analysis are met.
- d.
The COLR. including any mid-cycle revisions or supplements.
shall be provided upon issuance for each reload cycle to the NRC.
5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heatup. cool down, low temperature operation. criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
(continued)
SAN ONOFRE--UNIT 2 5.0-27 Amendment No. 219
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. NPF-15
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al.
(SCE or the licensee), dated June 27,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pUblic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 212, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k~t. 7/Jpfe aael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-15 and Technical Specifications Date of Issuance: February 3, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 212 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Facility Operating License No. NPF-15 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License REMOVE INSERT -3 Technical Specifications REMOVE INSERT 3.4-1 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 5.0-26 5.0-26 5.0-27 5.0-27
-3 (3)
SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 3 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.
C.
This license shall be deemed to contain and is sUbject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 212,are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 212
3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits LCD 3.4.1 ReS parameters for pressurizer pressure, cold leg t~mperature. and RCS total flow rate shall be within the limits specified in the COLR.
APPLICABILITY:
MODE 1.
NOTE-----------------------
Pressurizer pressure limit does not apply during:
- a.
THERMAL POWER ramp> 5% RTP per minute; or
- b.
THERMAL POWER step> 10% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Pressuri zer A.l Restore 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pressure or RCS flow rate not parameter{s) to within limit.
within limits.
(continued)
SAN ONOFRE--UNIT 3 3.4-1 Amendment No. 212
3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Re~uired Action an associ ated Completion Time of Condition A not met.
B.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.
RCS cold leg tem~erature not wit in limits.
C.1 Restore cold leg temherature to wit in limits.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D.
Re~uired Action an associated Completion Time of Cond ition C not met.
D.1 Reduce THERMAL POWER to
~ 30% RTP.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SR SR 3.4.1.1 3.4.1.2 SURVEILLANCE Verify pressurizer pressure is within the limits specified in the COLR.
Verify RCS cold leg temperature is within the limits specified in the COLR.
FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours (continued)
SAN ONOFRE--UNIT 3 3.4-2 Amendment No. 212
3.4.1 RCS DNB (Pressure. Temperature. and Flow) Limits ACTIONS (continued)
SURVEILLANCE FREQUENCY
NOTE---------------~-------
Required to be met in MODE 1 with all RCPs running.
SR 3.4.1.3 Verify RCS total flow rate is greater than or equal to the limits specified in the COLR.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SAN ONOFRE--UNIT 3 3.4-3 Amendment No. 212
Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Deleted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1.
Specification 3.1.1, IISHUTDOWN MARGIN (SDM) - T
>200°F;1I avg
- 2.
Specifi cati on 3.1.2, IISHUTDOWN MARGIN (SDM)
~ Tav9
- s:2000F; II
- 3.
Specifi cati on 3.1.4, "Moderator Temperature Coefficient;1I
- 4.
Specification 3.1.5, "Control Element Assembly (CEA)
Alignment; II
- 5.
Specification 3.1.7, "Regulating CEA Insertion Limits;1I
- 6.
Specification 3.1.8, "Part Length Control Element Assembly Insertion limits; II
- 7.
Specification 3.2.1, "Linear Heat Rate;"
- 8.
Specification 3.2.4, IIDeparture From Nucleate Boiling' Ratio;"
- 9.
Specification 3.2.5, "Axial Shape Index;"
- 10.
Specification 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits;
- 11.
Specification 3.9.1, "Boron Concentration. 1I
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
(continued)
SAN ONOFRE--UNIT 3 5.0-26 Amendment No. 212
Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)
(continued)
- 1.
CENPD-132P. "Calculative Methods for the C-E Large Break LOCA Evaluation Model"
- 2.
CENPD-137P. "Calculative Methods for the C~E Small Break LOCA Evaluation Model II
- 3.
CEN-356(V)-P-A. "Modified Statistical Combination of Uncertainties ll
- 4.
SCE-9801-P-A. "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 311
- 5.
CEN-635(S). IIIdentification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodologyll
- 6.
Letter. dated May 16. 1986. G. W. Knighton (NRC) to K.
P. Baskin (SCE). IIIssuance of Amendment No. 47 to Facility Operating License NPF-10 and Amendment No. 36 to Facility Operating License NPF-15." San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 3 SER)
- 7.
Letter. dated January 9. 1985. G. W. Knighton (NRC) to K. P. Baskin. IIIssuance of Amendment No. 30 to Facil ity Operating License NPF-10 and Amendment No. 19 to Facility Operating License NPF-15." San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)
- 8.
IIImplementation of ZIRLOTH Cladding Material in CE' Nuclear Power Fuel Assembly Designs.
1I CENPD...404... P-A
- c.
The core operating limits shall be determined assuming operation at RATED THERMAL POWER such that all applicable limits (e.g.. fuel thermal-mechanical 1imits. core thermal hydraulic limits. Emergency Core Cooling System (ECCS) limits.
nuclear limits such as SDM. transient analysis limits. and accident analysis linlits) of the safety analysis are met.
- d.
The COLR. including any mid-cycle revisions or supplements.
shall be provided upon issuance for each reload cycle to the NRC.
5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heatup. coo1down. low temperature operation. criticality. and hydrostatic testing as well as heatup and cool down rates shall be established and documented in the PTLR for the following:
(continued)
SAN ONOFRE--UNIT 3 5.0-27 Amendment No. 212
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 219 TO FACILITY OPERATING LICENSE NO. NPF-10 AND AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE NO. NPF-15 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
By application dated June 27,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081830515) (Reference 1), Southern California Edison Company (SCE, the licensee) requested changes to the Technical Specifications (TSs) for San Onofre Nuclear Generating Station (SONGS). Units 2 and 3.
The proposed changes would revise SONGS, Units 2 and 3, TS 3.4.1, "RCS [Reactor Coolant System] DNB [Departure from Nucleate Boiling] (Pressure, Temperature, and Flow) Limits," the associated bases of TS 3.4.1, and TS 5.7.1.5, "Core Operating Limits Report (COLR)," to replace the DNB numeric limits in the TSs with references to the COLR These changes are consistent with NRC-approved IndustryrrS Task Force (TSTF) Standard TS Change Traveler, TSTF-487, Revision 1, "Relocate DNB Parameters to the COLR" The changes would allow the licensee to recalculate the DI\\IB parameter limits using NRC-approved methodologies without the need for a future license amendment request (LAR). The availability of this TS improvement was announced in the Federal Register on June 5, 2007 (72 FR 31108) as part of the Consolidated Line Item Improvement Process.
Specifically, the proposed changes include the following:
Change TS 3.4.1, Limiting Conditions for Operation (LCO) 3.4.1 and the associated Surveillance Requirements (SRs) to replace the specific limit values of RCS pressurizer pressure, cold leg temperature, and RCS total flow rate with "the limits specified in the COLR" Change the bases for LCO 3.4.1 to reflect that the DNB limits are specified in the COLR
- 2 Change Section 5.7.1.5 of TS, "Core Operating Limits Report (COLR)" to include the NRC-approved methodologies and requirements used to calculate the DNB limits.
2.0 REGULATORY EVALUATION
In Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications," the Commission established its regulatory requirements related to the content of TS. Pursuant to 10 CFR 50.36, TS are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls.
The rule does not specify the particular requirements to be included in a plant's TS. As stated in 10 CFR 50.36(c)(2)(i), LCOs are "the lowest functional capability or performance levels of equipment required for safe operation of the facility." For the DNB parameters, 10 CFR 50.36(c)(2)(ii)(B) Criterion 2 applies, which requires that TS LCOs be established for each "process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."
LARs are required for each fuel cycle design that results in changes to parameter limits specified in TS. To meet 10 CFR 50.36(c)(2)(ii) requirements and alleviate the need for LARs to update parameter limits every fuel cycle, the NRC issued Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications" (Reference 2), with specific guidance for replacing the limit values for cycle-specific parameters in the TSs with references to an owner-controlled document, namely, the COLR. The guidance in GL 88-16 includes the following three actions:
- 1.
The addition of the definition of a named formal report (i.e., Core Operating Limits Report) in TS that includes the values of cycle-specific parameter limits that have been established using an NRC-approved methodology and consistent with all applicable limits of the safety analyses.
- 2.
The addition of an administrative reporting requirement (in TS 5.7.1.5) to submit the formal report on cycle-specific parameter limits to the Commission for information.
- 3.
The modification of individual TS to note that the specific parameters shall be maintained within the limits provided in the defined formal report (COLR).
GL 88-16 is the regulatory guidance for this change. The proposed change has been evaluated against GL 88-16 and found to be consistent with that regulatory guidance.
3.0 TECHNICAL EVALUATION
TS LCO 3.4.1 specifies the limit values of the DNB parameters to assure that the pressurizer pressure, the RCS cold leg temperature, and RCS flow rate during operation at the rated thermal power (RTP) will be maintained within the limits assumed in the safety analyses in the final safety analysis report. The safety analyses of anticipated operational occurrences and accidents assume initial conditions within the envelope of normal steady state operation at the
- 3 RTP to demonstrate that the applicable acceptance criteria, including the specified acceptable fuel design limits (such as DNB ratio) and RCS pressure boundary design conditions, are met for each event analyzed. The TS limits placed on the DNB-related parameters ensure that these parameters, when appropriate measurement uncertainties are applied, will be bounded by those assumed in the safety analyses, and thereby provide assurance that the applicable acceptance criteria will not be violated should a transient or accident occur while operating at the RTP.
It is essential to safety that the plant is operated within the DNB parameter limits. This change retains the requirement to maintain the plant within the DNB parameter limits in LCO 3.4.1 along with the SR verification for each of the DNB parameters. As these parameter limits are calculated using NRC-approved methodologies and are consistent with all applicable limits of the plant safety analyses, this change does not affect nuclear safety.
TS 5.7.1.5, "Core Operating Limits Report (COLR)," specifies that the core operating limits shall be determined such that all applicable limits of the safety analyses are met, and that the analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. This change modifies the list of NRC-approved methodologies in TS 5.7.1.5 to include those used to calculate the DNB limits on pressurizer pressure, RCS cold leg temperature, and RCS total flow rate. The limit values of these parameters in the COLR will comply with existing operating fuel cycle analysis requirements, and are initial conditions assumed in safety analyses. Replacing the DNB parameter values with references to the COLR does not lessen the requirement for compliance with all applicable limits.
Any revisions to the safety analyses that require prior NRC approval will be identified by the 10 CFR 50.59 review process. TS 5.7.1.5 also specifies that the COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
This will allow NRC staff to continue trending the information even though prior NRC approval of the changes to these limits will not be required.
Section 50.36 of 10 CFR requires LCOs to contain the lowest functional capability or performance levels of equipment for safe operation of the facility. The NRC staff finds that the proposed change to Leo 3.4.1 referencing the specific values of the DNB parameter limits in TS in the COLR continues to meet the regulatory requirement of 10 CFR 50.36(c)(2)(ii)(B)
(Criterion 2), and follows the guidance described in GL 88-16. The NRC staff, therefore, concludes that this change is acceptable.
For safety analyses of transients or accidents, various sections of Chapter 15 of the Standard Review Plan (Reference 3) specify that the reactor is initially at the RTP plus uncertainty, and the RCS flow is at nominal design flow including the measurement uncertainty. If one or more DNB parameter limits change, and these changes do not support the RTP, a license amendment would be required to either reduce the RTP or limit the plant operation at a level below the RTP.
10 CFR 50 Appendix K requires that the loss of coolant accident analysis be performed at 102 percent of the RTP. Other plant-specific analyses can contain an initial condition to be performed at RTP. To ensure a clear understanding of this requirement, TS 5.7.1.5.c. has been
- 4 reworded to add the underlined text: "The core operating limits shall be determined assuming operation at RATED THERMAL POWER such that all applicable limits... n 3.1 Summary The NRC staff has reviewed this proposed change to replace the values of the DNB parameters in TS with references to the COLR. This change will allow the licensee the flexibility to manage operating and core design margins associated with the DNB parameters without the need for cycle-specific LARs. Any future revisions to safety analyses that require prior NRC approval will be identified by the 10 CFR 50.59 review process. Based on this evaluation the NRC staff concludes that this change meets the regulatory requirements of 10 CFR 50.36, follows the guidance described in GL 88-16, and is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding published in the Federal Register on September 23, 2008 (73 FR 54868). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, on the basis of the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1.
James T. Reilly, Southern California Edison Company, letter to U.S. Nuclear Regulatory Commission, June 27,2008, "Application for Technical Specification Improvement to Adopt TSTF-487, Revision 1, 'Relocate Departure from Nucleate Boiling (DNB)
Parameters to the Core Operating Limits Report (COLR),' Using the Consolidated Line Item Improvement Process (CLlIP)" (ADAMS Accession No. ML081830515).
- 5
- 2.
U.S. Nuclear Regulatory Commission Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," October 4, 1988.
- 3.
NUREG-0800, "Standard Review Plan."
Principal Contributor: Matthew Hamm Date:
February 3, 2009
February 3, 2009 R. 1. Ridenoure
- 2 A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, IRN N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362
Enclosures:
- 1. Amendment No. 219 to NPF-10
- 2. Amendment No. 212 to NPF-15
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:
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- Edilona. IChanqes onlYI from sla ff provided SE
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