ML080360063
| ML080360063 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/08/2008 |
| From: | Wang A NRC/NRR/ADRO/DORL/LPLIV |
| To: | Keenan J Pacific Gas & Electric Co |
| Wang, A B, NRR/DORL/LPLIV, 415-1445 | |
| References | |
| TAC MD3992, TAC MD3993 | |
| Download: ML080360063 (4) | |
Text
February 8, 2008 Mr. John S. Keenan Senior Vice President B Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 770000, Mail Code B32 San Francisco, CA 94177-0001
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 - CORRECTION TO SAFETY EVALUATION PAGE ISSUED IN AMENDMENT NOS. 198 AND 199, RESPECTIVELY (TAC NOS. MD3992 AND MD3993)
Dear Mr. Keenan:
By letter dated January 8, 2008, the Nuclear Regulatory Commission (NRC) issued the Amendment No. 198 to Facility Operating License No. DPR-80 and Amendment No. 199 to Facility Operating License No. DPR-82 for the Diablo Canyon Power Plant (DCPP), Unit Nos. 1 and 2, respectively. These amendments were issued in response to your application dated January 11, 2007 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML070190094), as supplemented by letters dated August 9, and September 28, 2007 (ADAMS Accession Nos. ML072260512 and ML072840047, respectively)
In the Section 2.0, Regulatory Evaluation, of the Safety Evaluation (SE), the NRC staff makes references to Technical Specification (TS) Task Force (TSTF) Standard TS Change Traveler TSTF-493, Clarify Application Setpoint Methodology for LSSS [Limiting Safety System Settings]
Functions, Revision 1. TSTF-493 has not been approved by the NRC staff and therefore was not used in the approval of this amendment. The NRC staff has enclosed a new page 2 for the SE, excluding the language discussing TSTF-493 which may have implied that that TSTF-493 criteria was used for the approval of Amendment Nos. 198 and 199.
If you have any questions regarding this matter, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosure:
As stated cc: See next page
ML072260512 and ML072840047, respectively)
In the Section 2.0, Regulatory Evaluation, of the Safety Evaluation (SE), the NRC staff makes references to Technical Specification (TS) Task Force (TSTF) Standard TS Change Traveler TSTF-493, Clarify Application Setpoint Methodology for LSSS [Limiting Safety System Settings]
Functions, Revision 1. TSTF-493 has not been approved by the NRC staff and therefore was not used in the approval of this amendment. The NRC staff has enclosed a new page 2 for the SE, excluding the language discussing TSTF-493 which may have implied that that TSTF-493 criteria was used for the approval of Amendment Nos. 198 and 199.
If you have any questions regarding this matter, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosure:
As stated cc: See next page DISTRIBUTION:
PUBLIC LPLIV Reading RidsAcrsAcnwMailCenter RidsNrrDirsItsb RidsNrrDeEicb RidsNrrDorlDpr RidsNrrDorlLpl4 RidsNrrLAJBurkhardt RidsNrrPMAWang RidsOgcRp RidsRgn4MailCenter SMazumder, NRR/DE/EICB ACCESSION NO.: ML080360063 NRR-106 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang JBurkhardt THiltz DATE 2/8/08 2/8/08 2/8/08
Diablo Canyon Power Plant, Units 1 and 2 (August 2007) cc:
NRC Resident Inspector Diablo Canyon Power Plant c/o U.S. Nuclear Regulatory Commission P.O. Box 369 Avila Beach, CA 93424 Sierra Club San Lucia Chapter ATTN: Andrew Christie P.O. Box 15755 San Luis Obispo, CA 93406 Ms. Nancy Culver San Luis Obispo Mothers for Peace P.O. Box 164 Pismo Beach, CA 93448 Chairman San Luis Obispo County Board of Supervisors 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408 Mr. Truman Burns Mr. Robert Kinosian California Public Utilities Commission 505 Van Ness, Room 4102 San Francisco, CA 94102 Diablo Canyon Independent Safety Committee Attn: Robert R. Wellington, Esq.
Legal Counsel 857 Cass Street, Suite D Monterey, CA 93940 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Jennifer Post, Esq.
Pacific Gas & Electric Company P.O. Box 7442 San Francisco, CA 94120 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis, Obispo, CA 94306-0112 Director, Radiologic Health Branch State Department of Health Services P.O. Box 997414, MS 7610 Sacramento, CA 95899-7414 Mr. James Boyd, Commissioner California Energy Commission 1516 Ninth Street MS (31)
Sacramento, CA 95831 Mr. James R. Becker, Vice President Diablo Canyon Operations and Station Director Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 Jennifer Tang Field Representative United States Senator Barbara Boxer 1700 Montgomery Street, Suite 240 San Francisco, CA 94111 Mr. John T. Conway Site Vice President Diablo Canyon Power Plant P. O. Box 56 Avila Beach, California 93424
2.0 REGULATORY EVALUATION
NRC Regulatory Issue Summary (RIS) 2006-17, "NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specifications, Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," dated August 24, 2006, discusses the requirements of Part 50, Section 36 of Title 10 of the Code of Federal Regulations (i.e., 10 CFR 50.36) related to Limiting Safety System Settings and provides an approach acceptable to the NRC to address LSSS issues. LSSS are settings for automatic protective devices related to those variables having significant safety functions.
The NRC staff used the following references in its review of the SG Water Level-High High (P-14) setpoint change :
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, Section 36, Technical Specifications, states, [e]ach applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section. Specifically, paragraph 50.36(c)(1)(ii)(a) states,
[w]here a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. Furthermore, paragraph 50.36(c)(3) states, [s]urveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met.
10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, Criterion 13, Instrumentation and Control, requires that the instrumentation be provided to monitor variables and systems and that controls be provided to maintain these variables and systems within prescribed operating ranges.
10 CFR Part 50, Appendix A, Criterion 20, Protection System Functions, requires that the protection system be designed to initiate operation of appropriate systems to ensure that specified acceptable fuel design limits are not exceeded.