ML080360063

Correction to Safety Evaluation for Amendment Nos. 198 and 199, Revise Technical Specification (TS) 3.3.2, TS 5.5.9, and TS 5.6.10 to Support Replacement of Steam Generators (TAC MD3992 and MD3993)

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 RidsNrrDirsItsb RidsNrrDorlLpl4 RidsOgcRp LPLIV Reading RidsNrrDeEicb RidsNrrLAJBurkhardt RidsRgn4MailCenter RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrPMAWang 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 City Editor Diablo Canyon Power Plant The Tribune c/o U.S. Nuclear Regulatory Commission 3825 South Higuera Street P.O. Box 369 P.O. Box 112 Avila Beach, CA 93424 San Luis, Obispo, CA 94306-0112 Sierra Club San Lucia Chapter Director, Radiologic Health Branch ATTN: Andrew Christie State Department of Health Services P.O. Box 15755 P.O. Box 997414, MS 7610 San Luis Obispo, CA 93406 Sacramento, CA 95899-7414 Ms. Nancy Culver Mr. James Boyd, Commissioner San Luis Obispo California Energy Commission Mothers for Peace 1516 Ninth Street MS (31)

P.O. Box 164 Sacramento, CA 95831 Pismo Beach, CA 93448 Mr. James R. Becker, Vice President Chairman Diablo Canyon Operations and San Luis Obispo County Station Director Board of Supervisors Diablo Canyon Power Plant 1055 Monterey Street, Suite D430 P.O. Box 56 San Luis Obispo, CA 93408 Avila Beach, CA 93424 Mr. Truman Burns Jennifer Tang Mr. Robert Kinosian Field Representative California Public Utilities Commission United States Senator Barbara Boxer 505 Van Ness, Room 4102 1700 Montgomery Street, Suite 240 San Francisco, CA 94102 San Francisco, CA 94111 Diablo Canyon Independent Safety Mr. John T. Conway Committee Site Vice President Attn: Robert R. Wellington, Esq. Diablo Canyon Power Plant Legal Counsel P. O. Box 56 857 Cass Street, Suite D Avila Beach, California 93424 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

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.