ML041050133
| ML041050133 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/12/2004 |
| From: | Shukla G NRC/NRR/DLPM/LPD4 |
| To: | Rueger G Pacific Gas & Electric Co |
| Shukla G, NRR/DLPM/LPDIV-2/415-8439 | |
| References | |
| TAC MC2535 | |
| Download: ML041050133 (9) | |
Text
April 12, 2004 Mr. Gregory M. Rueger Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 3 Avila Beach, CA 93424
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NO. 1 - PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE (TAC NO. MC2535)
Dear Mr. Rueger:
The enclosed announcement was forwarded to the San Luis Obispo Tribune for publication. This announcement relates to your application dated April 2, 2004, that was superseded by application dated April 8, 2004, for an amendment to Facility Operating License No. DPR-80 for the Diablo Canyon Power Plant (DCPP), Unit No. 1. The proposed amendment would revise Technical Specification (TS) 3.3.5, "Loss of Power (LOP) Diesel Generator (DG)
Start Instrumentation," to allow performance of Surveillance Requirement (SR) 3.3.5.2, prior to first entry into MODE 4, by adding a note to the FREQUENCY column of SR 3.3.5.2 on a one-time basis.
Sincerely,
/RA/
Girija S. Shukla, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-275
Enclosure:
Public Notice cc w/encl: See next page
April 12, 2004 Mr. Gregory M. Rueger Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 3 Avila Beach, CA 93424
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NO. 1 - PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE (TAC NO. MC2535)
Dear Mr. Rueger:
The enclosed announcement was forwarded to the San Luis Obispo Tribune for publication. This announcement relates to your application dated April 2, 2004, that was superseded by application dated April 8, 2004, for an amendment to Facility Operating License No. DPR-80 for the Diablo Canyon Power Plant (DCPP), Unit No. 1. The proposed amendment would revise Technical Specification (TS) 3.3.5, "Loss of Power (LOP) Diesel Generator (DG)
Start Instrumentation," to allow performance of Surveillance Requirement (SR) 3.3.5.2, prior to first entry into MODE 4, by adding a note to the FREQUENCY column of SR 3.3.5.2 on a one-time basis.
Sincerely,
/RA/
Girija S. Shukla, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-275 DISTRIBUTION:
PUBLIC
Enclosure:
Public Notice PDIV-2 Reading RidsNrrDlpmPdiv (HBerkow) cc w/encl: See next page RidsNrrPMGShukla RidsNrrLAEPeyton RidsOgcRp RidsAcrsAcnwMailCenter RidsRgnIVMailCenter (BJones)
RidsNrrDlpmDpr MLesar SBurnell ACCESSION NO.: ML041050133 NRR-106 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME GShukla EPeyton JNDonohew for SDembek DATE 4/9/04 4/9/04 4/9/04 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML041050133.wpd OFFICIAL RECORD COPY
Diablo Canyon Power Plant, Units 1 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 c/o Henriette Groot 1000 Montecito Road Cayucos, CA 93430 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 Room 370 County Government Center 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 Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Richard F. Locke, Esq.
Pacific Gas & Electric Company P.O. Box 7442 San Francisco, CA 94120 Mr. David H. Oatley, Vice President and General Manager Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 City Editor The Tribune 3825 South Higuera Street P.O. Box 112 San Luis Obispo, CA 93406-0112 Mr. Ed Bailey, Radiation Program Director Radiologic Health Branch State Department of Health Services P.O. Box 942732 (MS 178)
Sacramento, CA 94234-7320 Mr. James D. Boyd, Commissioner California Energy Commission 1516 Ninth Street (MS 31)
Sacramento, CA 95814 Mr. James R. Becker, Vice President Diablo Canyon Operations and Station Director Diablo Canyon Power Plant P.O. Box 3 Avila Beach, CA 93424
PUBLIC NOTICE NRC STAFF PROPOSES AMENDMENT OF OPERATING LICENSE FOR DIABLO CANYON POWER PLANT, UNIT NO. 1 The U.S. Nuclear Regulatory Commission (NRC) staff has received an application dated April 2, 2004, that was superseded by application dated April 8, 2004, from Pacific Gas and Electric Company (PG&E), for an exigent amendment to Facility Operating License No. DPR-80 for the Diablo Canyon Power Plant (DCPP), Unit No. 1, located in San Luis Obispo County, California. DCPP Unit 1 is currently in its 12th refueling outage (1R12).
The proposed amendment would revise Technical Specification (TS) 3.3.4, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation." The associated TS SR 3.3.5.2 requires performing a trip actuation device operational test (TADOT) on an 18-month frequency on the LOP DG start instrumentation. Testing to satisfy SR 3.3.5.2 is normally performed at the end of each refueling outage. However, because of DCPP Unit 1s extended eleventh Refueling Outage (1R11), SR 3.3.5.2 became due for DCPP Unit 1 DGs 1-1, 1-2, and 1-3, in the beginning of 1R12, when the scheduled fuel reconstitution activities were being performed and the desired redundancy of safety-related equipment were not available. However, to allow scheduled fuel reconstitution activities to proceed as planned, a performance of the TADOT for SR 3.3.5.2 for DG 1-1 was conducted during the weekend of April 3-4, 2004. At this time, the TADOT has not been performed on the schedule required by TS SR 3.3.5.2 for DG 1-2 and DG 1-3. Currently, DG 1-2 is not available for testing.
The proposed change would allow performance of Surveillance Requirement (SR) 3.3.5.2 for DCPP Unit 1 only, prior to first entry into MODE 4, by adding a note to the FREQUENCY column of SR 3.3.5.2 on a one-time basis. PG&E requested the license amendment on an exigent basis to allow a delay in the performance of the SR 3.3.5.2 testing, which has come due on DCPP Unit 1. Early performance of the SR 3.3.5.2 test is not appropriate from an outage safety standpoint. From an outage defense-in-depth standpoint, it is better to perform SR 3.3.5.2 later in 1R12 as was originally planned, when the desired redundancy of safety-related equipment is available. Approval to extend the due date for SR 3.3.5.2 will allow performing SR 3.3.5.2 testing in conjunction with load shed and auto sequencing testing for each DG and its associated vital bus at the end of the outage, prior to entry into Mode 4, as currently planned. This approval is requested to support planned maintenance on DG 1-1, which is the only Unit 1 DG that is in compliance with SR 3.3.5.2.
Approval to extend SR 3.3.5.2, will allow declaring DG 1-3 operable at that time to support planned maintenance, without first having to perform SR 3.3.5.2 testing.
The licensee and the NRC staff have evaluated this proposed change with regard to the determination of whether or not a significant hazards consideration is involved. Operation of DCPP Unit 1 in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. Extending the frequency of SR 3.3.5.2 on a one-time basis for Unit 1 does not involve an accident initiator.
The SR only verifies that undervoltage (UV) relays operate (change state) when a UV condition occurs on a 4-kV vital bus. Other SRs performed in Mode 1 are used to verify relay setpoints and characteristics that are subject to time-dependent changes. Therefore, the proposed change will not increase the probability of any accident previously evaluated. Also, the proposed change has no affect on the radiological consequences of any accident previously evaluated because it will not delay or prevent any plant equipment from performing its design function. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment will not create the possibility of a new or different kind of accident from any previously analyzed. The proposed change does not involve or create an accident initiator. It only extends the surveillance interval for verifying operability of UV relay sequencing. Other SRs are used to verify relay setpoints and characteristics that are subject to time-dependent changes. Therefore, the proposed change does not create the possibility of a new or different accident from any accident previously evaluated.
The proposed amendment will not involve a significant reduction in a margin of safety.
The proposed change only involves extending a SR frequency that has no time-dependent characteristics. The SR itself is not changed. Other SRs are used to verify relay setpoints and characteristics that are subject to time-dependent changes. Extension of this SR frequency has no effect on any margin of safety. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Following an initial review of this application, the requested amendment has been evaluated against the standards in 10 CFR 50.92 and the NRC staff has made a proposed (preliminary) determination that the requested amendment involves no significant hazards considerations. The change does not significantly increase the probability or consequences of any accident previously considered, nor create the possibility of an accident of a different kind, nor significantly decrease any margin of safety.
If the proposed determination that the requested license amendment involves no significant hazards consideration becomes final, the staff will issue the amendment without first offering an opportunity for a public hearing. An opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.
If the staff decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before the amendment is issued.
Comments on the proposed determination of no significant hazards consideration may be (1) telephoned to Steve Dembek, Chief, Section 2, Project Directorate IV, by collect call to (301) 415-1455, or by facsimile to (301) 415-3313, (2) e-mailed to SXD@nrc.gov, or (3) submitted in writing to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555. All comments received by close of business on April 15, 2004, from 7:30 a.m. to 4:15 p.m. Federal workdays will be considered in reaching a final determination. A copy of the application may be examined electronically through the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room link at the NRC Web site http://www.nrc.gov/reading-rm/adams.html and at the Commissions Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.