ML13316B274
| ML13316B274 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/25/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316B272 | List: |
| References | |
| DPR-13-A-118 NUDOCS 8902020402 | |
| Download: ML13316B274 (9) | |
Text
oG UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.118 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensee) dated March 20, 1987, as supplemented July 22, 1988 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 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.
8902020402 8190125 FDR ADOCK 0500020, PDC
-2
- 2. Accordingly, the license is amended by changes to the Technical Speci fications as indicated in the attachment to this license amendment, and paragraph 3.B. of Provisional Operating License No. DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 118, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.
- 3. This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR RE ULATORY COMMISSION George Knighto, Director Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: January 25, 1989
ATTACHMENT TO LICENSE AMENDMENT NO.118 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 47 47*
48 48 48a
- Reissued without change.
-47 4.3 CONTAINMENT SYSTEMS 4.3.1 CONTAINMENT TESTING APPLICABILITY:
Applies to containment leakage.
OBJECTIVE:
To verify that leakage from the containment sphere is maintained within specified values.
SPECIFICATION:
- 1. Integrated Leakage Rate Tests, Type A A. Test Pressure In order to verify leakage from the containment sphere, a Type A test shall be performed. Type A tests shall consist of a peak pressure test or a reduced pressure test.
Peak pressure tests are conducted at a test pressure greater than or equal to 49.4 psig, and reduced pressure tests are conducted at a test pressure greater than or equal to 24.7 psig.
B. Acceptance Criteria For the peak pressure test program the containment sphere leakage rate measured is less than 0.090 wt%/24 hours of the initial content of the containment air at the calculated peak pressure of 49.4 psig. For the reduced pressure test program to be conducted at 24.7 psig, the measured leakage rate shall be less than 0.064 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig.
The accuracy of each Type A test is verified by a supplemental test which (1) confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 25% of 0.12 wt%/24 hours for the peak pressure test or 0.085 wt%/24 hours for the reduced pressure test, and (2) requires the quantity of air bled from or injected into the containment during the supplemental test to be equivalent to at least 75 percent of the total allowable leakage rate at 49.4 psig.
SAN ONOFRE -
UNIT 1 Amendment No. ?A,75
-48 C. Frequency A set of 3 periodic Type A tests are performed at 40 + 10 month intervals during each 10-year service period. The third test of each set is performed when the plant is shut down for the 10-year plant inservice inspection. The permissible period for Type A testing shall be limited to periods-when the plant facility is nonoperational and secured in the shutdown condition.
If any periodic Type A test fails to meet the acceptance criteria above, the test schedule applicable to subsequent Type A tests shall be submitted to the NRC for review and approval. If two consecutive periodic Type A tests fail to meet the above acceptance criteria, a Type A test is performed at each plant shutdown for refueling or approximately every 18 months, whichever occurs first, until two consecutive Type A tests meet the acceptance criteria, after which time the normal test schedule may be resumed.
II. Containment Penetration Leakage Rate Tests (TYDe B)
A. Test Pressure Type B tests are conducted at a test pressure at or above 49.4 psig. Personnel airlocks are tested every six months at or above 49.4 psig. In addition, a lower pressure test at or above 10 psig is performed on the personnel airlocks as required by Section II.C.
B. Acceptance Criteria The combined leakage rate of all penetrations subject to Type B tests and all containment isolation valves subject to Type C tests is less than 0.072 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig.
C. Test Schedule Type B tests, except for airlocks, are performed during every reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.
Airlocks volumes between the doors are tested:
(1) at least every six months at 49.4 psig, SAN ONOFRE -
UNIT 1 Amendment No.
07.118
-48a (2) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the airlock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, at or above 10 psig test pressure, and (3) prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the airlock that could affect.the airlock sealing capability at 49.4 psig.*
- Exemption to Appendix J of 10 CFR 50 SAN ONOFRE - UNIT 1 Amendment No. 118
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 NOTICE OF DENIAL OF AMENDMENT TO PROVISIONAL OPERATING LICENSE AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) has denied in part a request by the licensees for amendment to Provisional Operating License No. DPR-13, issued to Southern California Edison Company and San Diego Gas and Electric Company (the licensees), for operation of San Onofre Nuclear Generating Station, Unit No. 1 (the facility), located in San Diego County, California.
The application for amendment was dated March 20, 1987 as supplemented July 22, 1988. Notice of Consideration of Issuance of Amendment was published in the FEDERAL REGISTER on September 7, 1988 (53 FR 34611).
The amendment as proposed by the licensees, would consist of the following changes to the Technical Specifications (Appendix A to Provisional Operating License No. DPR-13):
- 1. Editorial changes to the test pressure and schedule for Type B containment air lock leak rate testing,
- 2. A modified requirement to test the air lock prior to establishing containment integrity only if maintenance has been performed on the air lock which could affect the sealing capability, and
-2
- 3. a change to the reduced pressure test for the air lock from 10 psig to 3 psig.
The portion of the application which would change the reduced pressure test from 10 psig to 3 psig has been denied. The licensee's supplemental letter of July 22, 1988 stated that test data to support this change would be available and provided to the NRC staff by September 30, 1988. To date this information has not been provided.
The licensees were notified of the Commission's denial of this request by letter dated January 20, 1989.
The other changes requested by the application have been approved by the issuance of Amendment No. 118.
By March 3, 1989, the licensees may demand a hearing with respect to the denial described above and any persons whose interest may be affected by this proceeding may file a written petition for leave to intervene.
A request for a hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, 2120 L Street, NW, Washington, DC, by the above date.
A copy of the petition should also be sent to the General Counsel, U.S.
Nuclear Regulatory Commission, Washington, D.C., 20555, and to Charles R. Kocher, Assistant General Counsel and James Beoletto, Esq., Southern California Edison Company, P.O. Box 800, Rosemead, California 91770, attorneys for the licensees.
-3 For further details with respect to this action, see (1) the application for amendment dated March 20, 1987, as supplemented July 22, 1988, and (2) the Commission's letter and Safety Evaluation issued with Amendment No. 118 to DPR-13 dated January 20, 1989.
These documents are available for public inspection at the Commission's Public Document Room, 2120 L Street, NW, Washington, DC, and at the General Library, University of California, P.O. Box 19557, Irvine, California 92713. Single copies of Item (2) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Division of Reactor Projects -
III, IV, V and Special Projects.
Dated at Rockville, Maryland, this 20-day of January, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation