ML13316B372
| ML13316B372 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/15/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316B371 | List: |
| References | |
| DPR-13-A-127 NUDOCS 8905220209 | |
| Download: ML13316B372 (4) | |
Text
F~ REGUZ.1 0
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. 127 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 February 17, 1989, as supplemented March 21 and 23, and May 3 and 8, 1989 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.
8905220209 890515 DR ADOCK 05000206 PPDiC"
- 2. Accordingly, the license is amended by the addition of new paragraph 3.M as indicated in the attachment to this license amendment.
- 3. This license amendment is effective as of the date of its issuance and must be fully implemented as described in the Attachment.
FOR THE NUCLEAR REGULATORY COMMISSION George. Knighto Director Project Directorate V Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
License Condition 3.M Date of Issuance:
May 15, 1989
3d 3.M Cycle X Thermal Shield Monitoring Program The neutron noise/loose-parts detection system shall be used to monitor the condition of the reactor vessel thermal shield throughout Cycle X or until repair.
Periodic monitoring of both neutron noise and loose-parts vibrations confirms that no long term unacceptable trend of degradation is occurring.
The details of this program are described below.
(1) The unit will be shut down no later than June 30, 1990 to inspect the condition of the thermal shield.
(2) During the first 7 days of Z 85% power, interim acceptance criteria for neutron noise/loose-parts monitoring will be developed. These interim criteria will be utilized until the final acceptance criteria is developed.
Final acceptance criteria for neutron noise/loose-parts monitoring will be established by performing baseline evaluations for 45 calendar days at > 85% power following return to service for Cycle X operation. The base line data will be established by recording a minimum of 16 segments of data information, each of 20 minute duration at > 85% power.
Adjustments to the acceptance criteria will be made for cycle burnup and boron concentration changes throughout the cycle.
(3) The neutron noise/loose-parts monitoring system shall be OPERABLE in MODE 1 with:
a)
At least two horizontal loose-parts detectors monitored for at least five (5) minutes 2 times per day; and, b) at least three (3) neutron noise inputs monitored for at least twenty (20) minutes once a week, and be analyzed for cross power spectral density', including phase and coherence.
(4) The data provided by the loose-parts/neutron noise monitor shall be analyzed once per week and compared with the established criteria.
If the data exceeds the acceptance criteria:
a)
Within 1 day the NRC will be informed of the exceedance.
b)
Within 14 days the conditions will be evaluated and a report provided to the NRC documenting future plans and actions.
Amendment No. 127
-3e c)
The plant will be shutdown should the remaining flexure be demonstrated failed.
(5) Each channel of the loose-part detection system shall be demonstrated OPERABLE in MODE 1 by performance of a:
a)
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b)
CHANNEL TEST at least once per 31 days The surveillance requirements for neutron noise monitor are covered by the Appendix A Technical Specification 4.1.1 for the Power Range Neutron Flux.
(6) With the neutron noise/loose-parts detection instrumentation inoperable for more than 7 days, licensee shall submit a Special Report to the Commission pursuant to Appendix A Tecnnical Specification 6.9.2 within the next 3 days outlining the cause of the malfunction and the plans for restoring the system to operable status.
(7) In the case of a seismic event of 0.25g or greater as indicated on site sensors, a controlled shut down shall be initiated.
Before operations are resumed, it will be demonstrated that no thermal shield damage has occurred due to the seismic event.
(8)
The provisions of Appendix A Technical Specification 3.0.4 are not applicable to this license condition.
Amendment No. 127