ML13316A976
| ML13316A976 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/18/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A975 | List: |
| References | |
| DPR-13-A-099, DPR-13-A-99, TAC-57658 NUDOCS 8706010437 | |
| Download: ML13316A976 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND 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. 99 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 licensees) dated May 9 1985, as revised on October 7, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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.
- 2. Accordingly, the license is amended by changes to the Technical Specifications 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:
8706010437 87051871)
PDR ADOCK 05000206 P
~PDR'
-2 B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
99, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective the date of issuance and shall be fully implemented no later than 30 days from date of issuance.
FOR THE NUCLEAR REG ATORY COMMISSION corge
. Knighto, Director Projec Directorate V Division of Reactor Projects-III/IV/V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 18, 1987
May 18, 1937 ATTACHMENT TO LICENSE AMENDMENT NO. 99 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 35a 35a 35al 35b 35b
-35a 3.6.2 CONTAINMENT ISOLATION VALVES APPLICABILITY:
MODES 1, 2, 3 and 4.
OBJECTIVE:
To provide assurance that the containment isolation valves listed in Table 3.6.2-1 will function when initiated by appropriate sensors.
SPECIFICATION:
The containment isolation valves specified in Table 3.6.2-1 shall be OPERABLE.
ACTION A. With one or more of the isolatAon valves(s) specified in Table 3.6.2-1 inoperable, for each affected penetration that is provided with two isolation valves and is open maintain at least one valve OPERABLE, and for all affected penetrations with either one or two isolation valves, one of the following Actions shall be taken:
- 1. Restore the inoperable valve(s) to.OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
- 2. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated* power operated valve secured in the isolation position, or
- 3. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or
- 4. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
B. The provisions of Specification 3.0.4 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the affected penetration is isolated in accordance with Action A.2 or A.3 above, and provided that the associated system, if applicable, is declared inoperable and the appropriate ACTION statements for that system are taken.
BASIS:
The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment." Containment isolation ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
- Valve may be temporarily activated for valve position verification and testing. While the valve is activated by this note, Action A.1 shall be applied and any system(s) declared inoperable pursuant to Action B shall not be declared OPERABLE.
Amendment No, 99
-35a1 3.6.2 CONTAINMENT ISOLATION VALVES (continued)
The isolation valves of the Sphere Purge Air Supply (POV-9) and Air Outlet (POV-10) lines have not been demonstrated capable of closure under the differential pressures generated by a design basis accident. For this reason, containment isolation in these lines shall be maintained. This configuration shall be accomplished by locking closed manual isolation valves CVS-301 and CVS-313 of these lines.
These valves shall remain locked closed during MODES 1, 2, 3, and 4 until POV-9 and POV-10 can be demonstrated capable of performing their containment isolation function under post accident conditions.
Temporary activation of a secured closed containment isolation valve permits position indication of certain types of valves and allows maintenance testing of isolation valves.
References:
- 1. NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.
Amendment No. 77, 99
35b TABLE 3.6.2-1 REMOTE MANUAL (RM) OR AUTOMATIC CONTAINMENT ISOLATION VALVE
SUMMARY
DESCRIPTION INSIDE SPHERE OUTSIDE SPHERE
- 1. Sphere Sump Discharge CV-102 CV-103
- 2. RCS Or Tk Discharge CV-104 CV-105
- 3. RCS Dr Tk Vent CV-106 CV-107
- 5. ORMS 1211/1212 Sphere CV-147 SV-1212-9 Sample Supply
- 6. ORMS 1211/1212 Sphere CV-146 SV-1212-8 Sample Return
- 7. A Stm. Gen. Stm. Sample SV-119
- 8. B Stm. Gen. Stm. Sample SV-120
- 9. C Stm. Gen. Stm. Sample SV-121
- 10. A Stm. Gen. Blowdown Sample SV-123
- 11.
B Stm. Gen. Blowdown Sample SV-122
- 12. C Stm. Gen. Blowdown Sample SV-124
- 13.
Service Water to Sphere CV-537 CV-115
- 14.
Service Air to Sphere Check Valve SV-125
- 15.
SI Loop C Vent SV-702B SV-702A
- 16.
SI Loop B Vent SV-702D SV-702C
- 17.
H2 Calibration Gas SV-3004 SV-2004
- 18.
RC Loop Sample (CV-955, CV-956, CV-957 CV-962) RM SV-3302
- 19.
Pressurizer Sample (CV-951, CV-953) RM CV-992
- 20.
Sphere Purge Air Supply*
POV-9
- 21.
Sphere Purge Air Outlet*
POV-10
- 22.
Sphere Equalizing/Vent CV-116 CV-10 Inst. Air Vent CV-40
- 23.
Primary Makeup to PRT CV-533 CV-534
- 24.
Cont. Cooling Out CV-515 RM
- 25.
Cont. Cooling In CV-516 RM
- 26. N2 Supply to PORV Check Valve CV-532 RM
- 27.
- 28.
Seal Water Return CV-527 RM CV-528 RM
- 29.
RC Loop Sample Return Check Valve SV-3303
- 30.
PRT Gas Sample CV-948 RM CV-949 Manual valves CVS-301 and CVS-313 of the Sphere Purge Air Supply and Air Outlet lines, respectively, shall be locked closed during MODES 1, 2, 3, and 4.
Amendment No. 59.77. 99