ML17278A666
| ML17278A666 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/18/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A665 | List: |
| References | |
| TAC-60546, NUDOCS 8603270258 | |
| Download: ML17278A666 (6) | |
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%y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment No.
21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply
- System, (the Supply System or licensee) dated January 17, 1986, 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 pro-visions 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 regulation; D.
The issuance of this amendment will not be inimical to the common defense and security or 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, Facility Operating License No. NPF-21 is amended to revise the Technical Specifications as indicated in the attachment to this amendment, and paragraph 2.C.(2) of Facility Operating License is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
21, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8 dW=
Elinor G. Adensam, Director BWR Project Directorate No.
3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO'1 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove Pa e
3/4 6-4 Insert Pa e
3/4 6-4
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CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.
Type B and C tests shall be conducted with gas at P, 34. 7 psig," at intervals no greater than 24 months"" except for tests involving:
l.
Air Locks 2.
Main steam line isolation valves, 3.
Valves pressurized with fluid from a seal
- system, 4.
ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and Purge supply and exhaust isolation valves with resilient seals.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement
- 4. 6. l. 3.
Main steam line isolation valves shall be leak tested at least once per 18 months.
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Leakage from isolation valves that are sealed with fluid fiom a seal system may be excluded, subject to the provisions of Appendix J,Section III.C. 3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P
a'8.2
- psig, and the'seal system capacity is adequate to maintain system pressure for at least 30 days.
ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at least once per 18 months.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6. 1.8.2 and 4.6.1.8.3.
The provisions of Specification 4.0.2 are not applicable to 24-month or 40 k 10-month surveillance intervals.
"Unless a hydrostatic test is required per Table 3.6.3-1.
""The 24 month type 8 test of the drywell head "0" rings is deferred until the first refueling outage but not later than May 15, 1986.
WASHINGTON NUCLEAR - UNIT 2 3/4 6-4 Amendment No. 21
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