ML17279A676
| ML17279A676 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/02/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A677 | List: |
| References | |
| TAC-57546, NUDOCS 8712090369 | |
| Download: ML17279A676 (8) | |
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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 Amendment No. 22 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated April 25, 1985, complies with the standards and requirements of the Atomic Enerqy Act of 1954, as amended (the Acti, 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 set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-21 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised throuqh Amendment No.
22, 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 amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGUlATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Elinor G. Adensam, Director RWR Proiect Directorate No.
3 Division of BWR Licensing Date of Issuance:
May 02, 1986
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ENCLOSURE TO LICENSE AMENDMENT NO. 22 FACILITY OPERATINA LICENSE NO.
NPF-21 DOCKET NO. 50-397 Replace the following paqe 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 3/4 6-1 INSERT 3/4 6-1
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I 3/4. 6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2" and 3.
ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY
'ithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in't least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE UIREMENTS
- 4. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
ao b.
C.
d.
After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing the seals with gas at P
, '34.7 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement
- 4. 6.1.2. d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L.
At least once per 31 days by verifying that all primary containment penetrations""--not capable of being closed by OPERABLE containment automatic isolation valves and requir'ed to be closed during accident conditions'are closed by valves, blind flanges, or deactivated auto-matic valves secured in position, except as provided in Table 3.6.3-1 of Specification 3. 6.3.
By verifying each primary containment air lock is in compliance with the requirements of Specification 3.6.1.3.
By verifying the suppression chamber is in compliance with the re-quirements of Specification
- 3. 6. 2. 1.
"See Special Test Exception 3.10. 1.
- ""Except valves, blind flanges, and deactivated atuomatic valves which are with-in the primary containment or other areas administratively controlled to pro-hibit access for reasons of personnel safety (i.e., radiation and temperature) and 5re locked, sealed, or otherwise secured in the closed position (1< inch and smaller valves connected to vents, drains or test connections must be closed but n'eed not'e sealed).
Valves inside containment shall be verified closed following primary containment d'e-inerting, but verification is not required more 'often than once per 92 days.
Valves in other administratively controlled areas shall be. verified closed during each COLD SHUTDOWN, but verification is not required more often than once per 31 days.
WASHINGTON NUCLEAR - UNIT 2 3/4 6-1 Amendment No.
22
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