ML17277B450
| ML17277B450 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/13/1984 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17277B451 | List: |
| References | |
| NUDOCS 8407230292 | |
| Download: ML17277B450 (7) | |
Text
UNITED STATES NUC LEAR R EG ULATORY COMMISS WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.2 AHENDMENT TO FACILITY OPERATING LICENSE License No.
NPF-21 Amendment No.
2 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (WPPSS, also the licensee),
dated January 20, February 8, and April 10, 1984, 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 as
- amended, 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 regulation set forth in 10 CFR Chapter I; 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.
The license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 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. 2, 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.
8407230292 8407l3 PDR ADDCK 05000397 P
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3.
This amendment was effective as of April 10, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION Ori8inal signed by A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO.
2 F
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. NPF-21 DOCKET N
. 50-397 Replace the following page of the Appendix "A" Technical Specifications with enclosed page.
The revised pages are identified by Amendment number and contain vertical lines ihdicating the area of change.
REIIOVE 3/4.4-10 INSERT 3/4.4-10
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REACTOR COOLANT SYST SURVEILLANCE RE UIREllENTS 4.4.3.2. 1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
a.
Honitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Honitoring the primary containment sump flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Honitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:
a.
b.
At least once per 18 months.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
The provi'sions of Specification 4,0.4 are not applicable for entry into OPERATIONAL CONDITION 3.*
4.4.3.2.3 The high/low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4. 3. 2-2 by performance of a:
a.
CHANNEL FUNCTIONAL TEST at least once per -31 days, and b.
CHANNEL CALIBRATION at least once per 18 months.
MASHINGTON NUCLEAR - UNIT 2 3/4 4-10 Amendment No.
2