ML17059A786
| ML17059A786 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/24/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A787 | List: |
| References | |
| NUDOCS 9504280138 | |
| Download: ML17059A786 (8) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated March 9,
- 1995, 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 2.C.2. of Facility Operating License No. NPF-69 is hereby amended to read as follows:
9504280138 950424 PDR ADOCK 050004l0 PDR
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2.
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
65, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMHISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 24, 1995 Ledyard B. Harsh, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENTS ENDMENT NO. 65 FACILITY OPERATING LICENSE NO. NPF-69
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-41 Revise Appendix A as follows:
3/4 6-4 Insert Pa e
3/4 6-4
- NTAINMENT Y TE PRIMARY NTAINMENT PRIMARY NTAINM NT A A RVEI AN A Q IRM T
4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45A-1972:
a.
Three Type A overall integrated containment leakage rate tests shall be conducted at 40 a 10-month intervals during shutdown at Pa, 39.75 psig or at Pt, 20.0 psig, during each 10-year service period.* The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
b.
If any periodic Type A test fails to meet 0.75 La or 0.75 Lt, as applicable, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 La or 0.75 Lt, as applicable, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 La or 0.75 Lt, as applicable, at which time the above test schedule may be resumed.
C.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 La or 0.25 Lt, as applicable.
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25% of the total measured leakage at Pa, 39.75 psig, or Pt, 20.0 psig, as applicable.
d.
Type 8 and C tests shall be conducted with gas at Pa, 39.75 psig, at intervals no greater than 24 months except for tests involving:
1.
- Airlocks, 2.
Main steam line isolation valves and the remainder of the valves specified in Table 3.6.1.2-'f.
3.
Containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 4.
Purge supply and exhaust isolation valves with resilient seals.
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The test interval for conducting the second Type A test of the first 10-year service period shall be extended to 72 months to allow the Type A test to be performed during the 5th refueling outage.
This extension expires upon completion of the 5th refueling outage.
NINE MILE POINT - UNIT 2 3/4 6A Amendment No. 6, 4k~
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