ML20038C468
| ML20038C468 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/19/1981 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20038C469 | List: |
| References | |
| NUDOCS 8112110092 | |
| Download: ML20038C468 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION
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ALABAMA POWER COMPANY DOCKET NO. 50-364
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JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. NPF-8 1.
The Nuclear Regulatory Comission (_the Comission) has found that:
A.
Pursuant to 10 CFR 50.12 of the Commission's Regulations, the Comission has authorized an exemption from the requirements of Appendix J to 10 CFR Part 50.
B.
The application for amendment by Alabama Power Company (the licensee) dated October 8,1981, 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; C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; D.
There is reasonable assurance (.1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; E.
The issuance of this amendment will not be inimical to the common defense and security or to the hea:lth and safety of the public; l
and l
F.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Comission's regulations and all applicable requirements have been satisfied.
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l 8112110092 811119 PDR ADOCK 05000364 P
. 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-8 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Apaendices A and B, as revised through Amendment No. 10, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificationt.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION y $ x. O (
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Marshall Grotenhuis, Acting Chief Operating Reactors Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 19, 1981 e
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ATTACHMENT TO LICENSE AMEN 0 MENT AMENDMENT NO.10 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revise Appendix A as follows:
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Insert Page 3/4 6-3 3/4 6-3
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
If any periodic Type A test fails to meet either 0.75 L or 0.75 L b.
the test schedule for subsequent Type A tests shall be feviewed anb, approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L or 0.75 L, a Type A test shall be perfo A 1 at t
least every 18 months until two consecutive Type A tests me c either at which time the above test schedule may be resume $.or0.75L 0.75 L t
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,, or 0.25 L *t 2.
Has a 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 percent of the total measured leakage at P, (48 psig) or Pt (24 psig.)
48 psig) at Type B and C tests shall be conducted with gas at Pintervals no greater l
d.
1rcks.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
g.
The provisions of Specification 4.0.2 are not applicable.
- This is a one-time Exemption to 10 CFR 50.46 Appendix J.
The 24 month interval may be extended during the first fuel cycle to allow individual penetrations to be tested as plant conditions permit, but in no case shall any individual test interval extend beyond the first refueling outage. If plant conditions support earlier testing or if incidents occur which could jeopardize the leak tight integrity of a penetration, the testing will be performed at that time.
t FARLEY-UNIT 2 3/4 6-3 Amendment No. 10 1
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