ML20069E565
| ML20069E565 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/17/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069E563 | List: |
| References | |
| NUDOCS 8209240134 | |
| Download: ML20069E565 (2) | |
Text
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- f tilSSISSIPPI POWER AWD LIMIT CO'9AtiY tilbOLE 50UTri Ef!ERGY, INC.
SOUTH tilS$l$51PPI LLECTRIC POWER ASSOCI ATION DOCKET NO.53-416 GRAND GULF NUCLEAR STATION, Ut!!T 1 AMEND lENT TO FACILITY OPERATING LICEM5E License No. NPF-13 Anendment No. 2 1.
The nuclear Regulatory Conmission (the Comission or the ?iP.C) having found that:
A.
The applications for the amendments filed by the :11ssissippi Power and Light Canaany <1ated July 2, Auqust 5 and August 10, 1932 comply with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, the provisions of the Act, and the regulations of the Co rtission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without cndangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this auendment will not be ininical to the comon defense and security or to the healtn and safety of the public; and E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirenents have be n sd ti s il e'i.
2.
Accordingly, the license is anended as follows:
A.
Change paragraphs 2.C.(42)(a)(b) and (f) to read as follows:
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. 2.C.(42)
(a) Technical Specification requirements to have Prinary Containment (Drywell & Containment) operable are suspended. These are Specifications 3.6.1.1, 3.6.1.2, 3.6.1.3, 3.6.1.4, 3.6.1.5, 3.6.2.1, 3.6.2.3, 3.6.3.4, 3.6.4 (including actuation instrumentation, Specification 3.3.2),3.8.4.1.
(b) In addition to the exceptions permitted by Specification 3.10.1, the following reactor vessel head off exceptions are also pemitted:
Technical Specification 3.3.2 (primary containment isolation actuation instrumentation o, d; 3.3.7.1, items 3,4 and 5; 3.3.7.4; 3.3.7.5 Tabi 3.3.7.5-1, items 8,9 and 12 through 18; 3.3.7.10;.i.3.7.12, l
Table 3.3.7.12, itens 2,4,6 and 7; 3.3.3; 3.4.2.1; 3.4.2.2; 3.4.7; 3.6.1.4; 3.6.1.9; 3.6.4; 3.6.5; and 3.8.4.1 (f) Provided that the outboard MSIVs and the main steam shutoff valves are closed, the provisions of the following specifi-cations nay be suspended:
3.3.1, Table 3.3.1-1, I ten 7; 3.3.2, Table 3.3.2-1, Item 2b; 3.3.7.1. Table 3.3.7.1-1, Items 3,4 and 5; 3.3.7.5, Table 3.3.7.5-1, Iten 17; and 3.6.1.4.
B.
Change Item 1(c) of Attachment 1 to License MPF-13 to read:
1(c) Resolve issue regarding eaintaining the control room at a pressure of 1/8 inch water gauge.
C.
Add Section 3 to Attachnent 1 to License LPF-13 to read:
- 3. Prior to exceeding 1 percent power, the licensee shall complete to the satisfaction of the t1RC the following open itens and construction deficiencies: a) control roon envelope leak tightness test.
3.
This amendment is effective as of the date of issuance.
FOR THE !tVCLEAR REGULATORY C0fMISS10tl 1
Darrell G. Eisenhut, Dircrtor Division of Licensing Office of Nuclear Reactor Regulation r/N.
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