ML20041G305
| ML20041G305 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/03/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20041G306 | List: |
| References | |
| DPR-46-A-076 NUDOCS 8203220031 | |
| Download: ML20041G305 (4) | |
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[pr.a ua h UNITED STATES u
y P(,g NUCLEAR REGULATORY COMMISSION
/.
WASHINGTON, D, C. 20555
%...../
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
.a A.
The application for amendment by Nebraska Public Power District dated January 25, 1982 complies with the standards and require-ments 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
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 (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 i
51 of the Commission's regulations and all appli, cable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. OPR-46 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8203220031 820303 PDR ADOCK 05000298 P
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This license amendment is effective as of its date of issuance.
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FOR THE NUCLEAR REGULATORY COMISSION p __/_ n_
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t Domenic B. Vassallo, Chief l
Operating Reactors Branch #2 i
Division of Licensing i
Attachment:
Changes to the Technical i
Specifications Dated: March 3,1982 it l
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ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE N0. OPR-46
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DOCKET N0. 50-298 Remove page 115 of the Appendix "A" Technical Specifications and i
replace with the enclosed page.
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ENCLOSURE A LIMITING CONDITIONS FOR OPERATION SURUEILLANCE REQUIREMENTS 3.5.A
(.c ont ' d. )
4.5.A (cont'd.)
2.
From and after the date that one of 2.
When it is determined that one core the core spray subsystems is made or spray subsystem is inoperable, the found to be inoperable for any reason, operable core spray subsystem, the LPCI subsystem and the diesel gener-continued reactor operation is per-ators shall be demonstrated to be missible during the succeeding seven days provided that during such seven operable immediately. The operable core spray subsystem shall be demon-days all active components of the strated to be operable daily there-other core spray suasystem and active after.
components of the LPCI subsystem and the diesel generators are operable.
3.
LPCI subsystem testing shall be as follows:
3.
Both LPCI subsystems shall be opera-ble:
Item Frequency (1) prior to reactor startup from a a.
Simulated Auto-Once/ Operating Cold Condition, except as matic Actuation Cycle specified in 3.5.F.7, or Test (2) when there is irradiated b.
Pump Operability Once/ month fuel in the vessel and when the reactor vessel pressure c.
Motor Operated once/ month is greater than atmospheric Valve Operability pressure, except as specified in 3.5.A.4 and 3.5.A.5 below, d.
Pump Flow Rate once/3 months During single pump LPCI, each RHR pump shall deliver at least 7700 GPM but no more than 8400 GPM against a system head equivalent to a reactor vessel pressure of 20 psid above dry-well pressure with water level below the jet pumps.
At the same condi-tions, two pump LPCI flow shall be ar least 15,000 GPM.
Recirculation pump discharge valves e.
shall be tested each refueling outage'to verify full open to full 4.
From and after the date that one of losed in 20 $ t f 26 seconds.
the RHR (LPCI) pumps is made or found to be inoperable for any reason, con-4.
When it is determined that one of the tinued reactor operation is permissi-RHR (LPCI) pumps is inoperable at a ble only during the succeeding thirty time when it is required to be operatir days provided that during such thirty the remaining active components of the days the remaining active components LPCI subsystems, the containment cool-of the LPCI subsystem and all active ing subsystem, both core spray system components of both core spray sub-and the diesel generators shall be systems and the diesel generators are demonstrated to be operable immediatet 21 operable.
and the operable LPCI pumps daily thereafter.
Amendment No. Jd' 76
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