ML20009G225
| ML20009G225 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/23/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009G226 | List: |
| References | |
| NUDOCS 8108030458 | |
| Download: ML20009G225 (4) | |
Text
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,,(pn naug[o, UNITED STATES NUCLEAR REGULATORY COMMISSION y,
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WASHINGTON, O. C. 20665 3,
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-46 1.
The Nuclear Regulatory Comission (.the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District dated July 16,1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conf?rmity 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 cori-ducted in compliance with the Comission's regulations; D.
The issuance of this arr.endment 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 Comission's regulations and all applic3ble 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. DPR-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. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8108030458 810723 PDR ADOCK 05000298 P
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. 3.
This license amendment is effective July 16, 1981.
FOR THE NUCLEAR REGULATORY COMISSION u
Th A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Dated: July 23,1981 l
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I ATTACHMENT TO LICENST. AMENDMENT N0. 72 FACILITY OPERATING LICENSE NO. OPR-46 l
l DOCKET NO. 50-298 l
Remove page 159 of the Appendix "A" Technical Specifications and replace wf th the revised page 159.
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t, MITINS CCNDITIONS TOR 0?D3.7!0"
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- 3. 7 Containment Systems 4.7 Contain=ent Systems Applienbility:
Acelie:biliev:
Applies to the operating status of Applies to the pri=ary and secondary the prfairy and ' secondary contain-containment integrity.
ment systems.
Objective:
O_),,ie ctive:
To assure the integrity of the pri-To verify the integrity of the prt=ary mary and secondary conta1=ent systems.
and seconds.y containment.
Soecification:
Soecifiestion:
A.
Prima-v Containment
- 1. -At any time that the nuclear.tystem 1.a.
The suppression pool water level L fnssarized above a:sosphetic and te=perature shall be checked pressure or work is being done once per day.
_ which has the potential to drain the vessel, the suppression pool b.
Ynenever there is indication of water volume and te=perature shall relief valve operation or testing l
. be saintained within the following which adds hea: to the suppression limits except as specified in pool, the pool te=pern ure shal' be continually =enitcred and also 3.7.A.2. and 3575 3
ened and logp enry 5 4
- a. '. Minimum water volume - 87650 f t minutes until the heat addition
?
3 is ter=inated.
b.: Maximum water volume - 91,000 ft c.
Whenever there is indication of l
C.
MaxLnum suppression pcol temperature relief valve operation with the 1
0 during normal power operation - 90 F.
For 45 days, commencing July 16, 1981.
temperature of th-suppression pool reachine ;K p or ore and the suppression pogi temperature may the pri=a.; aolan: sys:en pres-be increased to 95 F whenever the sure grer.ter than 200 psig, an river water temperatur' is such that external visual exanination of the pool temperature c unot be main-tained below 90 F.
the suppression cha=ber shall 0
be conducted before resuming d.
During testing which adds heat to the power operation.
suppression pool, the watcr
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0 d.
A visual inspection of the temperature shall not exceed 10 F above the normal power operation suppression cha=ber interior, limit specified in c. above.
In including watei line regions, shall be =ade at each =ajor connection with such testing, the pool temperature mu';t be reduced to refueling outage.
below the normal power operation limit specified in c. above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I e.
The reactor shall be scrammed.from any operating condition if the pool temperature reaches 1100F. Power operation shall not be resumed until the pool temperature is reduced below the normal power operation limit specified in c.
.159 -
above Amendment No. 72