ML20053C504
| ML20053C504 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/10/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20053C505 | List: |
| References | |
| DPR-46-A-079 NUDOCS 8206020242 | |
| Download: ML20053C504 (5) | |
Text
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NEBRASKA PUBLIC POWER DISTRICT DOCKET N0. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-46 1.
The Nuclear Regulatory Cbmmission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District dated March 23, 1982 complies with the standards and requirements of the Atomic Er.ergy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 2.
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 (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 51 of the Commission's regulations and all applicable 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. 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. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8206020242 820510 PDR ADOCK 05000298 P
2 3.
This license amendment is effective as of March 23, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION 1
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 10,1982 i
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h ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET N0. 50-298 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMEVIS 3.7. A (cont 'd.)
4.7.A (cont'd.)
d.
If specifications 3.7.A.4.a,b or c, Once each operating cycle, each vacuum c.
cannot be met, the situation shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the breaker valve shall be visually in-
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spected to insure proper maintenance
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reactor will be placed in a cold shutdown condition within the sub-and operation of the position indicatior switch. The differential pressure set-sequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
point shall be verified.
d.
Prior to t'aactor startup after each 5.
Oxygen Concentration refueling, a leak test of the drywell to suppressior: chamber structure a.
After completion of the startup test shall'bc conducted to demonstrate program and demonstration of plant that the requirement of 3.7.A.4.c electrical output, the primary con-is set.
tainment atmosphere shall be reduced to less than 4% oxygen with nitrogen 5.
Oxygen Concentration gas during reactor power operation with reactor coolant pressure above The primary containment oxygen con-a.
100 psig, except as specified in centration shall be measured and 3.7.A.S.b.
recorded at least twice weekly.
b.
Within the 24-hour period subsequent to placing the reactor in the Run mode following a shutdown, the contaf sent atmosphere oxygen concentration shall be reduced to less than 4% by volume b.
The quantity of liquid nitrogen in and maintained in this condition.
the liquid nitrogen storage tank shall De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be determined twic'e per week when the prior to a shutdown.
volume requirements of 3.7.A.S.c are in effect.
When the containment atmosphere oxygen c.
concentration is required to be less than 4%, the minimum quantity of liquid nitrogen in the liquid ~ nitrogen storage tank shall be 500 gallons.
d.
If the specifications of 3.7. A.5.a thru e cannot be met, an orderly shutdown shall be initiated and the reactor shal'. be in a cold shutdevn condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The specifications of 3.7.A.5.a thru d e.
are not applicable during a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> continuous period between the dates of March 22, 1982 and-March 25, 1982.
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B..
Standby Gas Treatment System B.
_S_tandby Gas Treatment System 1.
At least once per operating cycle the 1.
Except as specified in 3.7.B.3 below,
'10 both circuits of the standby gas treat-ment system and the diesel generators s.
Pressure drop across the. combined, HEPA filters and charcoal adsorber banks is Amendment No. 5er 79
-164 -
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e LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.7 (cont'd) 4.7 (cont'd)
E.
Drywell-Suppression Chamber E.
Drywell-Suppression Chamber Differential Pressure Differential Pressure 1,
Differential pressure between the 1.
The pressure differential drywell and suppression chamber between the drywell and shall be maintained at equal to suppression chamber shall or greater than 1.0 paid except be recorded at least once as specified in a, b, and c below, each shift.
a.
This differential shall be established within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> af ter placing the mode switch in run.
b.
This dif ferential may be de-creased to less than 1.0 paid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to placing mode switch in refuel or shut-d own.
c.
This differential may be decreased to less than 1.0 psid for a maximum of four (4) hours during required operability testing of the HPCI system pump, the RCIC system pump, and the drywell-pressure suppression chamber vacuum breakers.
2.
If the differential pressure of specification 3.7.E.1 cannot be maintained, and the differential pressure cannot be restored within the subsequent six (6) hour period, an orderly shutdown shall be initi-ated and the reactor shall be in Hot Standby in six (6) hours and in a Cold Shutdown condition within the following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
3.
The specifications of 3.7.E.1 and 3.7.E.2 are not applicable during a 48-hour continuous period betweer the dates of March 22, 1982 and l
March 25, 1982.
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Amendment No.,5f'79
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