ML20071F574
| ML20071F574 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/16/1978 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810200100 | |
| Download: ML20071F574 (4) | |
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(412) 471-4300 435 Sinth Avenue
$'$urgh, Pennsylvania October 16, 1978 Director of Nuclear Beactor Regulation United States Nuclear Regulatory Commission Attention:
A. Schwencer, Chief Branch No. 1 Division of Operating Reactors Washington, D. C.
20555
Reference:
Beaver Valley Power Station, Unit No. 1 DockctNo.(50-334N Correction to ber 4, 1978 Request for Amendment Gentlemen:
Enclosed are three (3) signed originals and thirty-seven (37) copies of cot re cted Proposed Technical Specifications 3.1.2.3 and 3.4.1.4.
Our October 4, 1978 submittal did not properly include the required action statements and surveillance requirements for these specifications, and in addition T.S. 3.4.1.4 was incorrectly numbered 3.4.14.
Please rep'.tce the incorrect copies of the Proposed Technical Specifications in our October 4, 1978 submittal with these corrected pages.
It should be noted that these specifications have been prepared to
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be consistent with NUREG 0452 dated June 15, 1978.
It is our understanding that this is the latest issue of Standardized Technical Specifications.for Westinghouse PWRS.
We have also referenced T.S. 4.0.5 (Pump Testing in accordarice' with AS!!E Section XI) which we have assumed will be approved prior toIthe issuance of these proposed specifications.
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Very truly yours, C. N. Dunn Vice President, Operations Attachment
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1810Aootos [
y (CORPORATE SEAL)
Attest:
H. W. Staas Secretary COMMONWEALTH OF PENNSYLVANIA)
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COUNTY OF ALLEGHENY
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On this N
day of t cJR^-
1978, before me,
' tnWATD WmSHANNON a Notary Public in and for said Ccmmonwealth and County, personally. appeared C. N. Dunn, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Sub-mittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
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. L Js DONALD W. SHANNON. Nctary Public Pittsburgh, Allegheny Co., Pa, My Commission Expires June 7,1979 t
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ch PROPOSED TECHNICAL SPECIFICATION REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1. 2. 3 One charging pump in the boron injection flow path required by Specification (3.1.2.1) shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY: MODES 5 and 6.
9 ACTION:
With no charging pump OPERABLE, suspend all operations involving CORE ALTERNATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.
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SURVEILLANCE REQUIREMENTS 4.1. 2. 3.1 The above required charging pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of > 2402 psig when tested pursuant to Specification 4.0.5.
4.1.2.3.2 All charging pumps, except the above required OPERABLE pump, shall be deaonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verifying that the motor circuit breakers have been removed from their electrical power supply circuits.
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,'y PROPOSED TECHNICAL SPECIFICATION 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS NORMAL OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.4 A reactor coolant pump in a non isolated loop shall not be started with one or more of the non isolated RCS cold leg temperature 1 275 F unless:
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The pressurizer water volume is less than 1120 cubic feet or 2.
The secondary water temperature of each steam generator is less than 50 F above each of the RCS cold leg temperatures.
APPLICABILITY: tiodes 4 & 5 ACTION:
With the pressurizer water volume greater than 1120 cubic feet or the temperature of the steam generator in the loop associated with the reactor coolant pump being started greater than 50 above the cold leg temperature of the other non isolated loops, suspend the start-up of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS:
4.4.1.4 The pressurizer water volume and the secondary water temperature of the non isolated steam generators shall be determined within ten minutes of starting a reactor coolant pump.
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