ML17321A307
| ML17321A307 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/28/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0452, RTR-NUREG-452 AEP:NRC:0906A, AEP:NRC:906A, NUDOCS 8412030401 | |
| Download: ML17321A307 (6) | |
Text
REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION,.NBR; 8412030401 DOC ~ DATE: 84/11/28 NOTARIZED:. NO.
DOCKET ¹ FACIE:50-315 Donald C.
Cook Nuclear Power Planti Unit 1i Indiana 8
05000315.
50-316 Donald C ~
Cook Nuclear Power Planti Unit 2i Indiana 3
05000316 AUTH~ NAME AUTHOR AFFILIATION ALEXICHiM,P, Indiana L.Michigan Electric Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTONiHeR ~
Office of Nuclear Reactor Regulationi Director
SUBJECT:
Requests NRC judgement re comp)iance of listed, plant procedures w/requirements of Tech Spec 4.7, 1.2",a,2.b,for turbine driven auxiliary feedwater pump, Tech Specs in Rev to NUREG"0452 (STS) do not address assumed water temp; DISTRIBUTION CODE:
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General Distr ibution NOTES!
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INDIANA 8 N ICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 November 28, 1984 AEP:NRC:0906A Donald C. Cook Nuclear Plant Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR<<74 INTERPRETATION OF THE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS FOR THE TURBINE DRIVEN AUXILIARYFEEDWATER PUMP (TDAFP)
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
Pursuant to our conversations with members of your Staff and the NRC Region IIIstaff, this letter is a request for you to provide an interpretation as to whether or not the D. C.
Cook Plant procedures, as described below, properly implement the requirements of Technical Specification (T/S) 4.7.1.2.a.2.b.
It is our current understanding that the basis of. the Technical Specification requirement for the TDAFP (T.S. 4.7. 1.2.a.2.b; "The steam turbine driven pump develops a discharge pressure of 1285 psig at a flow of 700 gpm when the secondary steam pressure is greater than 310 psig.")
was developed by degr ading the manufacturer's pump performance curve (flow vs. differential head) by 5 percent.
This degraded differential head in feet was utilized in calculating the disoharge pressure in psig, based on the specific gravity of water at 60 F.
The current plant procedure adjusts the Technical Specification required discharge pressure by establishing a-minimum discharge pressure associated with the actual oondensate temperature.
This correction allows a true oomparison of pump performance to that required in the Teohnical-Specification.
A review of past 2 years performance data was made and the maximum correction was found to be 6 psi.
The results of our examination show that the T/S, T/S Bases, and the Standard Technical Specifications for Westinghouse Pressurized Water Reactors (NUREG<<0452, Revision 4) do not address an assumed water temperature for the specified surveillance pressure of the TDAFP.
Further, it is our belief that the methodology described above provides an engineering rationale that prudently addresses the safety basis of the plant.
8412030401 841128 PDR
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Mr. Harold R.
D nton AEP:NRC:0906A This document has been prepared following Corporate procedures whioh incorporate a reasonable set of controls to insure its acouracy and completeness prior to signature by the undersigned.
Very truly yours, M.
.. Alp ich Vice Prgfsident
~i, I, I MPA/cm cc:
John E. Dolan W. G. Smith, Jr. - Bridgman G. Bruchmann R. C. Callen G. Charnoff NRC Resident Inspector - Bridgman
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