ML17321A470
| ML17321A470 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/01/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0919, AEP:NRC:919, NUDOCS 8503080281 | |
| Download: ML17321A470 (12) | |
Text
REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION. NBR:8503080281 OOC ~ DATE:,85/03/01 NOTARIZED'O DOCKET' FACIL:50 315 Donald C.
Cook Nuclear Power Planti Unit 1i Indiana L
05000315 AUTH BYNAME AUTHOR AFFILIATION ALEXICH<M,P, Indiana 8 Michigan Electric Co, RECIP ~ NAME.-
RECIPIENT AFFILIATION DENTONgH ~ Rs Office. of Nuclear Reactor Regulationi Director
~
SUBJECT:
. Application for amend to License OPR 58ir eyisipg, Tech specs
-to make footnote to Surveillance. Requirement 0 ~ 5,2',f in Unit 1 identical to corresponding footnote." in Unit 2" Tech Specs>
Fee paid, DISTRIBUTI N CODE:
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.COPIES RECEIVED:LTR L'NCL SIZE; TITLE; I.i cense Fees NOTES:
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INDIANA8 NICHIGAN ELECTRIC CONPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March 1, 1985 AEP:NRC:0919 Donald C. Cook Nuclear Plant Unit No.
1 Docket No. 50-315 License No.
DPR-58 MINIFLOW RATE TECHNICAL SPECIFICATIONS CHANGE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/S) for the Donald C.
Cook Nuclear Plant Unit No. 1.
Specifically we are proposing to make the footnote to Surveillance Requirement 4.5.2.f in Unit 1 identical to the respective footnote in Unit 2.
The reasons for the proposed change and our analysis concerning significant hazards considerations are contained in Attachment 1 to this letter.
The proposed revised Technical Specification page is contained in Attachment 2.
We believe that the proposed change will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, and (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and by the Nuclear Safety and Design Review Committee (NSDRC).
In compliance with the requirements of 10 CFR 50.91(b) (1), a copy of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. G. Bruchmann of the Michigan Department of Public Health.
Pursuant to 10 CFR 170.12(c),
we have enclosed an application fee of
$150.00 for the proposed amendments.
8503080281 850301 PDR ADOCK 05000315 j
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'Mr. Harold R. Denton AEP:NRC:0919 This document, has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, I
M.
. Al xich Vice Pr sident MPA/cm Attachments cc:
John E. Dolan W. G. Smith, Jr.
Bridgman G. Bruchmann R. C. Callen G. Charnoff NRC Resident Inspector Bridgman
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ATTACHMENT 1 TO AEP:NRC:0919 REASON AND 10 CFR 50.92 ANALYSIS FOR CHANGE TO THE DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 TECHNICAL SPECIFICATIONS
a
ATTACHMENT 1 TO AEP:NRC:0919 The purpose of this change is to allow the flow balancing of the Safety Injection System after the implementation of a modification which would increase the flow through the recirculation oircuit (miniflow) of the Safety In)ection pumps.
This change is identical to the one approved for Unit 2 in Amendment 64 and desoribed in our letters AEP:NRC:0860A and AEP:NRC:0860B (dated March 15, 1984 and March 23, 1984 respectively).
Based on the above, the proposed T/S change may result in some increase to the consequences of a previously analyzed accident or may reduce in some way a safety margin, but it is our belief that the results of the change are clearly within all acceptable criteria with respect to the system and components as they may affect the Safety Analysis of the plant.
Thus, the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92.
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ATTACHI1ENT 2 TO AEP:NRC:0919 PROPOSED CHANGE TO THE DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 TECHNICAL SPECIFICATIONS
EMERGEttCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued f.
By perforaing a flow balance test during shutdown following colpletion of modifications to the ECCS subsystem that alter the subsystem flow characteristics and verifying the following flow rates:
Boron Injection System Sin le P
Safety Injection System Sin le P
Loop 1 Boron Injection Flow 117.5 gptl Loop 2 Boron Injection Flow 117,5 gpm Loop 3 Baron Injection Flow 117.5 gpm Loop 4 Boron Injection Flow 117.5 gpm Loop 1 and 4 Cold Leg Flow ) 300 gpm Loop 2 and 3 Cold Leg Flow ) 300 gpm The flow rate in each Boron Injection (BI) line should be adjusted to provide 117.5 gpss (nominal) flow into each loop.
Under these conditions there is zero miniflow and 80 gpm simulated RCP seal injection line flow.
The actual flow in each BI line may deviate from the nominal sa lang as the difference between the highest and lowest flow is 10 gpm or less and the total flow to the four branch lines does not exceed 470 gptI.
Minimum flow (total flow) required is 345.8 gpa to the three most conservative (lowest flow) branch lines.
- Combined Loop 1,2,3, and 4 Cold Leg Flow (single pump) less than or equal to 640 gpm.
Total SIS (single pump) flow, including miniflow, shall not exceed 700 gpm.
0.
C.
COOK - UNIT 1 3/4 5-6a Aaendment No.