ML17321A752
| ML17321A752 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/30/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17321A753 | List: |
| References | |
| AEP:NRC:0942A, AEP:NRC:942A, NUDOCS 8508060166 | |
| Download: ML17321A752 (6) | |
Text
REGUI ATOR INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8508060166 DOC, DATE! 85/07/30 NOTARIZED; NO DOCKET' FACIL':50"315 Donald C.
Cook Nuclear Power Planti Unit 1i Indiana 8
05000315 AUTH~ NAME AUTHOR AFFILIATION ALEXICHrM,P, Indiana 8 Michigan Electric Co.
RECIP.NAi'iE.'ECIPIENT AFFILIATION DENTON~H,Re Office of Nuclear Reactor Regulationi Director
SUBJECT:
Application for amend to License DPR-58ichanging Tech Spec Tables 2<2 1<3,2."1 8 3.3 3 to accomodate use of Rdf resistance temp devices w/error in calibr allowance.Fee'aidy DISTRIBUTION CODE:
A001D COPIES RECElyED:LTR ENCL g SIZE:
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OR Submittal:
General Distribution NOTES: OL;10/25/74 05000315 RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL; ACRS 09 ELD/HDS3 NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAB RGN3 COPIES LTTR ENCL 7
7 6
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1 1
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RECIPIENT ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB METB REG FI E
04 COPIES LTTR ENCL 1
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EXTERNAL: 24X LPDR NSIC 03 05 1
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 July 30, 1985 AEP:NRC:0942A Donald C.
Cook Nuclear Plant Unit No.
1 Docket No. 50-315 License No. DPR-58 APPLICATION FOR AMENDMENT TO TECHNICAL SPECIFICATION Tables 2.2-1, 3.2-1 and 3.3-3 (RdF RTDs)
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 attachment constitute an application for amendment to the Technical Specifications (T/S) for the Donald C. Cook Nuclear Plant Unit No. 1.
Approval of the proposed amendment is requested to accommodate startup of Unit 1 which is currently scheduled for initial criticality on August 18, 1985.
These Technical Specifications will have to be in place at, least two days before this date so we can proceed with certain tests prior to the initial criticality of Cycle 9.
This letter proposes changes to T/S Table 2.2.-1 Functional Unit 7, Functional Unit 8, and Functional Unit 12; Notes associated with Table 2.2-1; Table 3.2-1, Limits for Reactor Coolant System Temperature (T
); and Table 3.3-3 and associated footnotes.
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'estinghouse Electric Corporation notified us on May 2, 1985 that they had found an error in their calibration allowance for RTDs manufactured by RdF.
We have been informed that they also notified you of this change in their letter dated May 6, 1985.
As you were informed in that, letter, the calibration performed by RdF was not compatible with Westinghouse instrument uncertainty assumed in the analysis.
Westinghouse is currently evaluating the impact, if any, of the calibration error on the Unit 1 safety analyses.
The proposed changes would accommodate the use of any of 16 RdF Resistance Temperature Devices (RTDs) in Unit 1 with this new error.
Two of the RdF RTDs are already installed in Unit 1 as spares.
The remaining
,14 RTD are being installed during the current refueling outage as replacements for Rosemount manufactured RTDs.
As indicated by the attached proposed T/S pages, the RTDs are used for temperature input to Overtemperature AT, Overpower AT, Loss of Flow, DNB protection, and T low-low Essential Safety Features (ESF) Actuation.
avg Contingent upon Westinghouse completing the above evaluation, we have identified the attached T/S pages that will be affected by the change in RTDs.
The attached T/S pages have been marked with brackets,
[ ], to identify where numbers may change as a result of the Westinghouse evaluation.
The new numbers and their justification will be fo arded to the NRC when received from Westinghouse.
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Mr. Harold R.
Den AEP:NRC:0942A With regard to the changes other than those associated with Table 3.3-3 we believe the Westinghouse evaluation will result in changes to accommodate the new instrument uncertainty, but will not change the results of the analysis itself.
The changes associated with Table 3.3-3 are to allow the startup of Unit 1 to continue during the time calibration data from the RdF RTDs is being evaluated.
The proposed change will delete, only at the beginning of the cycle, the requirement that the narrow range T
low-low ESF actuation signal be operational above the P-12 permissive.
ava During this time, the T safety signals associated with Table 3.3-3 will be placed in the trippei condition.
This will assure that the associated safety functions will be accomplished if necessary.
Since we are not changing the results of the analysis, we believe these changes will not involve a significant hazards consideration as defined by 10 CFR 50.92.
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.
Should our review of the results of the Westinghouse evaluations conclude otherwise, we will so notify you.
These proposed changes will be reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee upon receipt of the results of the Westinghouse'evaluation.
In compliance with the requirements of 10 CFR 50.91(b)(1),
a copy of this letter and its attachment has 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.
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In order to expedite this letter Corporate',review procedures have not been fully completed.
Upon completion of those procedures we will notify you of any changes to this application that are required.
Very truly yours, C
. P.
lexic
', Vice Preside t' 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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