ML17334B552

Forwards Addl Info Requested Following 950511 Meeting W/Nrc Re Unresolved Items from Util 1993 Sys Based I&C Insp Repts 50-315/93-12 & 50-316/93-12

ML17334B552
Person / Time
Site:	Cook
Issue date:	07/07/1995
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A849	List: IR 05000315/1993012 ML17332A848 ML17332A850 ML17332A851 ML17334B552
References
AEP:NRC:1184H2, NUDOCS 9507180130
Download: ML17334B552 (8)

Text

yPRIORZTY 1e, (ACCELERATED RZDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CESSION NBR:9507180130 DOC.DATE: 95/07/07 NOTARIZED: YES DOCKET g FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk) >s-'-~

SUBJECT:

Forwards addi info requested following 950511 meeting w/NRC re unresolved, items from util 1993 sys based I&C insp repts 50-315/93-12 & 50-316/93-12.

DISTRIBUTION CODE: AP01D COPIES RECEIVED:LTR l ENCL J SIZE:P TITLE: Proprietary Review Distribution Pre Operating License & Operating R NOTES:

RECIPIENT COPXES RECIPIENT .COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: - CENTE 01 1 1 OGC/HDS2 1 0 EXTERNAL: NRC PDR 1 0 NOTE,TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5DS (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 6 ENCL 4

0 ~ ~

indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 July 7, 1995 AEP:NRC'1184H2 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 REQUEST FOR ADDITIONAL INFORMATION, SBICI INSPECTION (50-315/316-93012)

M ll 1995 a meeting was held with.

personnel at Cook Nuclear Plant to discuss NRC NRR and Region unresolved item III our 1993 System Based Instrumentation and Control Inspection (SBICI). Following the meeting, we were asked to submit additional information to the NRC. The information requested is described in Attachment 1 and is provided in the subsequent attachments.

Sincerely, Vice President pit Attachments CC: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett g(L Iiok 9507180iZO 950707 PDR ADOCK 05000315 Q PDR

eW I e t 4 y

ATTAQBKNT 1 TO AEP NRC:1184H2 DESCRIPTION OF REQUEST FOR ADDITIONAL INFORMATION SBICI INSPECTION h

9507180130

ATTACHMENT 1 TO AEP:NRC:1184H2 Page 1 e

Item 1: . Provide a copy of WCAP-13801.

Response: The requested WCAP is provided in Attachment 2.

Because the document is considered proprietary to Westinghouse, Attachment 2 also contains an affidavit for withholding the document from public disclosure.

As discussed with the NRC staff on May ll, a non-proprietary version of the document is not available at this time. A non-proprietary version can be prepared if required by the NRC.

Item 2: Provide a discussion on the exclusion of environmental allowances (pressure, temperature, seismic) for those functional units/loops considered as back-up or secondary. "

Response: The requested discussion is contained in Attachment 3.

Item 3: Discuss the need to include environmental allowances

~ due to a harsh environment (including cable resistance effects) for the main steam flow/feedwater flow mismatch trip channels.

Response: The referenced trip is not a primary trip. The issue of environmental allowances for backup trips is addressed in the response to Item 2, in Attachment 3.

I Item 4: Discuss the use of containment pressure to detect a steam line break inside containment rather than steam line flow high and its conformance to IEEE 279-1968.

Response: The requested discussion is contained in Attachment 4.

Item 5: Provide an evaluation, including equipment qualification test results, that confirms Pat the condensate storage 'tank level instrumentation will continue to perform within the required accuracy following a seismic event.

Response: The requested evaluation is contained in Attachment 5.

ATTACHKBIT 1 TO AEP:NRC:1184H2 Page 2 e

Xtem 6: A) Discuss the lack of an environmental allowance for cable and transmitters located outside containment. Xt is noted that for post accident monitoring and emergency response guidelines an environmental allowance is included for instruments and cable associated with harsh environments inside containment only. Xn addition, B) provide an analysis to show the acceptability of not including cable degradation error in the RWST level instrumentation due to routing in a harsh environment.

Response: A) The requested discussion is provided in Attachment 6.

B) A copy of our calculation ECP 1-RPC-09 (RWST Level) was provided to the NRC during the visit on Hay 11, 1995. This calculation included the effect of insulation resistance degradation, and .

demonstrated that the effect of .insulation resistance degradation due to the harsh environment was insignificant.

Item 7: Provide a copy of WCAP 7306.

Response: The requested WCAP is provided in Attachment 7. The WCAP is non-proprietary.

Xtem 8: Provide a copy of the "Defense-in-Depth" @valuation performed for the Reactor Protection and Control Process Xnstrumentation Replacement Project.

Response: The requested evaluation, is provided in Attachment 8.

ATTACHMENT 2 TO AEP:NRC:1184H2 RESPONSE TO ITEM 1 WCAP 13801 AND AFFIDAVIT FOR WITHHOLDING FROM PUBLIC DISCLOSURE