ML17321A783

Forwards Revised Tech Specs,Changing Tables 2.2-1,3.2-1 & 3.3-3 Re Rdf Resistance Temp Detector (RTD) & Two Westinghouse Proprietary Safety Evaluations Re Rdf RTD Installation.Safety Evaluations Withheld (Ref 10CFR2.790)

ML17321A783
Person / Time
Site:	Cook
Issue date:	08/13/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17321A784	List: ML17321A783 ML17321A785 ML17321A786 ML17321A787
References
AEP:NRC:0942D, AEP:NRC:942D, NUDOCS 8508150366
Download: ML17321A783 (8)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:85081503e6 DOC.DATE: 85/oe/13 NOTARIZED: YES DOCKET FACIL:50 315 Donald AUTH, NAME C ~

AUTHOR Cook Nuclear Power Pl anti Unit AFFILIATION ii Indiana 8 05000315 ALEXICHiM.P. Indiana 8 Michigan Electric Co ~

RECIP,NAt'IE RECIPIENT AFFILIATION DENTONzH ~ RE Office. of Nuclear Reactor Regulationi Director

SUBJECT:

Forwards revised Tech Specsichanging Tables 2 ' ii3 2 ~ 1 3e3 3 re RdF resistance temp detector (RTD) 8 two Hestinghouse proprietary, Safety evaluations withheld (ref 10CFR2,790).

DISTRIBUTION CODE: PA01D COPIES RECEIVED:LTR ENCL l,"

SIZE: ~"

TITLE: Proprietary Review Distribution-Operating Reactor NOTES: 05000315 OL: 10/25/74 REC IP IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR. ENCL"

'7 NRR ORB1 BC

+py~h~q 7 INTERNAL: ~)4h4Pg> ELD/HDS3 1 0 1 1 RGN3 1 1 EXTERNAL 24X 1 0 LPDR 1 0 NRC PDR 1 0 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 15

f \

~ 0 I" i'l . H K

lf 'lp 1

f 0

IN DIANA 8 M ICH IGAN ELECTRIC COM PAN Y P.O. BOX 16631 COLUMBUS, OHIO 43216 August 13, 1985 AEP:NRC:0942D Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-3'l5 License'No. DPR-58 ADDITIONAL INFORMATION FOR RdF RTD TECHNICAL SPECIFICATIONS 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 provide the numer1cal values and the safety evaluation for the Techn1cal Specification changes identified in our letter dated July 30, 1985; identif1er AEP:NRC:0942A. Attachment 1 is the propr1etary version of the safety evaluation for these"values as determined by our NSSS vendor, Westinghouse Electric Corporation. The revised Technical Specification pages are 1ncluded as Attachment 2. - Attachment 3 1s the. Westinghouse Application for Withholding Proprietary Information from Public Disclosur e, CAW-85-051, accompanying affidavit, and Proprietary Information Notice for the safety evaluations included in Attachment 1.

=As previously ind1cated, we request approval of this amendment in time to support Unit 1 startup. These Technical Specification changes will have to be in place-two days before initial oriticality.

Attachment 4 is a Westinghouse safety evaluation for operation during the interval between our obtaining the RTD cross-calibration data and the incorporation of the resulting corrections into the-instrumentation.

Attachment 5 is the Westinghouse Applicat1on for Withholding Proprietary Information from Public Disclosure, CAW>>85-053, accompanying affidavit, and "

Proprietary Information Notice for the- safety evaluations included in Attachment 4.

The non-proprietary versions of the two safety evaluations, identified as Attachments 1 and 4 above, will be sent to the U.S. Nuclear Regulatory Commission under a separate letter. ~ 'I It 1s to be noted that 1n our July 30 letter, we agreed to maintain the Tavg safety signals in the tr 1pped condition when operating above the P-12 setpoint,- if we were granted the Technical Specification changes associated with Table 3.3-3 and its notes. Subsequent to that, we were able to perform a 85081503bb 8508i3

ggg

(

'PPDR ADOCK 05000315 PDR (go( 4~>K 9n - P~

1 ) '. ~ ~

e

~ ~

l Pk *!

ll

~

kl 1

Mr. Harold R. Denton AEP:NRC:0942D safety analysis (Attachment 4) which we believe demonstrates that placing the Tavg safety signals in the tripped cond1tion is not required for the protection of public health and safety. However,-discussions with your staff have indicated that they would like the requirement to remain in con)unction with the use of the proposed footnote to-Table 3.3-3 during the current startup. We agree to this commitment for the startup of Unit 1 Cycle 9 only, in order to prov1de your staff suffic1ent time to rev1ew"the safety analysis in Attachment As th1s submittal contains information proprietary to Westinghouse Electric Corporation, it is supported by two affidavits signed by Westinghouse, the owner of the informat1on. The affidavits set forth the basis on which the information may be withheld"from public-disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

I Accordingly, it is respectfully-requested that the information which is proprietary to Westinghouse be -withheld from publ1c disclosure in accordance with 10 CFR Section 2.790 of the Commiss1on's regulations. Correspondence with respect to'the proprietary aspects of the Applications for Withholding or the supporting Westinghouse affidavits should reference CAW<<85-051 or CAW-85-053 and should be addressed to R. A. Wiesemann, Manager Regulatory and Legislative Affairs, Westinghouse Electric. Corporation, P. 0. Box 355, Pittsburgh, Pennsylvania 15230.

Based upon the Westinghouse evaluations and our -initial reviews of those evaluations, we believe that the proposed changes will not result in 1) a signif1cant change in the types of effluents or a significant increase iri the amounts of any effluent that may be released offsite, or 2) a significant increase in individual or cumulative occupational rad1ation exposure and thus do not involve a significant hazards consideration as defined by 10 CFR 50.92.

These proposed changes will be reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee at their next regularly scheduled meetings. ~-

In compliance with the requirements of 10 CFR 50.91(b)(1), a copy of this letter and its non-proprietary attachments will'e transmitted to Mr. R.C.

Callen of the Michigan Public Service Commission and Mre G. Bruchmann of"the Michigan Department of Public Health..

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,

\

M. P. Alexd hIic gs Preetdect'gl

/'Ace I

Y

~ I

~ I ~ 1 ll 1

1 I'IP c. El t' Jt. I" Yl 4 l, "1 * ~

~ 1 lg 1

I J v

Mr. Harold R. Denton JI I AEP:NRC:0942D

/bus Attachments cc: John E. Dolan W. G. Smith, Jr. - Bridgman G. Bruohmann R. C. Callen G. Charnoff--

NRC"Resident Inspector - Bridgman

0 1

~ '"z W

el "'

~

J p . ~

'1 4 ll