ML17335A263

Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp

ML17335A263
Person / Time
Site:	Cook
Issue date:	10/08/1998
From:	Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17335A264	List: ML17335A263 ML17335A265
References
AEP:NRC:1317, NUDOCS 9810130323
Download: ML17335A263 (10)

Text

REGULA Y INFORMATION DISTRIBUTIO, SYSTEM (RIDS)

ACCESSION NBR:9810130323 DOC.DATE: 98/10/08 NOTARIZED: YES DOCKET FACIL:$0-'315 Dopald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315

.,y30-".16 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION POWERS,R.P. Indiana Michigan Power Co. (formerly Indiana 8 Michigan Ele RECXP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Applica'tion for amends to licenses DPR-58 5 DPR-74,revising C TS Containment Sys Bases 3/4.6,.1.4 re internal pressure &,

3/4.6.1.5 re air temp.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution E

NOTES:

6 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD3-3 LA 1 1 PD3-3 PD 1 1 STANG, J 1 1

'NTERNA XLE C ER 1 1 NRR/DE/ECGB/A 1 1 MCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

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Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071373 AEP:NRC:1317 October 8, 1998 10 CFR 50.92 Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-Pl-17 Washington, D.C. 20555-0001 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION AMENDMENT CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE and 3/4.6.1.5 AIR TEMPERATURE This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) bases for Cook Nuclear Plant units 1 and 2. This amendment proposes to change Containment Systems T/S bases 3/4.6.1.4, Internal Pressure, and 3/4.6.1.5, Air Temperature.

Background information relevant to the T/S and our analyses concerning significant hazards considerations is contained in attachment 1 to this letter. Attachment 2 contains current T/S pages marked up to show where the bases changes will be made.

Attachment 3 contains the new proposed T/S bases pages.

The proposed change has been reviewed by the plant nuclear safety review committee and the nuclear safety and design review committee. We request that the approved T/S amendment be effective thirty days from issuance.

In accordance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the oi Michigan Public Service Commission and the Michigan Department of y0 Public Health.

SWORN TO A SUBSCR D BEFORE ME.~,

f .~ r THIS DAY OF 1998",

R. P. Powers Vice President

~e %J 1J g Notary ublic

/jmc VhlERIE L BUNNEU.

Attachments My commission Expires I~

Vy~ Public, Beiien Counly, N 9810130323 '781008 9 PDR ADQCK 05000315 P PDR Q

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U.ST Nuclear Regulatory Commission AEP:NRC:1317 Page 2 c: J. A. Abramson J. L. Caldwell, w/attachments MDEQ B DW & RPD NRC Resident Inspector, w/ attachments J. R. Sampson, w/attachments

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U. S. Nuclear Regulatory Commission AEP:NRC:1317 Page 3 bc: T. P. Beilman w/attachments E. R. Eckstein/D. R. Hafer/K. R. Baker J. J. Euto FOLIO w/attachments B. J. Hickle G. Honma J. B. Kingseed/G. P. Arent/ M. J. Gumns J. F. Stang, Jr., NRC - Washington, DC, w/attachments

ATTACHMENT 1 TO AEP:NRC:1317 SUPPORTING ANALYSES FOR TECHNICAL SPECIFICATION AMENDMENT CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE and 3/4.6.1.5 AIR TEMPERATURE

Attachment 1 to AEP:NRC:1317 Page 1

~Back round Technical Specifications 3/4.6.1.4, Internal Pressure, and 3/4.6.1.5, Air Temperature, involve a containment pressure and temperature parameter (0.3 psig and 60'F respectively) that must be monitored and controlled during reactor operation. These two parameters are limited by the T/S to ensure the validity of initial condition assumptions used in the calculation for peak containment pressure following a loss of coolant accident(LOCA).

This calculation was the basis for a 12 psig design pressure for the Cook Nuclear Plant containments. The bases description of

.these two operating limits unnecessarily references the current calculated value (11.49 psig) of the peak containment pressure following a LOCA. Because a specific number is provided, changes to the plant or refinements in analysis that result in a change to the maximum calculated peak containment pressure also require changes to these two bases sections. The last such change was made in amendments 214 and 199, for units 1 and 2 respectively, as a result of refined analysis performed for 'the unit 1 30% steam generator tube plugging amendment.

Inclusion in the bases of the current specific calculated value of 11.49 psig for peak containment pressure is not necessary for an understanding and appreciation of the two operating limits controlled by T/Ss 3.6 '.4 and 3.6.1.5. Further, the 12 psig containment design pressure limit is already included in both bases sections. Therefore, this amendment request is proposing to modify T/S bases 3/4.6.1 4 and 3/4.6.1.5 by deleting reference

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to the specific numerical value of 11.49 psig currently calculated for the peak containment pressure following a LOCA.

Descri tion of Amendment Re uest In T/S bases 3/4.6.1.4 Internal Pressure, delete the second paragraph stating, "The maximum peak pressure resulting from a LOCA event is calculated to be 11.49 psig, which includes 0.3 psig for initial positive containment pressure." Add a new second paragraph stating, "The calculation for maximum peak containment pressure following a LOCA assumes an initial containment pressure of positive 0.3 psig and demonstrates that the 12 psig containment design pressure will not be exceeded."

In the second paragraph of T/S bases 3/4.6.1.5, delete the second sentence, "The lower temperature limit of 60'F will limit the peak pressure to 11.49 psig which is less than the containment design pressure of 12 psig.", and replace it with, "The lower temperature limit of 60'F will limi.t the calculated peak containment pressure to less than the containment design pressure of 12 psig."

to AEP:NRC:1317 Page 2 Justification for Amendment The purpose of technical specifications 3.6.1.4 and 3.6.1.5 is to maintain the validity of containment operating assumptions made in designing the Cook Nuclear Plant containment for a peak pressure of 12 psig. The bases for these specifications are adequately described without including in the discussion a specific numerical value for the current calculated peak containment pressure. The maximum peak containment pressure calculation and the current numerical value of 11.49 psig are properly described in Chapter 14 of the Cook UFSAR. The provisions of 10 CFR 50.59 Chan es tests and ex eriments, therefore, appropriately control changes or modifications having an impact on the calculation or numerical result. Deleting the current analysis value from the T/Ss will avoid the necessity of changing the T/Ss whenever, plant modifications or refined analysis techniques result in changes to the numerical value for the peak calculated containment pressure following a LOCA.

Basis for No Si nificant Hazards Determination In accordance with 10 CFR 50.92, this proposed amendment does not involve a significant hazards consideration if it does not:

(1)involve a significant increase in the probability or consequences of an accident previously evaluated. The changes to T/S bases 3.6.1.4 and 3.6.1.5 do not involve a physical change to the plant, change in analytical technique or change to any operating limit. of the T/Ss.

Therefore the probability or consequences of accidents previously evaluated could not be impacted.

(2)create the possibility of a new or different kind of accident from any accident previously evaluated. The changes to T/S bases 3.6.1.4 and 3.6.1.5 do not involve a physical change to the plant, change in analytical technique or change to any operating limit of the T/Ss.

Therefore the possibility of a new or different kind of accident from any accident previously evaluated could not be involved.

(3)involve a significant reduction in a margin of safety.

The changes to T/S bases 3/4.6.1.4 and 3/4.6.1.5 do not involve a physical change to the plant, change in analytical technique or change to any operating limit of the T/Ss. Therefore the change cannot involve a reduction in a margin of safety.