ML17325B139

Application for Amend to License DPR-74,modifying Tech Spec Table 3.2-1, DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis.Util No Significant Hazards Evaluation Encl

ML17325B139
Person / Time
Site:	Cook
Issue date:	02/03/1989
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	MURLEY T E NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17325B140	List: ML17325B139 ML17325B141
References
AEP:NRC:1070A, NUDOCS 8902080288
Download: ML17325B139 (9)

Text

A'C CKLFRATED SISTRIBUTlON DEMO.i STRATION SYSTEM REGULAT(ZNFORMATZON DZSTRZBUTZONZSTEM (RZDS)ACCESSION NBR;8902080288 DOC.DATE: 89/02/03 NOTARIZED:

NO DOCKET I FACIL:50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana&05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.

Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURDEY,T.E.

Office of Nuclear Reactor Regulation, Director (Post 870411

SUBJECT:

Application to amend DPR-74,to modify T/S Table 3.2-1 (DNB Parameters).

DISTRIBUTION'CODE:

A001D COPIES RECEIVED:LTR I ENCL J SIZE: (P+~TITLE: OR Submittal:

General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA STANGFJ COPIES LTTR ENCL 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 2 2 INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NUDOCS-BSTRACT E 01 EXTERNAL: LPDR NSIC 1 0 1 1 1 1 1 1 1 1 1 1-1 1 1 1 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 OGC/HDS1 RES/DSIR/EIB NRC PDR 1 1 1 1 1 1 1 1 1 0 1 1 1 1 R I NOrE'ro ALL RIDS~XXPIENXS.

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Indiana Wlichigan Power Company P.O.Box 16631.Columbus, OH 43216 8 AEP:NRC:1070A 10 CFR 50.90 Donald C.Cook Nuclear Plant Unit 2 Docket No.50-316 License No.DPR-74 TECHNICAL SPECIFICATION CHANGE: MINIMUM REACTOR COOLANT FLOW REQUIREMENT U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley February 3, 1989

Dear Dr.Murley:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant Unit 2.Specifically, we propose to modify T/S Table 3.2-1 (DNB Parameters) such that the reactor coolant system flow rate is expressed on a volumetric rather than a mass basis.The proposed change is intended to ensure the requirements of the safety analyses are appropriately reflected in the T/Ss.The change is similar to a change proposed for Unit 1 of the Cook Nuclear Plant in letter No.AEP:NRC:1067, dated October 14, 1988.Attachment 1 to this letter summarizes the basis for the proposed change and includes our significant hazards evaluation.

Attachment 2 contains the proposed revised T/S page.Attachment 3 contains a letter from ANF (the Cook Nuclear Plant Unit 2 fuel vendor)documenting their concurrence with the change.We believe that the proposed changes 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, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.8+02080288 8V0203 PDR ADOCK 05000~1+F'NU ot/l(

Dr.T.E.Murley-2-AEP:NRC:1070A In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr.R.C.Callen of the Michigan Public Service Commission and Mr.George Bruchmann of the Michigan Department of Public Health.This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M..Al xich Vice President ldp Attachments cc: D.H.Williams, Jr.W.G.Smith, Jr.-Bridgman G~Bruchmann R.C.Callen G.Charnoff A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:1070A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C.COOK NUCLEAR PLANT UNIT 2 Attachment 1 to AEP:NRC:1070A Page 1 We are proposing to change the minimum required reactor coolant system flog rate specified in Table 3.2-1 (DNB Parameters) from 138.6 x 10 lbs/hr to the corresponding flow rate of 364,960 gpm.This change is administrative in nature, intended to ensure consistency between the safety analysis assumptions and the T/S.The change from mass flow to volumetric flow in T/S Table 3.2-1 results from our review of the relationship between the analysis assumption and the surveillance test that ensures the safety analysis assumption is satisfied.

The safety analyses performed by Advanced Nuclear Fuels (ANF), the Unit 2 fuel vendor, make an assumption regarding the primary volumetric flow at the core entrance.The surveillance test, which is a calorimetric test, obtains the mass flow required to remove the heat generated in the core at the measured temperature difference between the hot and cold legs.The volumetric flow is approximately independent of coolant temperature.

However, the mass flow depends directly on coolant density, which does vary with temperature., In order to ensure a correct comparison between the safety analysis assumed flow and the measured flow, we propose to specify the volumetric flow in the T/Ss.The surveillance procedure will then convert the measured mass flow to volumetric flow using temperatures from the test data.The proposed minimum flow value of 364,960 gpm)s the volumetric flow corresponding to a mass flow of 138.6 x 10 lbs/hr and an inlet temperature of 542.3 F.The 364,960 gpm value is exactly 0 four times the single loop design flow value of 91,240 gpm specified in T/S Table 2.2-1.The inlet temperature of 542.3 F is consistent with the Unit 2 full power T value of 574.1 F.ANF's concurrence with the change is provi8e5 in Attachment 3 to this letter.A similar change was proposed for Unit 1 of the Cook Nuclear Plant in our letter AEP:NRC:1067, dated October 14, 1988.That letter provided the analyses and T/S changes which support our reduced temperature and pressure program for Unit 1.10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve significant hazards consideration if the proposed amendment does not: (1)involve a significant increase in the probability or consequences of a previously evaluated accident, (2)create the possibility of a new or different kind of accident from any previously evaluated, or (3)involve a significant reduction in a margin of safety.

Attachment 1 to AEP:NRC:1070A Page 2 Criterion 1 The change is administrative in nature, consisting only of changing a mass flow rate to a volumetric flow rate at the appropriate temperature.

The change does not lessen any previous requirements.

Thus, the change is not expected to increase the probability or consequences of a previously evaluated accident, nor should it reduce the margin of safety.Criterion 2 The change is administrative in nature, intended to ensure consistency between the T/Ss and the safety analysis assumptions.

Therefore, the change is not expected to create the possibility of a new or different kind of accident from any previously evaluated.

Criterion 3 See Criterion 1 above.We note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870)of amendments considered not likely to involve significant hazards consideration.

The first of these examples refers to changes that are purely administrative in nature: for example, changes to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature.

The proposed changes are intended only to ensure that currently existing analyses are reflected in the T/Ss.We believe that the changes are administrative in nature since they do not reflect new analyses or permit any'elaxation in requirements but rather'larify the relationship between analyses and T/Ss.We therefore believe that the Federal Register example cited is applicable and that the changes involve no significant hazards consideration.

Additionally, we have made an editorial change to Table 3.2-1.Mathematical symbols have been written out in words.Since these changes are purely editorial in nature, they will not increase the probability or consequences of a previously evaluated accident, will not create the possibility of a new or different kind of accident from any previously evaluated, and do not involve significant hazards consideration.

ATTACHMENT 2 TO AEP:NRC:1070A PROPOSED TECHNICAL SPECIFICATION PAGE