ML17334B286

Application for Amend to License DPR-58,modifying Tech Spec 4.1.1.5 Such That Temp Below Reactor Coolant Sys Average Temp Must Be Monitored Every 30 Minutes Reduced from 551 F to 545 F.Fee Paid

ML17334B286
Person / Time
Site:	Cook
Issue date:	12/30/1988
From:	ALEXICH M P INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	MURLEY T E NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17334B287	List: ML17334B286 ML17334B288
References
AEP:NRC:1067A, NUDOCS 8901120447
Download: ML17334B286 (11)

Text

ACCELERATED DIK+BUTION DEMONSTR+OAI SYFI'EM~~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR-8901120447 DOC.DATE: 88/12/30'OTARIZED:

NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.

Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to License DPR-58,modifying Tech Spec 4.1.1.5 re min temp for criticality.

DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL Q SIZE: 7~TITLE: OR Submittal:

General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DEST/SICB NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 0 1.1 1 1 1 1 1 1 1 0 1 1 1 1 1.1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/DOEA/TSB 11 NUDOC-BSTRACT G F g 01 NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE'ro ALL"RIDS" RECIPXZmS.

(/d cg g/<~~2.9(~g~h D S PZZASE HELP US K)REDUCE WIPE!CGHIACZ'%HE DOCUMEÃZ CONTROL DESKi ROOM P1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRZKITION LISTS FOR DOCGKBTZS YOU DGNiT NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 IMEHANll NlCMGAN ROMEO AEP:NRC:1067A 10 CFR 50.90 Donald C.Cook Nuclear Plant Unit 1 Docket No.50-315 ll License No.DPR-58 SUPPLEMENTAL TECHNICAL SPECIFICATION CHANGES FOR REDUCED TEMPERATURE AND PRESSURE PROGRAM U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Attn: T.E.Murley December 30, 1988

Dear Dr.Hurley:

This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss)for the Donald C.Cook Nuclear Plant Unit 1.Specifically, we are proposing to modify T/S 4.1.1.5 (Minimum Temperature for Criticality) such that the temperature below which the reactor coolant system average temperature must be monitored every 30 minutes is reduced from 551 F to 545 F.The change is desired since we plan to operate the upcoming Unit 1 Cycle 11 at reduced temperature and pressure (RTP)conditions.

The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The expected full power Tavg for Cycle ll is 0 approximately 550 F, reduced from the present (non-RTP)full power 0 Tavg of 567.8 F.Plant operation with the present T/S is not precluded under the RTP conditions; however, the T/S does place a burden on the plant operators since Tavg will have to be monitored every 30 minutes at essentially all times when the reactor is critical.This letter supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted the analyses that support RTP operation, as well as the T/S changes necessary to allow plant operation.

We request that your review of this request be completed by April 15, 1989, which is the same date requested in AEP:NRC:1067 for approval of the RTP analyses and associated T/S changes.pic'l pDR ADQCK 05OOo P'g,eel: 4i~~I os%~

Dr.T.E.Hurley-2-AEP:NRC:1067A Additional details about the change and our evaluation concerning significant hazards consideration are contained in Attachment 1 to this letter.The proposed revised T/S change is found in Attachment 2.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.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.Pursuant to the requirements of 10 CFR 170'2(c), we have enclosed an application fee of$150.00 for the proposed amendments.

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.P.Alexich Vice President MPA/eh Attachments cc: D.H.Williams, Jr.W.G.Smith, Jr.-Bridgman R.C.'allen G.Charnoff G.Bruchmann A.B.Davis-Region III NRC Resident Inspector-Bridgman ATTACHMENT 1 TO AEP:NRC:1067A DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C.COOK NUCLEAR PLANT UNIT 1

ATTACHMENT 1 TO AEP:NRC:1067A Page 1 Descri tion of Chan e Unit 1 Technical Specification (T/S)4.1.1.5.b (Minimum Temperature for Criticality) as presently written requires verification that the reactor coolant system Tavg is>541 F at least once per 30 minutes when the reactor is critical and Tavg is less than 551 F.We are proposing to revise the requirement such that Tavg must be verified every 30 minutes when Tavg is below/(545 F or when the low Tavg alarm is inoperable.

0 Reason for the Chan e Under present operating conditions, full power Tavg is 567.8 F.0 For the upcoming Unit 1 Cycle 11, however, we are planning to operate the plant under reduced temperature and pressure (RTP)conditions.

The RTP program supports a range of nominal full power Tavg from 547 F to 567.8 F.The full power Tavg will be lowered to approximately 550 F for Unit 1 Cycle ll.Since this 0 is below 551 F, the present wording of T/S 4.1.1.5.b would require that Tavg be verified to be above 541 F (the minimum temperature 0 for criticality) every 30 minutes essentially all times when the reactor is critical.Although this does not preclude operation under RTP conditions, it is burdensome and will distract the operators from other duties.This request supplements our letter AEP:NRC:1067, dated October 14, 1988.That letter transmitted.

the analyses which support RTP operation, as well as the T/S changes that are necessary in order to implement the RTP program.Justification for Chan e The proposed change does not alter the minimum temperature for criticality.

Tavg must be maintained above 541 F any time the reactor is critical.Should Tavg drop below 541 F, the action statement for T/S 3.1.1.5 requires that Tavg be restored above 0 541 F within 15 minutes or the unit must be placed in hot standby.T/S 4.1.1,5.b presently requires Tavg to be determined every 30 minutes when Tavg is less than 10 F above 541 F.This 10 F value is consistent with the latest revision of Westinghouse Standard T/Ss.Westinghouse has informed us the 10 F was established to protect against encroachment upon the 541 F minimum temperature 0 for criticality.

The 10 F value is not derived from any analysis.0 The plant is equipped with a low Tavg alarm that is currently set 0 at 554 F.The low Tavg alarm is derived from the bistables that close the main feedwater control valves on low Tavg coincident with a reactor trip.This function helps protect the reactor from excessive cooldown following a reactor trip.Diversity of signals

~~

ATTACHMENT 1 TO AEP'NRC'1067A Page 2 for terminating main feedwater is provided via the P-4 permissive, which trips the main feedwater pumps in the event of a reactor trip.The functions associated with the low Tavg bistable and the main feedwater pump trip on reactor trip are not delineated in the T/Ss.We are proposing to lower the low Tavg setpoint (including the alarm)from 554 F to 545 F.The temperature of 545 F is 0 0 sufficiently below the operating temperature to lessen the possibility of unnecessary.=alarms, but is high enough to provide the operator with ample warning that Tavg is approaching the 541 F 0 minimum temperature for criticality.

Lowering the low Tavg setpoint has minimal effect on the response of the plant to reactor trip because, as discussed above, the main feedpumps (MFP)are tripped directly on a reactor trip, via the P-4 permissive.

The FSAR LOCA and transient analyses do not take credit for feedwater isolation derived from the'low Tavg bistable.The function is modeled in the Westinghouse Owners Group analysis of steamline break mass and energy releases outside containment (WCAP 10961), because it is conservative to do so.Modeling of the function is conservative because it leads to earlier feedwater isolation than the other (T/S)signals that also provide feedwater isolation.

Early termination of feedwater results in greater steam generator tube uncovery, and thus more superheating of the steam exiting the break.Lowering the low Tavg setpoint is conservative with respect to this analysis, since it will somewhat delay the feedwater isolation.

We propose that the operator only be required to monitor and document Tavg on a 30-minute basis if Tavg is below the proposed low Tavg setpoint of 545 F, or if the low Tavg alarm is 0 inoperable.

This will avoid the burden that monitoring Tavg every 30 minutes places on the operators, and will help ensure the operators'ttention is not diverted from more important safety functions.

Tavg will continue to be measured at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Mode 1, as required by T/S 3.2.5 (DNB Parameters).

The resetting of the Tavg alarm to 545 F will ensure the operator is warned that Tavg is encroaching upon the 541 F minimum temperature 0 for criticality.

10 CFR 50.92 Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:

ATTACHMENT 1 TO AEP:NRC:1067A Page 3 1)Involve a significant increase in the probability or consequences of an accident previously analyzed, 2)Create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or 3)Involve a significant reduction in a margin of safety.Criterion 1 The periodic monitoring and documenting of Tavg when the plant is operated near the minimum temperature for criticality will be reduced.However, this change will be compensated for by lowering the alarm setpoint to warn the operator of approach to the minimum temperature for criticality.

Therefore, we do not believe our proposal will result in an increase in the probability or consequences of an accident previously analyzed.Criterion 2 The proposed T/S changes do not revise the minimum temperature for criticality of 541 F specified in T/S 3.1.1.5.The change only impacts the temperature at which Tavg must be monitored every 30 minutes.This will be compensated for by providing an alarm at a 0 Tavg of 545 F that will warn the operator that the plant is approaching the minimum temperature at which it may remain critical.Thus, we do not believe the change can result in any new or different kinds of accidents from any previously analyzed or evaluated.

Criterion 3 The purpose of the T/S is to ensure the reactor is not critical with Tavg below 541 F, without appropriate action being taken.We will ensure that the operator is warned that Tavg is approaching the 541 F limit by lowering the low Tavg alarm setpoint to 545 F.We believe this will provide adequate assurance that the 541 F Tavg limit is protected.

Therefore, the proposed change should not significantly reduce the margin of safety.Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing examples (48 FR 14870)of amendments considered not likely to involve significant hazards consideration.

The sixth of these examples refers to changes that may result in some*increase to the probability or consequences of a previously analyzed accident, but the results of which are within limits established as acceptable.

As discussed in the bases, the minimum temperature for criticality ensures that the reactor, instrumentation, and vessel are operated in their analyzed temperature ranges.These requirements are not I C ATTACHMENT 1 TO AEP:NRC:1067A Page 4 affected by our proposed revision to the surveillance requirements.

The change only impacts the temperature at which the operator must monitor Tavg every 30 minutes to ensure the temperature does not drop below the minimum temperature for criticality.

Me will be providing an alarm that will alert the operator that the temperature is approaching its minimum Tavg limit.Therefore, we believe the example cited is applicable and that the changes should not involve a significant hazards consideration.