ML17320B083

Informs That Implementation of Rev 1 to Emergency Response Guidelines in plant-specific Procedures W/Appropriate Reactor Coolant Pump Trip Setpoint Specified Resolves All Issues Associated W/Tmi Item II.K.3.5

ML17320B083
Person / Time
Site:	Cook
Issue date:	05/30/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.05, TASK-TM AEP:NRC:0785A, AEP:NRC:785A, GL-83-10C, GL-83-10D, NUDOCS 8406040216
Download: ML17320B083 (8)

Text

REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:8406040216, DOCBDATE: 84/05/30 NOTARIZED:

NO FACIL:50 315 Donald C ~

Cook Nuclear Power Planti Unjt iq Indiana 8

50 316 Donald C.

Cook Nuclear Power PlantE Unit 2< Indiana L

'AUTH,NAME AUTHOR AFFILIATION ALEXICHEM,PE Indiana 8 Michigan Electric Co.

RECIP,NAME RECIPIENT AFFILIATION EISENHUTqD ~ G ~

Division of Licensing

SUBJECT:

Informs that implementation of Rev 1 to emergencyresponse guidelines in plant specific procedures w/appropriate reactor coolant pump trip setpoint specified resolves all issues associated w/TMI Item II.KB'

'ISTRIBUTION CODE:

AOASS COPIES RECEIVED:LTR l-ENCl g SIZE:

TITLE:

OR Submittalt TMI Action Plan Rgmt NUREG~0737 8

NUREG 06 0

NOTES!

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INDIANA 8 MICHIGAN ELECTRIC CON PANY P.O. BOX 16631 COLUMBUS, OHIO 43216 Donald C. Cook Nuclear Plant Unit Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG-0737-II.K.3.5 Trip Criteria For Reactor Coolant (Generio Letter No. 83-10d) May 30, 1984 AEP:NRC:0785A Nos. 1 and 2 Pumps Mr. Darzell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

In our previous AEP:NRC:0785 submittal dated June 2,

1983, we presented a plan for demonstrating compliance with the criter1a for resolution of TMI Action Plan requirements item II.K.3.5.

These requirements were established in letters from Mr. Daz'rell G. Eisenhut of the Nuclear Regulatory Commission to all Applioants and Licensees with West1nghouse designed Nuclear Steam Supply Systems (Genez ic Letters 83-10 c and d) dated February 8, 1983. The submittals which fulfillthe established requ1rements have been transmitted to you by WOG letters OG-117, dated March 12, 1984 and OG-110, dated December 1, 1984. Seot1on I of the attachment to Generic Letters 83-10 o and d discusses "Pump Operation Critez ia which can Result in RCP Trip Duz'ing Transients and Accidents." Subsection 1 of'eotion I presents guidel1nes for establishing setpo1nts for RCP, trip. The Westinghouse Owners Group response to this seotion of Generic Letters 83-10 c and d is contained in Revision 1 to the WOG Emergency

Response

Guidelines, which has been issued to member utilities. The implementation of ERGs is included in ouz plan to update our Emergenoy Operating Procedures. The RCP trip or1ter1on being adopted 1n the D. C. Cock Plant specifio procedure not only assures RCP trip for all losses of primary coolant for wh1eh trip is oonsidered necessary, but also permits RCP operation to continue during most non-LOCA acoidents, including steam generator tube rupture events up to the design bas1s double-ended tube rupture. The genez1c applicability of'he RCP tz ip critez 1on selected has been documented by the Westinghouse Owners Group Report entitled, "Evaluation of Alternate RCP Tr1p Criteria," whioh has been submitted to the NRC for review in letter OG-110. I 8406040218 l540530 f ) PDR ADOCK 050003i5 F PDR

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Mr. Darrell G. nhut <<2 AEPzNRCz0/GSA i The Westinghouse Owners Group has also subm1tted to the NRC, via letter OG-117, the report entitled "Justification of Manual RCP Trip for Small Break LOCA Events." As stated

above, these submittals completed the WOG documentation compr1sing a generio reply to NRC Generic Letters 83-10 c and d.

Subsection 2 of Section I of the attachment to Generic Letters 83-10 c and d provides guidance for Justification of manual RCP tr9p. Subseot1on 2a requires that oompliance with 10 CFR 50.46 be demonstrated in an Appendix K small break LOCA analysis, given that the RCPs are tz ipped two minutes aftez the onset of reaotor conditions corresponding to the RCP trip setpoint. The Westinghouse Owners Group has generically verified in the OG-117 subm1ttal, that pzedicted LOCA. transients presum1ng the two-minute delayed RCP tr1p az e nearly identical to those presented in Safety Analysis Reports utilizing the WFLASH evaluation model. Thus, the final Safety Analysis Report for the D. C. Cook Plant demonstrates its compliance with the Subseotion 2a guidelines. The WOG has also performed most probable, best estimate, WFLASH analyses to demonstrate, generically, compliance with the gu1delines presented in Subsection 2b of Seotion I of the attachment to Generio Letters 83-10 c and d. These analyses 1dentify that the m1nimum time available for operator action for the complete range of LOCA break sizes exceeds the value contained in N660 (the proposed American Nuolear Sooiety guideline on operator action time). They show that the reaotor ooolant pumps may be tripped at any time dur1ng a LOCA event without resulting in excessive clad temperatures. The applicability information presented in the generic report affirms the applicability of these best estimate analyses to the D. C. Cook Plant. Therefore, 1n combinat1on with the Subseotion 2a Justification cited above, the best estimate analyses Justify that manual RCP trip is acceptable for the Donald C. Cook Plant when RCP tr1p setpo1nts consistent with Revis1on 1 to the Emergency

Response

Guidelines are in use. Furthermore, the generic report demonstzates that no addit1onal contingency emergency procedures are required to address the scenarios which may follow a missed RCP trip setpoint. t In summary, the generic 1nformation pzesented by the Westinghouse Owners Group in a report entitled "Evaluation of Alternate RCP Trip foz Small Break LOCA Events,~ provides the response to NRC Generic Letters 83-10 c and d for the D. C. Cook Plant. The implementation of Revision 1 to the Emergency

Response

Guidelines in the plant specific procedures with an appropr1ate RCP trip setpoint specified resolves all issues assooiated with automatic tr1pp1ng of the z eaotor coolant pumps.

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Mr. Darrell G. nhut AEP:NRC 0705A This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its aocuracy and completeness prior to signature by the undersigned. Very truly yours, MPA/cm M A exich$ Vice President ~)y ~ cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman

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