ML17255A588

Responds to Generic Ltr 83-10D, Automatic Trip of Reactor Coolant Pumps. Partial Response Submitted W/Westinghouse Owners Group 831201 Ltr.Generic Rept Justifying Manual Reactor Coolant Pump Trip Will Be Submitted by 840301

ML17255A588
Person / Time
Site:	Ginna
Issue date:	12/21/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-2.K.3.05, TASK-TM GL-83-10D, NUDOCS 8401040137
Download: ML17255A588 (6)

Text

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ACCESSION NBRs8u02040231 DOC.DATE: 83/22/22 NOTARIZED> No DOCKET FACILt50 244 Rober't Emmet.AGinna Nuc1 ear:Pl ant r Uni t 2 g Rochester G 05000244 AUTH ~ 'NAME'- AUTHOR AFFILIATION MAIERiJ ~ E ~ Rochester Gas 8 Electric Corp>

REC IP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELD<D ~ Operating Reactors Branch 5 SUBJEOT: Responds to,Generic Ltr'3 2,0dr "Automatic Trip of Reactor Coolant Pumps;" Partial-;response submitted w/Nestinghouse Owners Group 831201 l tr,'Generic'r ept Justifying manual reactor coolant pump tr ip will be submitted by 840301.

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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E< MAIBR TELEPHONE Vice Preeicient AREA coDE 7ie 546 2700 December 21, 1983 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Response to Generic Letter No.83-10d, "Automatic Trip of Reactor Coolant Pumps" R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

Our previous letter to you on the above subject dated April 22, 1983 presented the plan for demonstrating compliance with the criteria for resolution of TMI Action Plan Item II.K.3.5 which were established in letters from Mr. Darrel G. Eisenhut of the Nuclear Regulatory Commission to all Applicants and Licensees with Westinghouse,.designed Nuclear Steam Supply Systems (83-10d) dated February 8', 1983. This lettei presents the status of the planned responses to NRC Generic Letter 83-10d. The date by which all parts of the program are to be completed has now been revised to March 1, 1984. However, a submittal to partially fulfill the reguirements has been transmitted to you by WOG letter OG-110, dated December 1, 1983 (Sheppard to Mattson).

Section I of the attachment to NRC Letter 83-10d is concerned with "Pump Operation Criteria Which Can Result in RCP Trip During Transients and Accidents." Subsection 1 of Section I presents guidelines for establishing setpoints for RCP Trip. The Westinghouse Owners Group response to this section of NRC Letter 83-10d is contained in Revision 1 to the Emergency Response Guidelines, which has been approved and issued. The criterion for tripping the RCPs has already been incorporated as was committed to in our April 22, 1983 letter.

The RCP Trip Criterion, which has been adopted in the Ginna specific procedures, not only assures RCP trip for all losses of primary coolant for which trip is considered necessary, but also permits RCP operation to continue during most non-LOCA accidents,

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ROCHESTER GAS AND ELECTRIC CORP. SHEET NO.

DATE December 21, 1983 To Mr. Dennis M. Crutchfield including steam generator tube rupture events up to the design basis double-ended tube rupture. The generic applicability of the RCP trip criterion selected has been documented by the Westinghouse Owners Group in "Evaluation of Alternate RCP Trip Criteria", September, 1983, which as stated above has been submitted to the NRC for review.

Subsection 2 of Section I of the attachment to NRC Letter 83-10d provides guidance for justification of manual RCP trip.

Subsection 2a requires that compliance with 10CFR50.46 be demonstrated in an Appendix K small break LOCA analysis given that the RCPs are tripped 2 minutes after the onset of reactor condi-tions corresponding to the RCP trip setpoint. Westinghouse has completed generic verification for the Westinghouse Owners Group that predicted LOCA transients presuming the 2 minute delayed RCP trip are nearly identical to those presented in Safety Analysis Reports utilizing the WFLASH Evaluation Model. Thus, the Safety Analysis Reports for all plants are a valid means to demonstrate compliance with the Subsection 2a guidelines.

Westinghouse is now performing better estimate WFLASH analyses to demonstrate, generically, compliance witE the guidelines presented in Subsection 2a of Section I of the attachment to NRC Generic Letter 83-10d. These analyses will identify the minimum time available for operator action for a range of break sizes such that the ECCS acceptance criteria of 10CFR50.46 are not exceeded. It is expected that the minimum time available for operator action will be acceptable. Combined with the Subsection 2a justification, this will justify manual RCP trip for all plants. Rochester Gas and Electric will review this analysis for applicability to Ginna. It is expected that this report will resolve the RCP trip issue.

The Westinghouse Owners Group intends to submit the generic report justifying manual RCP trip by March 1, 1984. This will complete the documentation comprising a generic reply to NRC Generic Letter 83-10d.

Very truly yours, John E. Maier

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