ML17255A765
| ML17255A765 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/10/1984 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-TM GL-83-10D, NUDOCS 8404170087 | |
| Download: ML17255A765 (8) | |
Text
f REGULATOR NFORMATION DISTRIBUTION l'EM (RIOS)
ACCESSION NBR:8404170087 ODC ~ DATE: 84/04/10 NOTARIZED:
NO DOCKET FACIL:50 244 Robert Emmet Ginna Nuclear Plant"i Unit 1i Rochester G
05000244 AUTH,NAME AUTHOR AFFILIATION KOBERiR,N, Rochester Gas 8 Electric Corp.
RECIP ~ NAME RECIPIENT AFFILIATION CRUTCHF IELO,O ~
Operating Reactors Branch 5
SUBJFCT:
Submits final response to Generic Ltr 83>>10Di "Resolution of TMI Action II<K,3,5i.'Automatic Tr ip of Reactor Coolant Pumps'
'" Reactor coolant pump trip cr iterion based on primary 8 secondary sys pressure implemented, DISTRIBUTION CODE:
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ROCHESTER GAS AND I
5555k ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649.0001 ROGER W. KOBER VICE PRESIDENT ClECTRIC &STEAM PRODVCTION TSI.CPIIONC AREA CODE TIS 546-2700 April 10, 1984 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:
Final Response to Generic Letter No.83-10d, "Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps" R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
Previous letters dated April 22, 1983 and December 21, 1983 presented the plan for demonstrating compliance with the criteria for resolution of TMI Action Plan Requirements Item II.K.3.5 which were established in Generic Letter No.83-10d from Mr. Darrell G.
Eisenhut dated February 8,
1983.
The submittals which fulfillthe established requirements have been transmitted to you by Westinghouse Owners Group letters OG-117, dated 3/12/84 and OG-110, dated 12/1/83.
Section I of the attachment to NRC letter 83-10d discusses "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 WOG Emergency
Response
Guidelines, which has been issued to member utilities.
The implementation date for the Ginna Emergency Operating Procedures including Revision 1 is December 1985.
The RCP Trip Criterion based on primary and secondary system pressure has been implemented at Ginna.
This criterion 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, 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 Report entitled, "Evaluation of Alternate RCP Trip Criteria", which has been submitted to the NRC for review in letter OG-110.
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oATE April 10, 1984 Mr. Dennis M. Crutchfield SHEET NO 2
The Westinghouse Owners Group has also submitted 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 comprising a generic reply to NRC Generic Letter 83-10d.
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 10 CFR 50.46 be demonstrated in an Appendix K small break LOCA analysis given that the RCPs are tripped two minutes after the onset of reactor conditions corresponding to the RCP trip setpoint.
The Westinghouse Owners Group has generically verified, in the OG-117 submittal, that predicted LOCA transients presuming the two minute delayed RCP trip are nearly identical to those presented in Safety Analysis Reports utilizing the WFLASH Evaluation model.
- Thus, the docketed small break LOCA analysis for Ginna demonstrates its compliance with the Subsection 2a guidelines.
The WOG has also performed most probable, best estimate/
WFLASH analyses to demonstrate, generically, compliance with the guidelines presented in Subsection 2b of Section I of the attachment to NRC Generic Letter 83-10d.
These analyses identify that the minimum time available for operator action for the complete range of LOCA break sizes exceeds the value contained in ANSI N660; they show that reactor coolant pumps may be tripped at any time during a
LOCA event without resulting in excessive clad temperatures.
The applicability information presented in the generic report affirms the applicability of this best estimate analysis to Ginna.
Therefore, in combination with the Subsection 2a justification cited above, the best estimate analyses justify that manual RCP trip is acceptable for Ginna when RCP trip setpoints consistent with Revision 1 to the Emergency
Response
Guidelines are in use.
Furthermore, the generic report demonstrates that no additional contingency emergency procedures are required to address the scenarios which may follow a missed RCP trip setpoint.
In response to section I, subsection 3a and 3c of 83-10d, the instrumentation used to determine if RCPs should be tripped is the primary system wide range pressure indication and the steam generator pressure indication.
There are two primary system-wide range transmitters and six steam generator pressure transmitters (three transmitters per steam generator).
All transmitters are qualified to IEEE 323-1974 and IEEE 344-1975.
Operators have been trained in the use of the RCP trip criteria.
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DATE April 10, 1984 Mr. Dennis M. Crutchfield Cl SHEET NO.
3 In summary, the generic information presented by the
'estinghouse Owners Group in the reports entitled "Evaluation of Alternate RCP Trip Criteria" and "Justification of Manual RCP Trip for Small Break LOCA Events" provides the response to NRC Generic Letter 83-10d for Ginna.
The implementation of Revision 1 to the Emergency
Response
Guidelines in the plant-specific procedures with the current RCP trip setpoint resolves all issues associated with automatic tripping of the reactor coolant pumps.
V truly yours, R
er W. Kober
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