ML18081A344
| ML18081A344 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/29/1979 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7910160104 | |
| Download: ML18081A344 (3) | |
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Frederick W. Schneider Vice President Pub! ic Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201 /430-7373 Production August 29, 1979 Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
NRC IE BULLETIN NO.79-06C NO. 1 UNIT SALEM GENERATING STATION Pursuant to the subject bulletin, we hereby, submit the following response:
Short-Term Actions Item 1 A.
Station Emergency Procedures have been revised such that Reactor Coolant Pumps are immediately tripped upon Reactor Trip with initiation of Safety Injection caused by low reactor coolant system pressure.
B.
A station operating memo has been issued re-quiring the presence of two licensed operators Item 2 in the control room during operation in Modes 1, 2 and 3.
A series of Loss of Coolant Accident (LOCA) analyses for a range of break sizes and a range of time lapses between initiation of break and pump trip applicable *to the 2, 3 and 4 loop plants has been performed by the Westinghouse Owners' Group.
A report surmnarizing the results of the analysis of delayed Reactor Coolant Pump trip during small loss of coolant accidents for West-inghouse NSSS will be submitted to Mr. D. F. Ross 110/J:'
7910160
\\,_
Boyce H. Grier, Director
- 8-29-79 Item: 3 Item 4*
by Mr. Cordell Reed on August 31, 1979.
In the report, maximum PCT's for each break size con-
. sidered and pump shutoff times have been provided.
The report concludes that if the reactor coolant pumps are tripped prior to the reactor coolant system pressure reaching 1250 psia, the resulting peak clad temperatures are less than or equal to those reported in the FSAR.
In addition, i:t is shown that there is a finite range of break sizes and RCP trip times in all cases 10 minutes or later, which will result in PCT's in excess of 2200°F as calculated with conservative Appendix K models.
- The operator in any event would have at least 10 minutes to trip the RCP's following a small break LOCA, especially in light of the con-servatisms in the calculations.
This is appropri-ate for manual rather than automatic action, based on the guidelines for termination of RCP operation presented in WCAP-9600.
The Westinghouse Owners' Group has developed guidelines* which were submitted to the* NRC in Section 6 and Appendix A of WCAP 9600.
The analy-ses provided as the response to Item 2 are con-sistent with the guidelines in WCAP 9600.
No changes to these.guidelines are needed for both LOCA and non-LOCA transients.
The Owners' Group effort to revise emergency procedures covers many issues, including operation of the Reactor Coolant Pumps.
The action taken in response to item 1 is sufficient as an interim measure in regards to thes*e *pumps.
The expected schedule for re~ising the *LOCA, steamline break and steam generator tube *rupture emergency pro-cedures is the following:
Mid-October:
Guidelfnes* which have been reviewed by the NRC will be provided to each utility.
Appropriate *utility personnel associated with writirig procedures will meet with the Owners' Group Subcommittee on Procedures and Westinghouse to pro-vide the background ~or revising their emergency procedures.
Boyce H. Grier, Director 8-29-79 Ttem: 5 1 to 2 months from:
Mid-.
October.
1 to 4 months from:
Mid-October Plant specific procedures will be revised.
Revised procedures will be imple-mented* and operators trained.
Analyses related to inadequate core cooling and de-finition of conditions under which a restart of the RCP's should be attempted will be performed.
Resolution of the requirements for the analyses and an acceptable sch~dule for*providing the analyses and guidelines and procedures resulting from the analyses will be arrived at between the Westinghouse Owners' Group and the NRC staff.
Long Term *Acti*ons As discussed in our re~ponse to short-term item 2,
.we do not believe that.automatic tripping of the RCP's 'is a required function based on the analyses that have been performed and the guidelines that have been developed for manual RCP tripping.
We propose that this item. be discussed with the NRC staff following their review of the Owners' Group Submittal.
If you have any further questions on this matter we will be pleased to discuss them with you.
Sincerely, CC:. Directori Office*of Inspection and Enforcement USNRC Washington, DC 20555