ML20132D410

Forwards Request for Addl Info Re RCS Pump Trip.Info Needed within 30 Days in Order to Complete Review in Timely Manner

ML20132D410
Person / Time
Site:	Waterford
Issue date:	07/16/1985
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Leddick R LOUISIANA POWER & LIGHT CO.
References
NUDOCS 8507310384
Download: ML20132D410 (7)

Text

Docket No.:

50-382 Jill 10 1985 i

Mr. R. S. Leddick Senior Vice President - Nuclear Operations Louisiana Power and Light Company 317 Baronne St., Mail Unit 17 New Orleans, Louisiana 70160

SUBJECT:

REACTOR COLANT SYSTEM PUMP TRIP As you know, the NRC has been reviewing the post-LOCA status of reactor coolant pumps regarding trip versus no trip.

This issue has been pursued via the CE Owners Group (CEOG).

AS our review nears its conclusion, we find one area, post-LOCA status of rector coolant pump seal cooling, has been accorded plant-specific status by the CEOG. Accordingly, we request that you provide your written response to the enclosed questions.

We further request that you provide your response within thirty (30) days so that we may complete our review in a timely manner.

Sincerely, George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

Enclosure:

DISTRIBUTION As stated:

' Docket File ACRS(16)

NRC PDR JPartlow cc: See next page Local PDR DGrimes PRC System EJordan NSIC LB#3 Reading JLee JWilson OELD, Attorney l

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Docket No.: $0-382 Jll 16 1985 Mr. R. S. Leddick Senior Vice President - Nuclear Operations Louisiana Power and Light Company 317 Baronne St., Mail Unit 17 New Orleans, Louisiana 70160

SUBJECT:

REACTOR COLANT SYSTEM PUMP TRIP As you know, the NRC has been reviewing the post-LOCA status of reactor coolant pumps regarding trip versus no trip. This issue has been pursued viatheCEOwnersGroup(CEOG).

AS our review nears its conclusion, we find one area, post-LOCA status of rector coolant pump seal cooling, has been accorded plant-specific status by the CEOG. Accordingly, we request that you provide your written response to the enclosed questions.

We further request that you provide your response within thirty (30) days so that we may complete our review in a timely manner.

Sincerely, George W. Knighton, Chief I

Licensing Branch No. 3 Division of Licensing

Enclosure:

DISTRIBUTION As stated:

ITocket File ACRS(16)

NRC PDR JParticw cc: See next page Local PDR BGrimes PRC System EJordan NSIC LBf3 Reading JLee JWilson OELD, Attorney LB#3/

O LD D

JWilson.dh GWKnighton 01/15/85 07/QBS 1

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UNITED STATES y'

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JUL 2 61965 Docket No.: 50-382 Mr. R. S. Leddick Senior Vice President - Nuclear Operations Louisiana Power and Light Company 317 Baronne St., Mail Unit 17 New Orleans, Louisiana 70160

SUBJECT:

REACTOR COOLANT SYSTEM PUMP TRIP As you know, the NRC has been reviewing the post-LOCA status of reactor coolant pumps regarding trip versus no trip. This issue has been pursued via the CE Owners Group (CEOG).

As our review nears its conclusion, we find one area, post-LOCA status of rector coolant pump seal cooling, has been accorded plant-specific status by the CEOG. Accordingly, we request that you provide your written response to the enclosed questions.

We further request that you provide your response within thirty (30) days so that we may complete our review in a timely manner.

Sincerely.

7+

George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

Enclosure:

As stated cc: See next page

Mr. R. S. Leddick Louisiana Power & Light Company Waterford 3 cc:

W. Malcolm Stevenson, Esq.

Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Consnission 1432 Whitney Building Office of Executive Director New Orleans, Louisiana 70103 for Operations 611 Ryan Plaza Drive, Suite 1000 Mr. E. Blake Arlington, Texas 76011 Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Carole H. Burstein, Esq.

Washington, D.C.

20036 445 Walnut Street New Orleans, Louisiana 70118 Mr. Gary L. Groesch P. O. Box 791169 Mr. Charles B. Brinkman, Manager New Orleans, Louisiana 70179-1169 Washington Nuclear Operations Combustion Engineering, Inc.

Mr. F. J. Drummond 7910 Woodmont Avenue Suite 1310 Project Manager - Nuclear Bethesda, Maryland 20814 Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Mr. K. W. Cook Nuclear Support and Licensing Manager Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Luke Fontana, Esq.

824 Esplanade Avenue New Orleans, Louisiana 70116 Resident inspector /Waterford NPS P. O. Box 822 Killona, Louisiana 70066 Mr. Jack Fager Middle South Services, Inc.

P. O. Box 61000 New Orleans, Louisiana 70161 Chairman Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge, Louisiana 70804

REQUEST FOR ADDITIONAL INFORMATION CONCERNING REACTOR COOLANT PUMP TRIP In response to Generic Letter 83-10. CEN-268, " Justification of Trip Two/ Leave Two Reactor Coolant Pump Trip Strategy During Transients," was provided by the CE Owners Group. The following paragraph is taken from CEN-268:

6.5 SERVICE WATER AVAILABILITY RCP cooling water will be isolated at some plants upon a containment isolation actuation signal (CIAS). Continuous RCP operation under this condition may lead to potential RCP damage. Low RCP cooling flow alarms are available in the control room, and timely operator action could be employed to restore essential water service. Each utility should review the RCP cooling water service system requirements on a plant specific basis and make changes as necessary. (page6-5)

This information was provided in response to a specific issue in Generic Letter 83-10,I.l(e):

" Transients and accidents which produce the same initial symptoms as a LOCA(i.e.,depressurizationofthereactorandactuationofengineered safety features) and result in containment isolation may result in the termination of systems essential for continued operation of the reactor

coolant pumps (i.e., component cooling water and/or seal injection water).

It was the intent of TMI Action Plan Item II.E.4.2 to have licensees reevaluate essential and non-essential systems with respect to containment isolation. In particular, if a facility design terminates water services l

essential for RCP operation, then it should be assured that these water services can be restored in a timely manner once a non-LOCA situation is l

confirmed, and prevent seal damage or failure.

i It should be confirmed that containment isolation with continued RCP l

operation will not lead to seal or pump damage or failure."

l 1.

Does any containment isolation signal result in the termination of systems essential for continued operation of the reactor coolant pumps? If so, l

identify the signals and systems effected.

i 2.

If essential water services are terminated, provide a description of the l

operatorguidelines, training,andproceduresinplace(ortobeimplemented) 1 which assure that these services are restored in a timely manner to prevent i

seal damage or failure, once a non-LOCA situation has been confirmed.

i i

3.

Provide confirmation, included the technical basis, thdt containment l

l isolation with continued RCP operation will not lead to seal or pump damage or failure.

2

4 4.

Since RCP trip will be required for LOCA events, assurance must be provided l

l that RCP trip, when required, will occur. To address this concern, provide l

the following infomation:

i l

(a) Identify the components required to trip the RCPs. Include relays, power supplies and breakers. Address reliability and alternate trip methods.

(b) If necessary, as a result of the location of any critical component.

l l

include the effects of adverse containment conditions on RCP trip reliability. Describe the basis for the adverse containment parameters selected.

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