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Responds to NRC Request for Clarification of Startup Feedwater Pump Loading Sequence on to Emergency Bus E5,per 890630 Amend 62 to Fsar.Listed Procedures Revised to Ensure That Operators Verify Generator a Load Carrying Capability
	ML19325F077
Person / Time
Site:	Seabrook
Issue date:	10/31/1989
From:	Feigenbaum T; PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NYN-89134, NUDOCS 8911130337
	Download: ML19325F077 (12)
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i New' Hampshire fed C. Feigenboom ,

Senior Vice President and ;

Chief Operating Officer l l

NYN-89134 !

October 31, 1989 United States Nuclear Regulatory Commission l Washington, DC 20555 :

Attention: Document Control Desk

References:

(a) Facility Operating License NPF-67, Document No. 50-443 )

(b) NHY Letter NYN-89078 dated June 30, 1989, 'FSAR Amendment 62", T. C. Feigenbaum to USNRC

Subject:

Request for Additional Information Gentlemen:

l

.In Reference (b), New Hampshire Yankee (NHY) submitted Amendatnt 62 to the Seabrook Station Final Safety Analysis Report (FSAR). Amendment 62 ,

reflected control circuit enhancements which have been made to preclude automatic sequencing of the Startup Feedwater Pump (SUFP) onto an emergency diesel generator. During the review of this FSAR change the NRC Staff requested clarification of the SUFP loading sequence on to Emergency Bus E5.

The purpose of this letter is to document a discussion held with the NRC Staff on October 17, 1989. ,

.During a review of the SUFP control circuit NHY determined that in the unlikely situation where the SUFP had under contingency conditions been manually transferred by operator action to Bus E5, wac operating on Bus E5 and a loss of offsite power occurred, the SUFP would be shed from Bus E5 along with other loads and then automatically reconnected to Bus E5.during diesel load sequencing.

To prevent this unlikely event from occurring, a control circuit 3 enhancement was made as indicated on the attached schematic diagrams.

If the SUFP'is operating on Bus E5 and a loss of offsite power occurs then the following typical operator action would be taken in accordance with applicable i procedures: ,

- The pump trips on Bus E5 undervoltage. ,

- The pump is prevented from restarting until the diesel generator has completed sequencing and the operator has depressed the Remote Manual Override (RMO) reset pushbutton and the operator has placed the pump control switch in ]

stop/ pull to lock and the operator then returns the pump '

control switch to auto. gong 8911130337 891031 gDR ADOCK0500g3 ,

g New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

Sobrook, NH 03874 = Telephone (603) 474 9521 l

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Procedures E-0. ES-0.1 E-3, FR-H.1, ECA-0.1 and ECA-0.2 were revised to address concerns identified in NRC Inspection Report Unresolved Item 87-16-13 and subsequently closed in Inspection Report Number 50-443/88-10. These procedures were revised to ensure that operators would verify that emergency diesel generator 1A would have adequate load carrying capability before loading the SUFP onto Bus E5.

Therefore, before the SUFP is manually started by the operator, if required, it will be assured that sufficient emergency diesel generator capacity exists.

NHY believes that the above clarification adequately addresses the Staff's request, and should you have any questions regarding this matter, please contact Mr. Robert E. Sweeney at (301) 656-6100.

Very truly yours,

'f Ted C. Feigenbaum f

Enclosure e cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commi,sion Region I 425 Allendale Road King of Prussia, PA 19406 Mr. Yi. tor Nerses, Project Manager Project Directorate I-3 Division of Reactor Projects United States Nuclear Regulatory Commission Washington, DC 20555 NRC Senior Resident Inspector Seabrook Station Seabrook, NH 03874 l

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ML19325F077

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References:

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