ML19332F280

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Responds to Generic Ltr 89-19 Re Resolution of USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Facility Has Been Shut Down Permanently & Being Defueled,Therefore No Further Action Required
ML19332F280
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/08/1989
From: Crawford A
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-A-47, REF-GTECI-SC, TASK-A-47, TASK-OR GL-89-19, P-89463, NUDOCS 8912140212
Download: ML19332F280 (3)


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i A. Clegg Crawford Vice President

' December'8, 1989 Nuclear Operations

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'p-89463 U.S.- Nuclear Regulatory Commis sion ATTN: Document Control Desk

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PSC Response to Generic Letter l

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REFERENCE:

NRC Generic Letter 89-19, dated September 20, 1989 (G-89350)

Gentlemen:

In ' the reference cited above, the NRC transmitted Generic Lotter

-.89-19.concerning a Request for Action Related to Resolution of

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Unresolved Safety Issue A-47 " Safety Implications of -Control Systems j

in. LWR Nuclear Power Plants" pursuant to 10 CFR 50.54(f).

In this

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' letter, the NRC concluded that protection should be provided for l

certain : control ' systems failures and that selected emergency l

procedures' should be modified to assure.that plant transients j

resulting from control system failure do not compromise public l

safety.

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As PWRs and BWRs could be subject to transients potentially resulting j

in the overfill of steam generators and reactor vessels

-(respectively), the staff concl.1ded that all PWR plants should provide automatic steam generato overfill protection and that all j

BWR plants should provide at tomatic reactor vessel overfill J

protection. Additionally, the staJf stated that plant procedures and

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technical specifications should pro ride for operability verification of the overfill protection and to assure that it is available to j

mitigate ' main feedwater overfeed events during reactor power operation.

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PubliciSorvice Company of LColorado (PSC) lias reviewed.thisl letter for i

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applicability 1to the L Fort St. Vrain~- Nuclear:. Generating ? Station.

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' thei nature 'of" its design,.: the' Fort St. Vrain High' Temperature Gas

. Cooled Reactor cannot-accomodate the recommendations'provided in;this

' letter. J PSC has also -determined that 'aince ~ Fort 4 St. Vrain) has been -

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T Whutdawn (permanently; ~~and11s - in..the process 'of. being: defueled, noi Efurther: action is required' relativ's to.the concerns raised in' Generic:

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Should-you, have any-questions concerning this matter, please contact?

Mr.. David C. Goss (303) 480-6959;for further assistance.

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Very truly yours,-

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.A. C. Craw ord Vice President' Nuclear. Operations

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-Attachment i

Reg onal Administrator, Region IV

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. ATTN:

-Mr. T.F. Westerman, Chief

. Projects Section.B

. Mr.LRobert Farrell

Sonior;Rosident Inspector

' Fort St..Vrain.

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'A.E Clegg' Crawford -being first duly sworn,-deposes and says: That,he 'is' Vice, President,, Nuclear ~ Operations, :of-Public J Service i. Company 1 of ~ = Colorado,.the Licensee herein, that he hasiread the.information presented in the - attached letter-and' knows'.the contents thereof, and; that: the

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statements and matters set forth therein !are true:'and correct' to. the best of his knowledge,.information'and.

belief.:

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A.- Clegg'Crawfond' Vice President l

Nuclear 0perations j

l STATE OF COLORADO

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COUNTY OF DENVER

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Subscribe and sworn to before me, a Notary Public on this' l

8th

day of December

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My commission expires January 6

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