ML19332C714

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Delineates Util Understanding of 891117 Telcon Re Actions to Be Taken Concerning Defueling of Plant
ML19332C714
Person / Time
Site: Fort Saint Vrain 
Issue date: 11/21/1989
From: Crawford A
PUBLIC SERVICE CO. OF COLORADO
To: Weiss S
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
P-89457, NUDOCS 8911280460
Download: ML19332C714 (3)


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Public Service' O*;%.

f-P.O. Box B40 Denver CO 80201 0840 A. Clegg Crawford November 21, 1989 Vice President Fort St. Vrain

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Unit No. 1 P-89457 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D. C. -20555 Attn: Mr. Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate t

Docket No. 50-267

SUBJECT:

NRC/PSC Telephone Conversation of November 17, 1989

REFERENCES:

See Attachment

Dear Mr. Weiss:

A telephone conversation between you and Mr. P. B. Erickson of the

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NRC and Mr. H. L. Brey and Mr. M. H. Holmes of Public Service Company of-Colorado (PSC) took place on November 17, 1989.

This letter delineates PSC's understanding of the significant results of this conversation and actions to be taken relative to the defueling of the Fort St. Vrain Nuclear Generating Station (FSV).

o NRC is in the process of final review of Technical Specifications amendments submitted in References I through 6.

Approval by the NRC of these Technical Specifications to allow defueling is projected in l

the December 4-8 time frame.

Boronated graphite defueling elements will not be placed into the FSV reactor prior to this approval, o

PSC will provide to the NRC a request to amend the FSV license to prohibit future operation of the reactor.

This license amendment will be submitted prior to initiation of defueling.

However, because current Technical Specifications (LC0 4.7.1) preclude PSC from bringing the reactor critical, defueling may commence prior to formal approval by NRC of this license amendment.

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P-89457 November 21;1989-o L

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LThe' NRC has reviewed the PSC defueling Safety s

IJ Analysis' Report (Reference 7) and. PSC's responses to questions on the SAR.

It is PSC's understanding that NRC does not intend to formally reply to this document.

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o Technical Specification amendments submitted in

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References 4 and 5 provide minor adjustments to the i

same Technical Specifications submitted in.

References 1 through 3,

and it is.

PSC's understanding that these will not require formal noticing by NRC, It is also PSC's understanding that regardless of how NRC chooses tu disposition l.

these amendments, the approval date for the

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Technical. Specifications relating to the defueling of the FSV reactor is projected to be on or. before December 8, 1989,

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If.you have any questions regarding this letter, please contact Mr.

. M. H. Holmes at (303) 480-6960.

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Very truly yours, f

A. &-

A..C, Crawford Vice President Nuclear Operations

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. Attachment cc:

Regional Administrator, Region IV ATTN: - Mr T. F, Westerman, Chief e

Projects Section B Mr. Robert Farrell b

Senior Resident Inspector Fort.St. Vrain V

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Attachment to' P-89457-Page 1.of 1 K-

REFERENCES:

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. 1..PSC: letter, Crawford to Weiss, Dated September 14, 1989

- ( P.-89341).

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2.

PSC.- letter, Crawford to Weiss, Dated. September 14','1'989.

-(P-89344)'

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PSC letter,LCrawford to Weiss, Dated September 14, 1989' F-(P-85350) p

.4.

PSC '. ~ 1etter, Crawford to Weiss, Dated October 13, 1989 (P-89394)-

5.

PSC letter,. Crawford.to Weiss, Dated October 13, 1989-

(F-89395).
6..PSC. letter,. Crawford to Weiss, Dated October 30, 1989 (P-89428)

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- 7. : PSC-letter, Crawford to Weiss, Dated August 16,-1989(P-

89287)'

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