ML19325F389

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Forwards Rev 3 to Fire Protection Plan for Fort St Vrain Nuclear Generating Station, for Review & Approval.Proposed New Fire Protection Cooldown Trains Rely Solely on Pcrv Liner Cooling for Core DHR
ML19325F389
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/08/1989
From: Crawford A
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19325F391 List:
References
P-89431, NUDOCS 8911210033
Download: ML19325F389 (4)
v • d • e


Text

-

L S

y I hPublic Service-s fa.*tah..

(O B"c5 80s-a November 8, 1989 g

Fort St. Vrain Unit No. 1 P-89431 A. Clegg Crawford p

$c'E*o$$on.

U.

S.' Nuclear Regulatory Commission ATTN: Document Control Desk 6,

Washington, D.C.

20555 Docket No. 50-267

SUBJECT:

Fire Protection Program Plan Revision 3

References:

1)

PSC Letter, Crawford to Au Weiss, Dated (P-89287) gust.16, 1989 2)

NRC Letter, Denton to Walker, Dated February 7, 1986 (G-86062)

Gentlemen:

Enclosed is one (1) signed original and ten (10) additional copies of Revision 3 to the Fire Protection Program Plan (FPPP) for Fort.St.

Vrain Nuclear Generating Station (FSV) which is being submitted in accordance with 10 CFR 50.71(c) for NRC review and approval.

The principal changes in Revision 3 involve two new Fire Protection Cooldcwn Trains (Trains 1 and 2), which will replace the existing trains (Trains A and B).. The proposed new Fire Protection Cooldown Trains rely solely on PCRV liner cooling for core decay heat removal.

Due to the present low levels of decay heat generation resulting from shutdown of FSV on August 18, 1989, forced circulation cooling is no longer necessary to prevent fuel damage in the event of a fire. As discussed in Section 5.2.7 of the Defueling Safety Analysis Report, submitted to the NRC in Reference 1 PCRV liner cooling (one loop) has the capability to remove sufficient decay heat to ensure maximum temperatures of the fuel, PCRV liner, concrete, and outer liner insulation cover plates remain below their normal operating temperatures in the event of a permanent loss of forced circulation.

The proposed new Fire Protection Cooldown Train 1 uses the electric 1

motor-driven firewater pump, powered by the ACM Diesel Generator, to supply water to Loop 2 of the PCRV liner cooling system, in an open

. loop cooling mode. Makeup water is supplied to the firewater pump pit by a circulating water makeup pump, also powered by the ACM Diesel Generator.The NRC previously performed a Safety Evaluation on this cooling mode for a permanent loss of forced circulation from 35%

A00b i \\0 8911210033 89110s hDR ADOCK 05000267 PDC

g P-89431 Page 2 4

. November 8,~1989 I

power, as' documented in. Reference 2, with the conclusion that for. the depressurized mode of cooling, which is' the preferred mode, the licensee can operate the Liner Cooling System with fire water to prevent significant~ damage to any of the fission product barriers."

i N

The proposed new Fi re' Protection Cooldown Train 2 uses one of the lant cooling water pumps in the reactor plant cooling Loop 2 reactor p(System water system

46) to provide cooling water flow through the Loop'2 PCRV cooling tubes in a closed loop cooling mode.

Heat is removed by the System 46 heat exchat,gers, cooled by service water.

Standby Diesel Generator IB-supplies power to the electrical equipment in Train 2.

This is the cooling mode evaluated by FSAR Section 14.10 and Appendix D for Design Basis Accident No.1, a

permanent loss of forced circulation.

These trains have the advantage of exceptionally good separation of equipment and cabling from the alternate train, since nearly all Train 1 electric equipment and cables are located outside the Reactor ano. Turbine Buildings. A relatively small number of components in each train is relied upon to cool down following a fire. Train 1 is relied upon to remove core decay heat in the event of 6 fire in a congested cable area.

The FSV FPPP has also been revised to document changes in loadings of certain combustibles which have taken place since the FSV shutdown, i

Hydraulic oil has been drained from the hydraulic oil system.

Hydrogen for main turbine generator cooling has been completely removed from the Turbine Building.

The presence of graphite defueling elements, stored on the Turbine Deck, and increased levels of combustibles on the Fuel Deck, are discussed.

In addition, FPOR-16, Issue 4. FPOR-17, Issue 4, and FPOR-21, Issue 1, are being submitted in accordance with 10 CFR 50.71(e).

FPOR-16 Issue 4,

contains the list of equipment in the proposed new Fire Protection Cooldown Trains.

FPOR-17 is being deleted. FPOR-21 Issue l

1, defines requirements for the Site Fire Brigade, equivalent to those in Technical Specification AC 7.1.1.

A 10 CFR 50.59 evaluation l

was performed on FPOR-16, FPOR-17, and FPOR-21. The evaluation l

determined that the revisions were safety related, but were not safety significant and did not involve or create an unreviewed safety question. The revisions do not require changes to the FSV Technical l.

Specifications.

Revision 3 of the FPPP will not be distributed and implemented until NRC approval has been received. Until such time as Revision 3 is approved, the current Revision 2 of the FPPP, Issue 3 of FPOR-16, and Issue 3 of FPOR-17, will remain in effect.

PSC intends to discuss the proposed new Fire Protection Cooldown Trains in the meeting between PSC and the NRC on November 16, 1989,

r g.

p F

P-89431-Page 3-

~ ' '

November 8, 1989 s'

E at FSV.

PSC will also review the other changes made to the FPPP, in Revision 3, at this meeting.

w-If you have an questions or comments, please contact Mr. M. H.

Holmes, at(303)y480-6960.

Very truly yours, A. Clegg Crawford Vice President Nuclear Operations i

ACC/BRD/drg Enclosure cc: Regional Administrator, Region IV Attention: Mr. T. F. Westerman, Chief Projects Section B (with one copy of Revision 3 to the FPPP)

Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain (with one copy of Revision 3 to the FPPP)

Mr. D. J. Kubicki U.S.N.R.C. Fire Protection Engineer Chemical Engineering Branch I

W.-

J.

p' W

.P-89431 Page 4

-November 8, 1989 i

p UNITED STATES OF AMERICA x

L NUCLEAR REGULATORY COMMISSION

[. -

In the Matter i"

Public Service Company of Colorado Docket No. 50-267 Fort St. Vrain Unit No. 1 AFFIDAVIT A.

Clegg Crawford being first duly sworn, deposes and says: That he is Vice President, Nuclear Operations, of Public Service Company l

of Colorado, the Licensee herein, that he has read the information presented in the attached letter and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

42 dh A. Clegg Crawfor F Vice President Nuclear Operations STATE OF COLORADO COUNTY OF DENVER Subscribe and sworn to before me, a Notary Public on this 8th day of November

, 1989 l

fM mt246 Notary Public My commission expires January 6

, 19,9,3 l

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