JPN-95-017, Advises That Util Abandoning Temporary Exemption to 10CFR50, App R for Pump Room Ventilation

Advises That Util Abandoning Temporary Exemption to 10CFR50, App R for Pump Room Ventilation

ML20081L809
Person / Time
Site:	FitzPatrick
Issue date:	03/28/1995
From:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-95-017, JPN-95-17, NUDOCS 9503310022
Download: ML20081L809 (3)

Text

' 123 Main' Street White Plains. New York 10601

• 914 4 81 4 840 914-287,3309 (FAX) b William J. Cahill, Jr.

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.M80d$ Chief Nuclear Officer March 28,1995 JPN-95-017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Appendix R Exemption On Pump Room Ventilation  ;

REFERENCES:

Ne4 page

Dear Sir,

The Authority has recently completed an analysis (Reference 1) where the continued

< operation of the FitzPatrick North and South Safety Related Pump Rooms was evaluated in the event of ventilation system loss due to a postulated fire in the Screenwell House. This analysis demonstrates that pump performance will not be degraded in the event of ventilation system ,

loss due to a postulated fire in the Screenwell House. Based on that analysis, the Authority is abandoning the temporary exemption to 10 CFR 50, Appendix R (Reference 4) for these rooms.

The Authority reported in LER 91-021-00 (Reference 2) the possible degradation of the ventilation systems in the North and South Safety Related Pump Rooms in the event of a fire in the Screenwell House. These rooms contain the Emergency Service Water (ESW) and -

Residual Heat Removal Service Water (RHRSW) pumps. The Authority subsequently requested a temporary exemption (Reference 3) to a!!ow time to develop and install a modification. The request detailed interim compensatory actions which would remain in effect until modifications to the ventilation systems could be completed. The NRC granted this temporary exemption in Reference 4.

f In lieu of a modification, the Authority undertcak an analysis to determine if a postulated fire in the Screenwell House, which degraded or disabled the ventilation for the pump reoms, would cause the ESW or the RHRSW pumps to overheat. The analysis (Reference 1) determined that, with certain additional combustible controls (i.e., restrictions on amounts and placement of combustibles) for the Screenwell House, pump performance would not be i degraded even with the loss of ventilation systems during a postulated fire. The analysis modeled the Pump Rooms and the Screenwell House including the Screenwell House combustible loading. Resultant fires were then computer modelled to predict the temperature and smoke profiles in the Pump Rooms. The results of the analysis are acceptable and modifications to the ventilation system are unnecessary.

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The configuration used in the model reflects the actual plant configuration and analysis reconimendations have been incorporated into the applicable FitzPatrick procedures to maintain the appropriate administrative control of combustibles. Examples of these administrative controls include, but are not limited to, increased fire inspectivts, fire watches, etc.

Both the analysis (Reference 1) and the revised FitzPatrick procedures are available at FitzPatrick for NRC review. There are no new commitments being made in this letter.

If you have any questions, please contact Ms. C. D. Faison.

Very truly yours, t

William J. Cahill, Jr.

Chief Nuclear Officer Nuclear Generation

REFERENCES:

1. FitzPatrick Screenwell Smoke and Hot Gas Analysis, Engineering Planning and Management / Hughes Associates, Inc., dated September 23,1994.

2. FitzPatrick LER 91-021-00, dated November 27,1991, regarding Residual Heat Removal, Emergency Diesel Generators and Fire j Pumps potentially made inoperable due to inadequate modification installation activities, transmitted by NYPA letter, R. J. Converse to the NRC, dated November 27,1991 (JAFP-91-0786). i

3. NYPA letter, R. E. Beedle to the NRC, dated June 26,1992 (JPN-92-032), regarding revised, new or temporary exemptions from 10 CFR 50, Appendix R.

4. NRC letter, R. A. Capra to R. E. Beedle, dated September 10,1992, regarding issuance of exemptions from requirements of 10 CFR Part 50, Appendix R for the James A. FitzPatrick Nuclear Power Plant (TAC No. M83969). l I

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Regional Administrator. _ ,

, ' 1. U.S. Nuclear Regulatory Commission  !

-475 Allendale Road King of Prussia, PA 19406.. .;

4 . Office of the Resident inspector

. U.S. Nuclear Regulatory Commission i y

.P.O. Box 136 i

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' Lycoming, NY 13093 j ,

Mr. C. E. Carpenter, Jr., Project Manager i Project Directorate 11 .;

Division of Reactor Projects - 1/ll- .

U.S. Nuclear Regulatory Commission -!

Mail Stop 14 B2  !

Washington, DC 20555.  ;

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