ML20010A378

Forwards Mod to Util Submittal Addressing Item II.K.2.16 of NUREG-0718,reactor Coolant Pump Seal Damage Following Small Break LOCA W/Loss of Offsite Power.Mod Should Be Inserted on Page 0-8 of App 0 to PSAR

ML20010A378
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	08/05/1981
From:	Goldberg J HOUSTON LIGHTING & POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0718, RTR-NUREG-718, TASK-2.K.2.16, TASK-TM AC-HL-AE-522, NUDOCS 8108110375
Download: ML20010A378 (4)

Text

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( Y August 5, 1981 0 Z AC-HL-AE-522 ,

Wq ,1 -5 4, 6' Mr. Harold R. Denton Office of Nuclear Reactor Regulation ro /7

-M (ifg Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Denton:

Allens Creek Nuclear Generating Station Unit 1 Docket No. 50-466 This letter modifies the submittal of Houston Lighting and Power Company addressing Item II.K.2.16, Impact of RCP Seal Damage Following Small - Break LOCA with Loss of Offsite Power, of NUREG-0718. The attached section (e) should be inserted on page 0-8 of Appendix 0 to the ACNGS PSAR. This change will be formally cubmitted by a PSAR Amendment in the near future.

Very truly yours, f

J. H. Goldberg Vice President Nuclear Engineering and Construction LJK/bai cc: (w/ attachment)

C. G. Robertson J. G. Copeland (B&B) goyo?

[> . Powell (LNRA)

R. H. Culp(LNRA)

P. A. Horn / [/

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Service List 8108110375 810805 PDR ADOCK 05000466 A PDR

. Service List Sheldon J. Wolfe, Esq., Chaiman Susan Plettman, Esq.

Atomic Safety and Licensing David Preister, Esq.

Bot d Panel Texas Attorney General's Office U.S. Nuclear Regulatory Commission P. O. Box 12548 Washington, DC 20555 Capitol Station Austin, Texas 78711 Dr. E. Leonard Cheatum Route 3, Box 350A Hon. Charles J. Dusek Watkinsville, Georgia 30677 Mayor, City of Wallis P. O. Box 312 Mr. Gustave A. Linenberger Wallis, Texas 77485 Atomic Safety and Licensing Board Panel Hon. Leroy H. Grebe U.S. Nuclear Regulatory Commission County Judge, Austin County Washington, DC 20555 P. O. Box 99 Bellville, Texas 77418 Chase R. Stephens Docketing and Service Section Atomic Safety and Licensing Office of the Secretary of Board Panel the Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555

. Richard Black, Esq.

Atomic Safety and Licensing U.S. Nuclear Regulatory Appeal Board Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 John F. Doherty James M. Scott, Jr. 4372 Alconbury Lanc #3 Houston, Texas 77021 13935 Ivy Mount Sugar Land, Texas 77478 TexPirg William Schuessler Att: Clarence Johnson 5810 Darnell Executive Director 23 Houston, Texas 77074 y,rsi of Houston Houston, Texas 77004 Stephcn A. Doggett, Esq.

P. O. Box 592 Rosenberg, Texas 77471 Carro Hinderstein 609 Fannin Street an k Suite 521 Houston, Texas 77002 3H to e Houston, Texas 77098 D. Marrack 420 Mulberry Lane J. Morgan Bishop Bellarie, Texas 77401 Margaret Bishop 11418 Oak Spring Houston, Texas 77043 Brenda McCorkle 6140 Darnell Houstan, Texas 77074 W. Matthew Perrenod

@ 0 Merrick F. H. Potthoff, III Houston, Texas 77024 1814 Pine Village Houston, Texas 77080 Wayne E. Rentfro P.O. Box 1335 Rosenberg, Texas 77471

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ACNGS-PSAR II.K.2.16 ,

The results of this leakage analysis show that, even with gross degradation of the seals, the leakage would be less than 70 gallons per minute. This amount of leakage is within normal reactor fluctuations and the nonsal vessel water level control systems will easily compensate for it. Also, 70 GPM is much less than the bounding values of loss-of-coolant accident analyses, hence there are no adverse effects on LOCA analyses.

(c) Completion Date The study is complete, and was transmitted to the NRC in Reference 1.

f (d) Program for Implementation of Results The study concluded that the leakage through a grossly f ailed RCP seal is

,[ q fe/1- of no consequence to any of the LOCA analyses. Therefore, no changes are required to implement the results.

REFERENCES

1. NEDO-24083, " Recirculation Pump Shaf t Seal Leakage Analysis", November 1976. (Licensing Topical Report)

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i 0-8 Am. Na. 59, (6/81) i

e) Need For Additional Study Even though the referenced analysis has shown that normal plant systems can easily handle the estimated consequences of a complete loss of cooling to the Recirculation pump seals, the desirability of maintaining seal integrity by ensuring continued cooling is recognized. A loss of off-site power is one potential sequence that could result in loss of all cooling water to the recirculation pump seals by tripping the CRD and EPCCW pumps.

For this reason, one of the EPCCW pumps and an associated Open Loop Cooling Water pump, have been designed to be powered from the B& lance of Plant diesel generator, a highly-reliable on-site emergency power source. This will assure the automatic availability of a cooling water supply to the re-circulation pump seals, adequate to maintain seal integrity in the event of a loss of off-site power.

Further evaluations will be conducted to determine the ne7d for and methods of providing increased protection for the recirculation pump seals.

The cooling water system and the power source for the cooling water system following a loss of off-site power will be evaluated.

The results of this evaluation will be available within 2 years of the issuance of the Allens Creek Construction Permit. The resolution of this item will be factored into the final design of Allens Creek ar.S will be submitted in the ACNGS FSAR. 5 l

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