ML18096A668
| ML18096A668 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 04/30/1992 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.079, RTR-REGGD-1.079 NLR-N92059, NUDOCS 9205040320 | |
| Download: ML18096A668 (3) | |
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Public Service Electric and Gas Company Stanley LaBruna o.~'i'Pt,..,
Vice President - Nuclear Operations Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200
/JIR 3 o 1~\\:ll NLR-N92059 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
SAFETY EVALUATION OF THE IMPACT ON HOPE CREEK FROM THE STORAGE AND DELIVERY OF AMMONIUM HYDROXIDE AT SALEM SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311, 50-354 Public Service Electric and Gas (PSE&G) has completed the safety evaluation of the potential impact on Hope Creek from a postulated accidental release of ammonium hydroxide at Salem.
A release could occur due to a postulated failure of Salem's secondary water chemical feed system 3000 gallon storage tank or from a tank truck during delivery.
PSE&G is providing the evaluation results in response to an NRC Inspector request.
This commitment is contained in our previous transmittal dated February 28, 1992 (NLR-N92016).
The evaluation concludes that the toxic limit for anhydrous ammonia per Regulatory Guide 1.78 Table C-1 will not be exceeded within two minutes after detection and that control room habitability is maintained in accordance with 10CFR50 Appendix A General Design Criterion 19.
Four conditions were evaluated, two for the storage tank and two for the tanker truck.
Calculations performed in support of the safety evaluation used the conservative computer model "VAPOR",
applicable assumptions contained in Regulatory Guide 1.78, and design bases information.
The computer model "VAPOR" was previously discussed in our transmittals dated December 30, 1991, and February 28, 1992.
The first condition evaluated was the postulated failure of the storage tank at Salem containing a maximum design volume 'Of 3000 gallons of 27.5 wt.% ammonium hydroxide.
As a result of the potential impact on Salem, as discussed in our previous.
transmittal dated February 28, 1992 (NLR-N92016), PSE&G took conservative action that reduced the stored concentration of ammonium hydroxide to 15 wt.%.
The second condition evaluated was a postulated accidental release from the 3000 gallon storage tank containing 15 wt.% ammonium hydroxide.
Dochment Control Desk NLR-N92059 2
,.,APR., o\\~
A third condition which was evaluated involved a postulated release from a tanker truck accident during delivery.
Because the concentration of ammonium hydroxide to be stored and used at Salem was reduced from 27.5 wt.% to 15 wt.%, the frequency of delivery is anticipated to exceed 10 per year.
Therefore, in accordance with Regulatory Guide 1.78 position C.2, an evaluation of the failure during tanker truck delivery was evaluated.
The evaluation considered the postulated failure of a tanker truck containing 2000 gallons of 15 wt.% ammonium hydroxide during delivery using an established route which is the Salem auxiliary guardhouse access point.
An additional condition was evaluated for the scenario of a tanker truck using the main guardhouse access point.
If a tanker truck uses the main guard house access point, the conservative action of requiring Hope Creek's control room to go into recirculation mode will be initiated to ensure a conservative marg~n of safety.
The safety evaluations conclude that Hope Creek's control room habitability is maintained under the postulated accident conditions and that the toxic limits of Regulatory Guide 1.78 are not exceeded within two minutes using the limits for anhydrous ammonia.
Should you have any questions, please contact us.
Sincerely,
Document Control Desk NLR-N92059 3
c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager -
Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. s. Dembek, Licensing Project Manager U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (809)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Document Control Desk
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