ML20073H558

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Discusses Alternative Method of Monitoring Containment high- Range Radiation Monitors,Per Amend 116 to License DPR-16. Justification Provided to Support Conclusions That Addl Preplanned Monitoring of Monitors Unwarranted
ML20073H558
Person / Time
Site: Oyster Creek
Issue date: 04/24/1991
From: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C321-91-2060, TAC-64015, TAC-64381, NUDOCS 9105070174
Download: ML20073H558 (2)


Text

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.e GPU Nuclear Corporation

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= gf r 388 Forked River, New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:

April 24,1991 C321-91-2060 U.S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555 Gentlemen:

Subjects Oyster Creek Nuclear Oenerating Station (OCNGS)

Docket No. 50-219 License No. DPR-16 Containment High Range Radiation Monitors - Alternative Monitoring References (1) NRC Letter, March 31, 1987,'" Oyster Creek Nuclear l Generating Station - Containment High Range Radiation Monitors (TSCR 152, TAC 64381 and 64015)." i The Reference (1) letter provided approval of Amendment No. 116 to Provisional Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station.

The safety Evaluation, sections 2.1 and.2.3, enclosed with the Reference (1) letter requested a technical specification be proposed for a proplanned alternative method of monitoring containment radiation to be initiated if both containment high range radiation monitors are inoperable for more than 7 days or to provide justification for not needing this technical specification for Oyster Creek.=

GPU Nuclear has evaluated existing plant features and procedures, and concluded

.that based on the following justification an additional preplanned method of monitoring' containment radiation is not warranted.

The containment high range radiation monitors are redundant and therefore can tolerate single failure. Currently, the containment high range radiation monitors function to observs release of radioactive materials into the drywell during and following an accident. During and following an accident, any exhaust through the main stack would be monitored by the high range RAGEMS

noble gas monitor (Technical Specification 3.13.G.3). In addition, the existing Oyster Creek Nuclear Generating Station post-accident sampling and analysis procedure for the PASS addresses isotopic analyses of iodine and particulate cartridges for drywell dome and ring header samples.

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  • C321-91-2060 Page 2 I

In summary, independent plant features currently exist to replace the functions of the containment high range radiation monitors in the unlikely event of oosh high range monitore being inoperable for more than 7 days.

If you have any questions on this submittal, please contact Mr. Michael W.

Laggart, Manager, corporate Nuclear Licensing at (201)3'.6-7968 Si cerely, f?

J.,J.yor .

a ikee , Oyster Creek JJE/RZ/ pip j  !

cc: Administrator, Region I Senior NRC Resident Inspector oyster creek Project Manager RZ C3212060

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