ML20006E146
| ML20006E146 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/13/1990 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Cottle W SYSTEM ENERGY RESOURCES, INC. |
| Shared Package | |
| ML20006E147 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-69057, NUDOCS 9002220161 | |
| Download: ML20006E146 (1) | |
Text
F February 13, 1990 Docket No. 50-416 DISTRIBUTION Doctet m e LKintner NRC & Local PDRs OGC Mr. W. T. Cottle PD21 R/F EJordan Vice President, Nuclear Operations SVarga System Energy Resources, Inc.
CWHehl ACRS(10)
Post Office Box 469 ETourigny Port Gibson, Mississippi 39150
Dear Mr. Cottle:
SUBJECT:
GRANDGULFNUCLEARSTATION, UNIT 1(GGNS.1).DRYWELLPRESSURE NARROW RANGE INSTRUMENT TO MEET REGULATORY GUIDE 1.97 REQUIREMENTS (TAC NO 69057)
By letter dated July 22, 1988, System Energy Resources, Inc. (the licensee) requested the NRC to review its position statement regarding a deviation from the guidelines of Regulatcry Guide 1.97, " Instrumentation for Light-Water.
Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and FollowinganAccident"(RG1.97). The deviation is use of a containment-to-drywell differential pressure instrument with a range of +2 psid to -2 ptid and a wide range drywell pressure instrument with a range of -10 to 40 psig instead of the RG 1.97 recommended drywell pressure instrument with a range of
-5 psig to 3 psig.
The NRC staff has reviewed this requested deviation.
The staff's Safety Evaluation is enclosed. We conclude that the licensee has adequately justified this deviation from the RG 1.97 recommendation.
The licensee has committed to make changes in the Updated Final Safety Analysis Report (UFSAR) to ref?ect use of the differential pressure instrument for post-accident monitoring.
The implementation date for UFSAR changes and l
any emergency operating procedure changes is December 31, 1990.
Sincerely.
Original Signed By:
Lester L. Kintner, Senior Project Manager Project Directorate 11-1 90022201619$$$h16 Division of Reactor Projects - I/II PDR ADOCK O PNV Office of Nuclear Reactor Regulation P
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Enclosure:
Safety Evaluation I
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