ML20151M670

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Informs That 850823 Submittal of Final Rept on in-plant Safety Relief Valve Tests Acceptable Per License Condition 2.C.(34)
ML20151M670
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 12/20/1985
From: Butler W
Office of Nuclear Reactor Regulation
To: Kingsley O
MISSISSIPPI POWER & LIGHT CO.
References
TAC-59535, NUDOCS 8601020654
Download: ML20151M670 (3)


Text

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DEC 2 01985 Docket No. 50-416 Mr. 0 liver D. Kingsley, Jr.

Vice President, fluclear Operations Mississippi Power and Light Company P.O. Box 23054.

Jackson, Mississippi 39205

Dear Mr. Kingsley:

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - FINAL REPORT ON INPLANT SAFETY RELIEF ~ VALVE TESTS By letter dated August 23, 1985, the Mississippi Power & Light Company (MP&L) submitted the final report of inplant safety relief valve (SRV) tests as required by Paragraph 2.C.(34) in Facility Operating License tiPF-29.

In a June 6, 1985 submittal, MP&L provided preliminary results and analyses of SRV tests conducted in the startup test program and r(quested staff approval of its conclusion that these tests were sufficient to confirm structural-adequacy of the containment for SRV loadings.

In its letter dated July 23, 1985, the NRC staff prcvided its safety evaluation of the preliminary test results and analyses. The staff concluded that additional tests were not needed-to confirm structural adequacy of the containment provided the results of'the final data reduction and analyses did not show significant deviations frcm data obtained in SRV tests at the Kuosheng Nuclear Plant and the design values for Grand Gulf Unit 1.

The NRC staff.has reviewed the final report and finds that the finalized test results are mostly' enveloped either by the Kuosheng test data-or by the design values, even though there are some deviations between the preliminary analyses of test results and the finalized ones. The portions of results that are not envelcped by the design spectra are in the frequency region above 50. Hertz, which has no structural significance. The deviations in the analyses of the final test results from the preliminary analyses are due to some corrections of instrumentation errors and final data reduction. These deviations are insignificant and have no effect on the conclusions. Accordingly, the staff concludes that the containnent building response to SRV loads is acceptable and that License Condition 2.C.(34) has been satisfied.

Sincerely, Original Signed by 8601020654 851220 PDR ADOCK 05000416 Walter R. Dutler, Director P

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OEC 20 G b-Docket No. 50-416 Mr. Oliver D. Kingsley, Jr.

Vice President, Nuclear Operations Mississippi Power and Light Company P.O. Box 23054 Jackson, Mississippi 39205

Dear Mr. Kingsley:

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - FINAL REPORT ON INPLANT SAFETY RELIEF VALVE TESTS By letter dated August 23, 1985, the Mississippi Power & Light Company ~ (f1P&L) submitted the final report of inplant safety relief valve (SRV) tests as required by Paragraph 2.C.(34) in Facility Operating License NPF-29.

In a June 6,1985 submittal, MP&L provided preliminary results and analyses of SRV tests conducted in the startup test program and requested staff approval of its conclusion that these tests were sufficient to confirm structural j

adequacy of the containirent for SRV loadings.

In its letter dated July 23, 1985, the NRC staff provided its safety evaluation of the preliminary test j

results and analyses.

The staff concluded that additional tests were not needed to confirm structural adequacy of the containment provided the results 1

]

of the final data reduction and analyses did not show significant deviations frcm data cbtained in SRV tests at the Kuosheng Nuclear Plant and the design values for Grand Gulf Unit 1.

j i

i The NRC staff has reviewed the final report'and finds that the finalized test j

results are mostly enveloped either by the Kuosheng test data or by the design values, even though there are some deviations between the preliminary analyses i

of test results and the finalized ones. The portions of results that are not enveloped by the design spectra are in the frequency region above 50 Hertz, 1

which has no structural significance.. The deviations in the analyses of the final test results from the preliminary analyses are due to some corrections of instrumentation errors and final data reduction. These deviations are insignificant and have no effect on the conclusions. Accordingly, the staff concludes that the containment building response to SRV loads is acceptable and that License Condition 2.C.(34) has been satisfied.

Sincerely, Walter R. Bu er, Director BWR Project Directorate No. 4 Division of BWR Licensing cc: See next page

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Mr. Oliver D. Kingsley, Jr.

Mississippi Power & Light Company Grand Gulf Nuclear Staiton cc:

Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice

' Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Libennan, Cook, Purcell and Reynolds 120017th Streec, N.W.

Washington, D.- C.

20036 Mr. Ralph T. Lally Manager of Quality Assurance Office of'the Governor Middle South Services, Inc.

State of Mississippi P.O. Box 61000 Jackson, Mississippi 39201 New Orleans, Louisiana 70161 Attorney General Mr. Larry F. Dale, Director Gartin Building Nuclear Licensing'and Safety Jackson, Mississippi 39205 Mississippi Power & Light Company P.O. Box 23054 Mr. Jack McMillan, Director Jackson, Mississippi 39205 Solid Waste Mississippi State Board of Health Mr. R. W. Jackson,' Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Maryland 28077-1454 Alton B. Cobb, M.D.

State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident Inspector P.O. Box 1700 U.S. Nuclear Regulatory Comission Jackson, Mississippi 39205 Route 2, Box 399 Port Gibson, Mississippi 39150 President Claiborne County Board of Supervisors Regional Administrator, Region II Port Gibson, Mississippi 39150 U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Mr. Ted H. Cloninger Atlanta, Georgia 30323 Vice President, Nuclear Engineering and. Support Mr. J. E. Cross Mississippi Power & Light Company Grand Gulf Nuclear Station Site Director Post Office Box 23054 Mississippi Power & Light Ccmpany Jackson, Mississippi 39205 P.O. Box-756 Port Gibson. Mississippi 39150 Mr. C. R. Hutchinson GGNS General Manager Mississippi Power & Light Company.

Post Office Box 756 Port Gibson, Mississippi 39150 i