AECM-85-0266, Forwards Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept. Effects of Safety Relief Valve Hydrodynamic Loads Adequately Covered in Original Plant Design.Substantial Margins in Discharge Loads Exist

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Forwards Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept. Effects of Safety Relief Valve Hydrodynamic Loads Adequately Covered in Original Plant Design.Substantial Margins in Discharge Loads Exist
ML20137H995
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/23/1985
From: Dale L
MISSISSIPPI POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20137H999 List:
References
AECM-85-0266, AECM-85-266, TAC-59535, NUDOCS 8508300102
Download: ML20137H995 (2)


Text

1 MISSISSIPPI POWER & LIGHT COMPANY

] Helping Build Mississippi BetR&lidAE P. O. B O X 164 0, J AC K S O N, MIS SIS SIP PI 39215-1640 August 23, 1985 NUCLEAR LICENSING & SAFETY DEPARTMENT U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director

Dear Mr. Denton:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/M-9050/650 SRV In-Plant Test - Final Test Report AECM-85/0266 Mississippi Power & Light (MP&L) conducted an in-plant Safety / Relief Valve (SRV) test program as required by Grand Gulf Nuclear Station (GGNS) Unit 1 Operating License Condition 2.C.(34). The test program was developed and implemented to confirm that the GGNS Unit 1 containment building response to SRV loads is acceptable. A major portion of the planned tests was conducted April 23 through April 25, 1985.

The final rest report provided as an attachment to this letter describes the testing, test instrumentation, data reduction and presents the test results. Based on the test results, MP&L concludes that the effects of SRV hydrodynamic loads have been adequately covered in the original plant design and there are substantial mt.rgins in the SRV discharge loads.

Based on conversation with the GCNS NRC Project Manager (L. L. Kintner) ten copies of the final test report are enclosed. Five (5) additional copies were transmitted separately to Mr. Kintner. MP&L considers that the attached report, which includes the test results, satisfies the requirements of Operating License Condition 2.C.(34). If you have any questions, please contact this office.

Yours truly, 8508300102 850823 -

PDR ADOCK 05000416 P PDR L. F. Dale Director MLC/JGC:vog [

Attachment cc: (See Next Page) I 0 0\

J13AECM85082301 - 1 Member Middle South Utikties System

AECM-85/0266 Page 2 cc: Mr. J. B. Richard (w/a) .

Mr.~ 0. D. Kingsley. . Jr. (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds.(w/a)

Mr. H. L. Thomas (w/o) .

.Mr. R. C.' Butcher (w/a)

Mr. James M. Taylor, Director (w/a)

Office.of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. J. Nelson Grace. . Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W.,. Suite 2900 Atlanta, Georgia 30323 J13AECM85082301 - 2