ML18191A230

General Electric Report NEDC-21581-P Final Report, In-Plant Safety-Relief Valve Discharge Load Test, Monticello Plant

ML18191A230
Person / Time
Site:	Columbia
Issue date:	08/23/1977
From:	Sobon L General Electric Co
To:	Stello V Office of Nuclear Reactor Regulation
References
MFN-321-77
Download: ML18191A230 (4)

Text

STANDARD DIST. OF INC01'IING TOPI GENERIC LETTERS 8 TOPICAL REP S ON NARK I CONTAINIIIENT US. NUCLEAR REGUI ATORV CO ATION NRC FORM 195 12.76) WoP ic &<<

1 FILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL FROM: DATE OF DOCUMENT General Electric Company 8/23/77 Mr. Vi Stello San Jose, Cai DATE RECEIVED L Z Sobon 8/23/77 QHCOTO R IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED RELETTER ORIGINAL Q COP'V 0UNCLASSIFIED XXX I I uM DESCRIPTION ENCLOSURE I

Consists of the following:

AffidavtIti~ ~ ~ notorized 8/17/77-

"Final Report, In-Plant Safety/Relief Valve Discharge Load'est, Monticello Plant"-

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VASSALLO W 2 GOLLER QO SCHRODER W3 TEDESCO 2.

STELLO '33 EISENHUT SCHWA'/ENCER ~

SIHWEIL ~ S J. GUIBERT (2 4-EXTERNAL OISTR ISUTION CONTROL NUMBER 2 @A ~

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GENERAL ELECTRIC NUCLEAR ENERGY SYSTEMS DIVISION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 HC 681, (408)925-3495 T DEPARTMENT August 23, 1977 -'~

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Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: V. Stello, Director Division of Operating,Reactors.~,,

Gentlemen:

ALUUEQ I UIIY gg PL,,

SUBJECT:

GENERAL ELECTRIC REPORT NEDC-21581-P "FINAL REPORT, IN-PLANT SAFETY/RELIEF VALVE DISCHARGE LOAD TEST, HONTICELLO PLANT"

Reference:

Letter L. J. Sobon to V. Stello dated January 28, 1977 "In-Plant Safety Relief Valve Test - Preliminary Report" One hundred copies of the report "NEDC-21581-P, Final Report, In-Plant Safety/Relief Valve Discharge Load Test, Honticello Plant" are being provided by General Electric Company on behalf of the Hark I and II Owners Groups. As you are aware,- both of these Owners Groups have previously indicated that information obtained from safety/relief valve (SRV) tests performed at the Monticello Nuclear Generating Plant will be used to confirm and support portions of their containment evaluation programs. This report presents information on the structural and hydro-dynamic measurements obtained during the test and documents completion of Task 5.1.1 of the Mark I Program and Task B.3 of the Hark II Program.

Separate Hark I utility correspondence will reference this General Electric transmittal for use on their docket. The applicability of this report to the Hark II program will be described in the report "Hark II Containment Supporting Program Report," .Revision 1, NEDO-21297 which is scheduled for issue in August 1977.

This Final Report supersedes the reference Preliminary Report (NEDC-21465-P) entirely, therefore Preliminary Reports should be destroyed or returned to the General Electric Company.

The report, NEDC-21581-P, contains information which General Electric Company customarily maintains in confidence and withholds from public disclosure. The information has been handled and classified proprietary by General Electric as indicated in the attached affidavit. The affidavit

GENERAL ELECTRIC Attention: V. Stello Page 2 August 23, 1977 al,so contains proprietary commercial financial information. Accord-ingly, we hereby request that NEDC-21581-P and the affidavit accompany-ing this letter be withheld from public disclosure in accordance with the provisions of 10CFR 2.790.

A non-proprietary version of the report, NEDC-21581, will be provided on or before September 26, 1977.

Sincerely L. J. Sobon, Manager BMR Containment Licensing LJS:LDS:at/65-66 Attachment

'c:

L. S. Gifford (GE-Bethesda)

J. C. Guibert (NRC)

R. L. Tesdesco (NRC)

C. I Grimes (NRC)

S. Miner (NRC)

,R. S. Boyd (NRC)

R. C. DeYoung (NRC)

H. C. Brinkmann (Mark II Owners Group)

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