ML18191A230: Difference between revisions
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| issue date = 08/23/1977 | | issue date = 08/23/1977 | ||
| title = General Electric Report NEDC-21581-P Final Report, In-Plant Safety-Relief Valve Discharge Load Test, Monticello Plant | | title = General Electric Report NEDC-21581-P Final Report, In-Plant Safety-Relief Valve Discharge Load Test, Monticello Plant | ||
| author name = Sobon L | | author name = Sobon L | ||
| author affiliation = General Electric Co | | author affiliation = General Electric Co | ||
| addressee name = Stello V | | addressee name = Stello V | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:STANDARD DIST.OF INC01'IING TOPI GENERIC LETTERS 8 TOPICAL REP S ON NARK I CONTAINIIIENT NRC FORM 195 12.76) | {{#Wiki_filter: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 &<< | ||
AffidavtIti | 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 | ||
~~~notorized 8/17/77-"Final Report, In-Plant Safety/Relief Valve Discharge Load'est, Monticello Plant"-~--+)gag(f(II fggg (1~1/2")BQÃ0'CENTRAL.FILES 2 NRC PDR LPIP OH'4 Y NSIC L.g Q O&t Y TIC LPfZ.os C ICE 7)ACRS 16 L.SHAO 4 G.LAINAS 4<J.P.IQJIGHT 2>4/ | Consists of the following: | ||
AffidavtIti~ ~ ~ notorized 8/17/77- | |||
V.Stello, Director Gentlemen: | "Final Report, In-Plant Safety/Relief Valve Discharge Load'est, Monticello Plant"- | ||
~--+ | |||
PLANT. NAME: Monticello )gag(f(II fggg (2-P) (1 ~ 1/2") | |||
BQ Ã0 gg5 ~46,~au /oC) t'I SF.R~ | |||
SZ~V Ve d. I FOR ACTION/INFORMATION | |||
'CENTRAL. FILES 2 NRC PDR LPIP OH'4 Y NSIC L.g Q O&t Y TIC LPfZ. os C ICE 7) | |||
ACRS 16 INTERNALOl RIBUTION L. SHAO 4 G. LAINAS 4 < HHcr r8w W J. P. IQJIGHT 2 > 4 / ~ QE YOUQ BUTLE 4 STOLZ W kV , ShJG.LL WS I L DAVIS LEAR 2 W7 REID 4 47 H IA/FR. | |||
MOORE M D. | |||
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 ~ | |||
77>XXO ohio 69 | |||
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 -'~ | |||
jpj~ | |||
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:== | ==SUBJECT:== | ||
GENERAL ELECTRIC REPORT NEDC-21581-P "FINAL REPORT, IN-PLANT SAFETY/RELIEF VALVE DISCHARGE LOAD TEST, HONTICELLO PLANT" | |||
==Reference:== | ==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) | |||
i | |||
.4A}} | |||
Latest revision as of 21:57, 20 October 2019
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"-
~--+
PLANT. NAME: Monticello )gag(f(II fggg (2-P) (1 ~ 1/2")
BQ Ã0 gg5 ~46,~au /oC) t'I SF.R~
SZ~V Ve d. I FOR ACTION/INFORMATION
'CENTRAL. FILES 2 NRC PDR LPIP OH'4 Y NSIC L.g Q O&t Y TIC LPfZ. os C ICE 7)
ACRS 16 INTERNALOl RIBUTION L. SHAO 4 G. LAINAS 4 < HHcr r8w W J. P. IQJIGHT 2 > 4 / ~ QE YOUQ BUTLE 4 STOLZ W kV , ShJG.LL WS I L DAVIS LEAR 2 W7 REID 4 47 H IA/FR.
MOORE M D.
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 ~
77>XXO ohio 69
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 -'~
jpj~
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)
i
.4A