ML20246F463: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 4
| page count = 4
| project =  
| project = TAC:65690
| stage = Approval
| stage = Approval
}}
}}
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                 .the ASME Code. The program is submitted to the NRC for review and approval.
                 .the ASME Code. The program is submitted to the NRC for review and approval.
The review entails verifying that the program is based on the applicable Code edition addenda, verifying that the program covers testing of all appropriate pumps ana valves, and verifying the acceptability of the requests for rclief from the requirements of Subsection IWP and IWV.
The review entails verifying that the program is based on the applicable Code edition addenda, verifying that the program covers testing of all appropriate pumps ana valves, and verifying the acceptability of the requests for rclief from the requirements of Subsection IWP and IWV.
The IST program adoressed in this report covers the second ten-year interval from April 17, 1985 to April 17, 1995. Rancho Seco's program was st.bmitted in a letter dated January 28, 1988. This report incorporates the review of Rancho Seco's IST program through revisions identified in a submittal to NRC dated February 15, 1988.
The IST program adoressed in this report covers the second ten-year interval from April 17, 1985 to April 17, 1995. Rancho Seco's program was st.bmitted in a {{letter dated|date=January 28, 1988|text=letter dated January 28, 1988}}. This report incorporates the review of Rancho Seco's IST program through revisions identified in a submittal to NRC dated February 15, 1988.
The FRC staff, with technical assistence from EG&G Idaho, Inc. (EG&G) has reviewed ana evaluated the IST program and requests for relief submitted for Rancho Seco.
The FRC staff, with technical assistence from EG&G Idaho, Inc. (EG&G) has reviewed ana evaluated the IST program and requests for relief submitted for Rancho Seco.
The steff adopts the evaluations and conclusions contained in the Technical Evaluation Report (TER) prepared by EG&G. The enclosed SER incorporates the TER and its findings.
The steff adopts the evaluations and conclusions contained in the Technical Evaluation Report (TER) prepared by EG&G. The enclosed SER incorporates the TER and its findings.

Latest revision as of 23:31, 16 March 2021

Forwards Safety Evaluation & Technical Evaluation Rept Supporting Util Inservice Testing Program for Pumps & Valves.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable
ML20246F463
Person / Time
Site: Rancho Seco
Issue date: 05/04/1989
From: Reynolds S
Office of Nuclear Reactor Regulation
To: Firlit J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML20246F466 List:
References
TAC-65690, NUDOCS 8905120256
Download: ML20246F463 (4)


Text

___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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,[- Waroq[4 g UNITED STATES y -i g g NUCLEAR REGULATORY COMMISSION

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Jq, rj WA"HINGTON, D. C. 20555

%*'****/a May 4, 1989 o

Docket No. 50-312 Mr. Joe Firlit Chief Executive Officer, Nuclear Rancho Seco Nuclear Generating Station 14440 Twin Cities Road

'ferald, California 95638-9799

Dear Mr. Fir 11t:

SUBJECT:

INSERVICE TESTING PROGRAM FOR RANCHO SECO NUCLEAR GENERATIls j STATION (TACNO.65690}

The NRC staff has reviewed Rancho Seco's inservice testing (IST) program for pumps and values. The results of tbc staff review are provided in the enclosed Satety Evaluation Report.

TheCodeofFederalRegulations, paragraph 10CFR50.55a(g)requirescertalti Class 1, 2, ano 3 pumps and valves in water-cooled nuclear reactor facilities to meet the inservice testing requirements stated in the ASME Boiler ard Pressure Vessel Code,Section XI; specifically, Subsection IWP, Inservice Testing of Pumps in Nuclear Power Plants, and Subsection IWV, Inservice Testing ~of Valves in huclear Power Plants. Each facility is required to establish a progrcm for the inservice testing of pumps and valves which is updated every ten years to meet the requirements in the latest approved edition and addenda to Section XI of

.the ASME Code. The program is submitted to the NRC for review and approval.

The review entails verifying that the program is based on the applicable Code edition addenda, verifying that the program covers testing of all appropriate pumps ana valves, and verifying the acceptability of the requests for rclief from the requirements of Subsection IWP and IWV.

The IST program adoressed in this report covers the second ten-year interval from April 17, 1985 to April 17, 1995. Rancho Seco's program was st.bmitted in a letter dated January 28, 1988. This report incorporates the review of Rancho Seco's IST program through revisions identified in a submittal to NRC dated February 15, 1988.

The FRC staff, with technical assistence from EG&G Idaho, Inc. (EG&G) has reviewed ana evaluated the IST program and requests for relief submitted for Rancho Seco.

The steff adopts the evaluations and conclusions contained in the Technical Evaluation Report (TER) prepared by EG&G. The enclosed SER incorporates the TER and its findings.

Certain relief requests have been denied where proposed alternative testing is unacceptable or where an acequate basis for the relief request has not been provided. The NRC staff has determined that the IST program is acceptable for in.plementation providec the omissicos and inconsistencies identified in Appendix C of the TER are addresste within three months of the receipt of this SER.

O i 890512O206 890504 PDR h[]

4 ADOCK 05000312 )

l P PDC

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2 Rancho Seco is required to comply with the IST program defined in the above referenced letters in accordance with the relief granted in the enclosed SER.

Program changes that involve additional relief requests or changes to relief requests should be submitted for NRC staff review and should not be implemented prior to review and approval by the NRC. Program changes that involve only additions or deletions of components from the IST program should also be provided to the NRC.

Sincerely, Steven A. Reynolds, Project lianager Project Directorate V Division of Reactors Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

1. Safety Evaluation Report i

l 1

L_______

1 g,I' ^

May 4, 1989

'd "'

Rancho'Seco is required to comply with the IST program defined in the above referenced letters in accordance with the relief granted in the enclosed SER.

Program changes that involve additional relief requests or changes to relief

[ requests should be submitted for NRC staff review and should not be implemented prior to review and approval by the NRC. Program changes that involve only additions or deletions of components from the IST program should also be provided to the NRC.  !

Sincerely,

/s/

Steven A. Reynolds, Project Manager Project Directorate V Division of Reactors Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

1. Safety Evaluation Report DISTRIBUTION,,,

Docket Files.~./

NRC'& Tocal PDRs PD #5 Reading MVirgilio JLee SReynolds GKalman OGC (f/into only) ,

EJordan BGrimes f 7,4 9

/PD5 DR ,P 5 DRS PD5 OGCMf/ D D5 S lds G an p -

4/ 89 4/H/89 4/ 89 4/sp/89 /89 LOG p2 4/4

1,' ' y a- ...

~ I

~ Mr. Joe Firlit . .

Rancho Seco Nuclear Generating.. l

' Chief Executive Officer Nuclear- Station

, Rancho Seco Nuclear Generating Station

'14440 Twin Cities Road-l Herald, California.:95638-9799 i cc:

Mr. David .S.= Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Commission District 825 North Capitol Street, N. E.

6201 S Street .

Washington, D.C. 20426 P. O. Box 15830 Sacramento, California 95813 Thomas A. Baxter,' Esq. Ms. Helen Hubbard Shaw, Pittman, Potts & Trowbridge P. O. Box 63 2300 N Street, N.W. . Sunol, California 94586 Washington, D.C. 20037 ~

Mr. Steven Crunk Manager, Nuclear Licensing Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cit.ies Road Herald, California 95638-9799 Mr. Robert B. Borsum, Licensing Representative Babcock & Wilcox Nuclear Power Division 1700 Rockville Pike - Suite 525 Rockville, Marylar,d' 20852 Resident Inspector / Rancho Seco

.c/o U. S. N. R. C.

14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Paul Szalinski, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building f8 Sacramento, California 95814-Sacramento County Board of Supervisors 700 H Street, Suite 2450 Sacramento, California 95814

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