ML20151R834

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Providing Results of NRC Review of Summer Inservice Testing Program for Pumps & Valves. Technical Evaluation Rept Encl
ML20151R834
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/19/1988
From: Adensam E
Office of Nuclear Reactor Regulation
To: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
Shared Package
ML20151R839 List:
References
TAC-49976, NUDOCS 8804280105
Download: ML20151R834 (4)


Text

.

0

/ p aucug'o UNITED STATES E 'h, NUCLEAR REGULATORY COMMISSION

W ASWNGTON, D. C. 20555 y

\...../ APR 191988 Docket No. 50-395 Mr. Dan A. Nauman Vice President, Nuclear Operations South Carolina Electric & Gas Company Post Office Box 88 (Mail Code 601)

Jenkinsville, SC 29065

Dear Mr. Nauman:

SUBJECT:

SAFETY EVALUATION ON THE INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES, V.C. SUMMER NUCLEAR STATION (TAC. N0 49976)

The enclosed Safety Evaluation (SE) provides the results of the NRC staff's review of the Sumer inservice testing program for pumps and valves.

The Code of Federal Regulations, paragraph 10 CFR 50.55a(g), requires certain Class 1, 2 and 3 pumps and valves in water-cooled nuclear reactor facilities to meet the inservice testing reauirements stated in the ASME Boiler and Pressure Vessel Code,Section XI; specifically, subsection IWP, Inservice Testing of Pumps in Nuclear Power Plants, and subsection IWV, Inservice Testing of Valves in Nuclear Power Plants. Each facility is reouired to establish a program 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: (1) is based on the applicable Code edition and addenda, (2) covers testing of all appropriate pumps and valves, and (3) contains acceptable relief reouests from the requirements of subsections IWP and IWV.

The IST program addressed in this report covers the first ten year interval from January 1, 1984 to January 1, 1994 The licensee's program and revisions were provided by letters dated January 5, 1983, March 1, 1983, March 17, 1983, August 2, 1984, and January 28, 1985.

The staff, with technical assistance from EG&G Idaho, Inc. (EG&G), has reviewed and evaluated the IST Program and requests for relief submitted for Sumer.

The staff adopts the evaluations and conclusions contained in the Technical Evaluation Report (TER) prepared by EG&G. The enclosed SE incorporates the TER and its findings. We have recommended that relief be granted from the testing requirements which would be impractical to perform, not compromise the safety of the facility, and result in hardships or unusual difficulties without a compensating increase in the level of ouality and safety. Certain relief l

requests should be denied where proposed alternative testing is unacceptable or where an adequate basis for the relief request has not been provided. We have determined that the IST program for Sumer is acceptable for implementation provided the omissions and inconsistencies identified in Appendix C of the TER are addressed within 3 months of the receipt of this SE.

8804280105 880419 DR ADOCK 050 g5

4 The licensee is required to comply with the IST program defined above in accordance with the relief granted in the enclosed SE. For the relief granted, the staff has determined (1) pursuant to 10 CFR 50.55a(a)(3)(i) that the proposed alternatives provide an acceptable level of quality and safety or (2) that conformance with certain requirements of the applicable Code edition and addenda is impractical and, pursuant to 10 CFR 50.55a(g)(6)(i), the relief granted and alternative requirements imposed are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest, giving due consideration to the burden that could result if the requirements were imposed on the facility.

Program changes such as revisions, additional relief requests, or deletions of any components from the IST program should be submitted for staff review.

Program changes must be approved by NRC prior to implementation.

For those items of this SE which will necessitate procedural changes, your plant has 90 days to implement the changes. For those items of this SE which will necessitate design modifications, your plant will have until startup following the next refueling outage to implement the modification.

This SE is not based upon a review of your revised IST program as described in your December 23, 1987 letter. If you have already implemented all or part of the revised program and/or the two relief requests of that letter and those portions implemented are not addressed in this SE, then you have 90 days to provide a justification as to why this implementation meets the findings of this safety evaluation and the requirements of the ASME Code Section XI.

You should provide a detailed listing of all deviations and of your rationale for the acceptability of these deviations. If the staff finds these I

l justifications adequate, you will be able to implement only those portions found acceptable in the enclosed esaluation.

Sincerely, l

\Y Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II i

Enclosure:

1 As stated cc w/ enc 1:

See next page

  • SEE PREVIOUS CONCURRENCE
  • LA:PD21:DRPR *PM:PD21:DRPR *EMEB: DEST *0GC 0:PD21: PR JHayes LBMarsh Young EAdensam PAnderson 04/07/88 04/07/88 04/07/88 04/08/88 04//j/88 i

I e Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.

Washington, D. C. 20036 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council i P.O. Box 293 l Winnsboro, South Carolina 29180 l Attorney General Box 11549 Columbia, South Carolina 29211

(

Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201

- _ _ _ _ _ _ _ _ _ _ _ _ _ _