ML20042C080
| ML20042C080 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 03/26/1982 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM GL-81-36, SLNRC-82-017, SLNRC-82-17, NUDOCS 8203300165 | |
| Download: ML20042C080 (2) | |
Text
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SNUPPS Standardised Nucteer Unit Power Piet System 5 Choke Cherry Hood Nicholas A. Petrick RockviHe, Meryland 20850 Executive Director March 26, 1982 SLWRC 82-017 FILE: 0541 SUBJ: NUREG 0737 Item II.D.1
/
AKS~
/ Mr. Harold R. Denton, Director
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Office of Nuclear Reactor Regulation
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U.S. Nuclear Regulatory Commission
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3 Washington, D. C.
20555 ht N2h Docket Nos:
STN 50-482 and STN 50-483 j
\\Y NRC (Eisenhut) letter to all licensees of cperating plants anld-: Syn Ref:
g applicants for operating licenses and holders of construction s
y tion of TMI Action Plan Item II.D.1, Relief and Safety Valve' p o, permits dated September 29, 1981, Revised Schedule for Comple; Testing (Generic Letter No. 81-36).
Dear Mr. Denton:
The referenced letter extended completion dates for the Relief and Safety Valve Test Requirements for Item II.D.1 of NUREG-0737. Speci-fically, the PWR (EPRI) testing program report was extended to April 1, 1982 and the PWR plant specific reports were extended to July 1, 1982. Review of the status of the EPRI testing program, the EPRI evaluation of the test data, and the EPRI development of the discharge piping load modeling of the test results indicate that some of the plant specific report submittal dates extended by the above reference are not realistic and cannot be met for the SNUPPS plants. Only after EPRI fully releases the data and models can the plant specific reports be generated.
Careful review of the information requested by the NRC and the release dates to the PWR utilities of the Enl generated information applicable to this requirement, dictates that wt extend the submittal dates for some of the plant specific documentat 'on requirements set forth in the above reference. The SNUPPS submittal dates are tabulated below:
SNUPPS NRC Submittal Item Date Date P1 ant specific submittals confirming 4/1/82 5/1/82 adequacy of safety and relief valves
/>
based on licensee / applicant prelimi-
[q0 nary review of generic. test program J
results
/O 8203300165 B20326 PDR ADOCK 05000482 A
D SLNRC 82-017 Page Two SNUPPS NRC Submittal Item Date Date Plant specific reports for safety and 7/1/82 12/31/82*
relief valve qualification Plant specific submittals for piping 7/1/82 12/31/82*
support evaluations An action plan based on evaluation of the test data as applicable to the SNUPPS plants will be generated by 7/1/82 and submitted to the NRC. Upon completion of this action plan, these dates will be re-evaluated.
It appears at this time, after consultation with EPRI, that the PWR (EPRI) generic testing program report will meet the current NRC required submittal date of 4/1/82.
In addition, the SNUPPS specific submittal for block valve qualification should meet the NRC required submittal date of 7/1/82.
Very truly yours, M%C
- Nicholas A. Petrick J0C/jdk/la9-10 cc: G. L. Koester KGE D. T. McPhee KCPL D. F. Schnell UE l
T. E. Vandel NRC/WC J. H. Neisler NRC/ CAL i.