ML20054M487
| ML20054M487 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/01/1982 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054M488 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8207130495 | |
| Download: ML20054M487 (3) | |
Text
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q Malling Address Alabama Power C7mpany 6C3 Nort* 1th Street 0" -
' Pogt Of h. ; Bc f 2341 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L. Clayton, Jr.
b Rn 'JO*:y"'
AlabamaPower a
re souttun etectre sntern July 1, 1982 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 & 2 NUREG-0737, Item II.D.1 Gentlemen:
In accordance with NUREG-0737 Item II.D.1, as amended by the NRC Generic Letter No. 81-36, Alabama Power Company is required to submit by July 1, 1982:
(1)
A plant-specific report for safety and relief valva qualification; and, (2)
A plant-specific submittal for piping and support evaluations.
This letter documents Alabama Power Company's compliance with these requirements.
The NUREG-0737, Item II.D.1, and the Unit 2 Full Power License, NPF-8, requirements for block valve qualifica-tion are addressed in a separate submittal, this same date.
Alabama Power Company is a participant in the Generic PWR Safety and Relief Valve Test Program implemented by the Electric Power Research Institute (EPRI) at the request of participating PWR utilities in response to NUREG-0737, Item II.D.1.
The primary objective of the test program was to provide full scale, proto-typical test data to confirm the operability of the primary system f
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8207130495 820701 PDR ADOCK 05000348 P
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O Mr. S. A. Varga July 1, 1982 Director, Nuclear Reactor Regulation Page 2 U. S. Nuclear Regulatory Commission Power Operated Relief Valves (PORV's) and Safety Valves for expected operating and accident conditions.
The second objective of the program was to obtain suf ficient piping thermal hydraulic load data to permit plant specific evaluation of the safety and relief valve piping systems.
The reports prepared by EPRI documenting the test program results are as follows:
" Valve Selection / Justification Report"
" Test Condition Justification Report"
" Westinghouse Plant Condition Justification Report"
" Safety and Relief Valve Test Report"
" Application of RELAP 5/ MOD 1 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads" All of these documents have been received by Alabama Power Company and were transmitted to the NRC by Mr. David Hof fman of Consumers Power Company on behalf of the participating PWR utilites on April 1, 1982.
A plant specific evaluation of the EPRI program results has been performed by Westinghouse to demonstrate that the test conditions and results are applicable to the Joseph M. Farley Nuclear Plant - Units 1 and 2.
The results of the evaluation are contained in the following reports prepared by Westinghouse:
"PWR Safety and Relief Valve Adequacy Report For Alabama Power Company, Joseph M. Farley Unit 1 and Unit 2," June 25, 1982 (Attachment 1).
" Pressurizer Safety and Relief Line Piping and Support l
Evaluation, Alabama Power Company, Joseph M.
Farley Unit 1 and Unit 2," July 1,1982 i
(Attachment 2).
i These reports demonstrate that the safety and relief valves, l
piping arrangements, and fluid inlet conditions for Joseph M.
Farley Units 1 and 2 are bounded by the valves and test parameters of the EPRI Safety and Relief Valve Test Program.
The EPRI tests confirm the ability of the Safety and Relief Valves to open and close under the expected operating fluid conditions.
The piping evaluation has been completed with determination of new loads on i
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the downstream piping.
Further analysis of the new loads is currently in progress with expected completion due in October 1982.
Based on engineering judgement, minor modifications and/or revised calculations will qualify the new piping loads.
m
t Mr. S. A. Varga July 1, 1982 Director, Nuclear Reactor Regulation Page 3 U.lS. Nuclear Regulatory Commission
.If there are any questions, please advise.
Yours very tr b
5-F. L. Clayton, Jr.
FLCJr/ JAR:jc-D17 Attachments cc:
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford i
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