ML20198G747
| ML20198G747 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 08/02/1976 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1130 NUDOCS 8605290750 | |
| Download: ML20198G747 (4) | |
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AUG 21976 j
l Docket Nos.
I Assistant Director for Light Water Reactors i
Division of Project Management WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS) WASHINGTON NUCLEAR PROJECT NOS.1AND4(WNP-1/4)(CP)DOCKETNUMSERS 50-460/513 (TAR-3916)
Plant flame: Washington Nuclear Project Ncs.1 and 4 (WNP-1/4)
Suppliers: Babcock & Wilcox; United Engineers & Constructors Docket Husibers: 50-460/513 Responsible Branch: LWR 1 Project Manager:
T. H. Cox Systems Review Branch: Materials Engineering Branch (MTEB) l Target Cocipletion Date: July 15, 1976 Description of Request: The review should address the adequacy of WPPSS' April 23,1976 letter presentation entitled
" Pipe Break Integrity. Attachment B" i
l In response to your Technical Assistance Request (TAR-3916), the Materials Integrity Section of the Materials Engineering Branch has reviewed the letter pmsentation on the proposed plant design changes in " Attachment B, Pipe Break Integrity."
The applicant proposes to design for pipe breaks outside containment in I
accordance with criteria in NRC Branch Technical Positions APCSB 3-1, l
" Protection Against Postulated Piping Failures in Fluid Systems Outside Containment" and MEB 3-1, " Postulated Break and Leakage Locations in Fluid System Piping Outside Containment."
j In the PSAR, the applicant connitted to comply with Regulatory Guide 1.46 and NRC documents entitled " General Information Required for Consideration of the Effects of a Piping System Break Outside Containment" and " Pipe Whip Analysis."
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8605290750 760802 PDR ADOCK 05000460 G
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i AD for Light Water Reactors,
i Our evaluation indicates that the applicant has not addressed compliance with the inservice inspection requirements of NRC Branch Technical Positions APCSB 3-1 and MEB 3-1.
We require verification of this compliance in the PSAR.
1 J. P. Knight, Acting Assistant Director i
for Engineering Division of Systems Safety Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enc 1:
R. E. Heineman, DSS D. Eisenhut. 00R i.
J. Miller, NRR S. Varga, DPM F. Schroeder, DSS J. P. Knight, DSS l
J. F. Stolz, DPM l
T. H. Cox, DPM S. S. Pawlicki, DSS U. Potapovs. DSS H. F. Conrad, DSS F. B. Litton, DSS cc w/o encl:
R. S. Boyd, DPM i
W. G. Mcdonald, MIPC l
DISTRIBUTION:
i Docket Files (50-460/513)
NRR Reading File MTEB Reading File TAR MI 14 nn u' DSS:MTES DSS:MTEB
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F$t bfmb _M R 1RRls JF istit ou 1 hl16 112$16 SLYJ.76
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W u. s. oovannusm? Pa'avene errecs s.74.sae see Focus AEC.)t3 (Re. 9-53) AICM 0240
AD for Light Water Reactors Our evaluation indicates that the applicant has not addressed compliance with the inservice inspection requirements of NRC Branch Technical Positions APCSB 3-1 and MEB 3-1.
We require verification of this compliance in the PSAR.
7 J. P. Knight, Acting Assistant Director for Engineering Division of Systems Safety Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ encl:
R. E. Heineman, DSS D. Eisenhut, D0R J. Miller, NRR S. Varga, DPM F. Schroeder, DSS J. P. Knight, DSS J. F. Stolz, DPM T. H. Cox, DPM S. S. Pawlicki, DSS U. Potapovs, DSS H. F. Conrad. DSS F. B. Litton, DSS cc w/o encl:
R. S. Boyd, DPM W. G. Mcdonald, MIPC h
o 120-1 120.0 MATERIALS ENGINEERING BRANCH 120.1 We require verification of compliance with the inservice inspection requirements of NRC Branch Technical Positions APCSB 3-1, " Protection Against Postulated Piping Failures in Fluid Systems Outside Containment" and MEB 3-1, " Postulated Break and Leakage Locations in Fluid System Piping Outside Containment."
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