ML20214G611
| ML20214G611 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/23/1972 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0132, CON-WNP-132 NUDOCS 8605220320 | |
| Download: ML20214G611 (3) | |
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Boger 8. Boyd, Assistaat Director for EWR's, Division of Roaster Licensing M&SMINGTON FUBLIC POWER SUFFLY SYSTEM, EA550RD 50. 2, D0 2R7 30. 50-397 l
The taformatiam embaitted by the applissat la the PSAR and la response to our regnant for addicianal information la Amendment 2 has been reviewed by the Materials Engineering Bransk, DR8. Aaseptable responses have been re-ceived in the areas of reacter coelast leakage (4.11 to 4.17 inclusive),
inservice inspection (c.1 to C.3 inclusive) and containment leak testing (5.1). Inadequate responses have been received for the areas listed in the enclosure. Complete and acceptable responses will be needed by April 10, 1972 in order for us to oemplete our eenstruction permit safety evaluation report scheduled for submission to DEL by June 12, 1972 This memorandem is in response to DRL's second request (Q2) for additimaal information.
Onuh* s**1 by yy p7 R.R.Maarm R. R. Maccary, Assistant Director for Engineering Division of Reactor Standards Enclosures i
Materials Engineering Branch Request for Additional Information (Q2) cc w/encie E. J. Bloch, DR S. H. Hanauer, DR E. C. Case, DRS R. Clark, DEL S. Miner, DEL
M. Fairtile, DRS se e/o seals R. Smith, DRs
- v. C. MeD aid, DEL l
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on < s e s t i.4 t e 4e s 0605220320 720323 PDR ADOCK 05000397 A
HANFORD NO. 2 NUCLEAR POWEE PLANT SECOND REQUECT TOR ADDIi!DNAL INFORMATION NATERIAL4 EN"INEERING, DRS
Reference:
Letter, R. 5. Royd to Washington Putlic Power Sypply System, requesting additional teformtfon on Hanford No. 2 Nucleat Power Plant, Docket No. 50-397, dated January 20, 1972, Questions:
4.1 We recommend that the applicant be 1equested to comply with the f racture tough-and 4.2 ness testing methods and the ferritic materials acceptance criteria of the recently revised ASME Code Section III,1971 Edition, fragture toughnass rules.
This means providing fracture toughness data for all pressure-retaicing f arritje components of the reactor coolant pressure boundary including the following 9 for materials for vessels, materials with nominal well thlekness over 21/2 inches for piping, and materials for pumps, valves, and fittings with any pipe connection of nominal wall thickness greater than J 1/2 inches:
1.
NDT temperatures obtained from dtop-weight (DVI) tests, and 2.
Temperatures at which " weak" directiou Charpy V-notch specimens exhibit at least 35 mils lateral expansion and not less than 10 f t-lb absorbed energy.
4.3 For the reactor vessel beltline materials, we reconeend that the applicant I
be requested to provide fracture toughness data ir. accordance with the recently revised ASME Code Section !!!, 1971 Edition, fracture toughness rules that pertain to vessel materials.
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4.4 We recommend that the applicant be requested to provide proposed operating limitations curing startup and shutdown of the reactor coolant system based on compliance with Appendix G " Protection Against Non-Ductile Failure", of the recently revised ASME Code Section III,1971 Edition, fracture toughness rules.
4.5 The applicant has stated that ASTM E185-70 will not be complied with regarding such significant items ass (1) taking specimens from the heat that has the highest initial ductile-brittle transition temperature; (2) required chemical analysis of the surveillance material; (3) having t
provision for later insertion of surveillance materialg and (4) having material for two extra sets of capsules. We reccamend that the applicant l
be requested to comply with the above provisions of E185-70
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The applicant also has not indicated that withdrawal schedule of the capsules will comply with the AEC proposed 50.55a Appendix H, " Reactor Vessel Material Surveillance Program Requirements".
t 4.7 We recommend that the applicant be requested to provide more details on the precautions that will be taken to avoid sensitisation of austenitic stainless steel in the reactor coolant presourc boundary. For example, the applicant should detail the steps to prevent furnace sensitization of austenitic stainless steel safe ends that join ferritic components to austenitic stainless steel components.
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