ML20058F417
| ML20058F417 | |
| Person / Time | |
|---|---|
| Issue date: | 11/01/1990 |
| From: | Jocelyn Craig Office of Nuclear Reactor Regulation |
| To: | Griffing E NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| NUDOCS 9011080276 | |
| Download: ML20058F417 (2) | |
Text
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November 1, 1990 T Mr. Edward Griffing Manager, Technical Division Nuclear Management and Resources Council
'17?6 Eye $treet, N.W.
Suite.300 Washington, D.C.
20006-2496
Dear ftr. Griffing:
SUDJECT:
PRESSURE WATER REACTOR YESSEL LICENSE REllEWAL INDUSTRY REPORT NRC statf concents on the subject Industry Report (IR) were forwarded to you by letter dated September 14, 1990.
Continuing staff review has resulted in the identification of a set of connents with generic IR applicability. Those generic concents applicable to the PWR Reactor Vessel IR are provided as an enclosure to thit,-letter.
Please add the connents to those previously forwarded and include proposed resolutions for the concerns and issues raised in your formal reply.
If you have any questions concerning this matter, please contact either rayself.
l or P.T..r,uo at 492-3147.
Sincerely,
)
Original signed by:
John W. Craig, Director License Renewal Project Directorate Division of Reactor Projects. III, IV, Y and Special Projects Office of Nuclear Reactor Regulation we i
Enclosure:
As stated Distribution:
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D. Crutchfield G. Bagchi.
C. McCracken
-J. Partlow F. Gillespie R. Bosnak R. Jones 3
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A. Thadani J. Vora-W. Travers 1
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R. Kirkwood L. Shao Sf h
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Enclosure GENERIC COMMENTS /PPLICALLE TO PWR REACT 0f: VESSEL 1)
HLterials in the heat affected zone (Ht.7) usually indicate severe neutron embrittlernent prob 1 cms. The IR should address this issue.
2)
Nuclear plants have been designec' and built by many A/E firms and construction companies at different times following various specifications and design procedures.
It is not clear how such variations have been enveloped in the evaluttions. The 1E should derhonstrate that the variations have been enveloped and identify whether there are any limitations that v.ould place restrictions on the applicttion of the results presented in the report.
3)
Since the 10 is to be widely used for license renewal purposes, it is reccinmended that the report include a cornplete listing of all assumed pararneters and a user-oriented checL11st such thct the user con verify the opplicability of the assurnptions that were made it, performing the degredation analysis. The IR should clearly specify any and all assuirptions that were made while perforrning the degradation analysis, 4)
An evtluation and/or analysis must be performed un the inspection o
program (s) thet are in place. The adequ:.cy and thoroughness of the programs must be evaluated, as well es whether or not the programs can detect degradation.
In addition, it must be possible to use the results of the inspection programs to trend performance.
5)
Low temperature sensitization (LTS) of 204 types of stainless steel should be discussed.
LTS could occur either in the base material or in L
heat affected zones.
LTS could render the components susceptible to 1GSCC.
If LTS is not going to be considered as an aging effect, justification for this decision should be provided.
6)
The ip should include specific guidelines for the utilities with regard i
to selecting a strategy for managing oging.
If plant specific tpproaches are recomrrended, an acceptable plant specific epproach should then be-presented.
L 7)
The report should cover the need for benchraart or base-line levels of parameters or indicators for recordkeeping and trending. The need for the trending of degradation data taken periodically to evaluate extended life operability should also be discussed.
l~
F)
The vessel should have essentially a 100 percent weldment inspection prior to license renewal using qualified personnel, procedures, and equipraent per ASME Section XI Appendices VII and VIII.
I L
.