ML20197G722
| ML20197G722 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/09/1998 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-01, GL-97-1, W3F1-98-0198, W3F1-98-198, NUDOCS 9812100138 | |
| Download: ML20197G722 (8) | |
Text
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O Entergy operations,Inc.
PC. Box B l
Killona. LA 70066 Tel 504 739 6242 Early C. Ewing, til u a afety & Regulatory Affairs l
W3F1-98-0198 A4.05 PR l
l December 9,1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
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Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 l
Response to Request for Additional Information On Generic Letter 97-01 Gentlemen:
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By letter dated September 10,1998, the NRC staff issued " Request for Additional information Regarding Utilities Participating in the Combustion Engineering Owners i
Group (CEOG) Response to Generic Letter (GL) 97-01, ' Degradation of CEDM Nozzle and Other Vessel Closure Head Penetrations'-Topical Report CE NPSD-1085, Revision 0." Entergy Operations at Waterford 3 is a participant in the Nuclear Energy institute (NEI) and CEOG program to address this request. NEl and CEOG are scheduled to respond to the NRC staff on December 11,1998 in a submittal entitled " Generic Response to the NRC Request for Additional Information on Generic Letter 97-01."
The portions of the NEl submittal that will provide the Waterford 3 response are described in the Attachment to this letter.
Ao95' 9812100138 981209 f
PDR ADOCK 05000382t P
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Response to Request for Additional Information On Generic Letter 97-01 l
W3F1-98-0198 Page 2 December 9,1998 h
if you should have any questions regarding this matter, please contact Roy Prados at (504) 739-6632.
Very truly yours, E.C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/RWP/rtk Affidavit Attachment i
(w/ Attachment) cc:
E.W. Merschoff (NRC Region IV)
C.P. Patel (NRC-NRR)
J. Smith N.S. Reynolds NRC Resident inspectors Office i
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i
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In the matter of
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l Entergy Operations, incorporated
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Docket No. 50-382 -
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Waterford 3 Steam Electric Station
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AFFIDAVIT Early Cunningham Ewing, being duly sworn, hereby deposes and says that he is Director, Nuclear Safety & Regulatory Affairs - Waterford 3 of Entergy Operations, incorporated; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Response to Request for Additional Information on Generic Letter 97-01; that he is familiar with the content thereof; and that the matters set forth U
therein are true and correct to the best of his knowledge, information and belief.
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1 hwh tarl/Cunninghdm Ewing i
Director, Nuclear Safety & Regulatory Affa l
Waterford 3 i
STATE OF LOUISIANA
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PARISH OF ST. CHARLES
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Subscribed and sworn to before me, a 'otary Public in and for the Parish and State above named this 9 O day of
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,1998.
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Notary Public My Commission expires d4d 1
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1 Attachment to W3F1-98-0198
i Attachment to j
W3F1-98-0198 Page 1 of 4 Response to RAI on Generic Letter 97-01 NRC REQUESTED INFORMATION 1
Designate which crack susceptibility model is being endorsed for the l
assessment of CEDM penetration nozzles at your plant.
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RESPONSE
1 The requested information will be provided in the December 11,1998, Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional information," Response to Question 1.
NRC REQUESTED INFORMATION Indicate how the susceptibility model being endorsed relates to the CEOG's integrated program for assessing the CEDM penetration nozzles at ABB-CE designed plants, and whether or not the design of the susceptibility model is consistent with the contents of Topical Report CE NPSD-1085.
RESPONSE
The requested information will be provided in the December 11,1998, Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional Information," Response to Question 2.
NRC REQUESTED INFORMATION If the ABB-CE PITM model is being endorsed for the assessment of CEDM penetration nozzles at your plant, address items a. - e. below.
if the PITM models are being endorsed for the assessment of your CEDM penetration nozzles:
4 a.
Provide an expanded discussion and additional details describing how the time-to-failure model in the PITM relates to the PITM's time-to-initiation model. In particular, include an expended discussion of how the PITM model relates growth of postulated flaws to the time-to-initiation model, and how the two aspects relate to each other and to the probability of failure methodology.
Attachment to W3F1-98-0198 Page 2 of 4 t
b.
Provide the latest PITM susceptibility ranking of CEDM penetration nozzles and,if applicable, of the vessel head instrumentation nozzles at your plant relative to the rankings of those at the other CEOG member plants.
c.
Provide a description of how the PITM model for assessing postulated flaws in vessel head penetration nozzles was benchmarked, and list and discuss the standards the models were l
benchmarked against.
d.
Provide any additional information regarding how the model will be refined to allow the input of plant-specific inspection data into the model's analysis methodology.
e.
Describe how the variability in the product forms, material specifications, and heat treatments used to fabricate each CEDM penetration nozzle at the CEOG member utilities are addressed in the PITM model.
RESPONSE
The CEOG now endorses the use of the EPRI model for the assessment of PWSCC in Alloy 600 reactor vessel head penetrations. This information will be provided in the December 11,1998, Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional Information," Response to Question 1.
Therefore, no further response to items a. - e. is necessary.
NRC REQUESTED INFORMATION If the Dominion Engineering susceptibility modelis being endorsed for the assessment of CEDM penetration nozzles at your plant, address items
- f. - 1. below, if the susceptibility model developed by Dominion Engineering is being endorsed for the assessment of your CEDM penetration nozzles:
f.
Provide a description of how the various product 'orms, material specifications, and heat treatments used to fabrict to eEch CEDM penetration nozzle at the CEOG member utiliUca are, handled in the Dominion Engineering susceptibility model.
Attachment to W3F1-98-0198 Page 3 of 4
RESPONSE
f.
It should be noted that the EPRI model, now endorsed by the CEOG and Waterford 3, is the Dominion Engineering developed model. The requested information for this item will be provided in the December 11, 1998, Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional Information," Response to Question 3.
NRC REQUESTED INFORMATION g.
Provide any additional information,if available, regarding how the model will be refined to allow the input of plant-specific inspection data into the model's analysis methodology.
RESPONSE
g.
The requested information will be provided in the December 11,1998, l
Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional Information," Response to Question 5.
I NRC REQUESTED INFORMATION h.
Describe how the Dominion Engineering crack initiation and crack growth models for assessing postulated flaws in vessel head penetration nozzles were bench-marked, and provide a listing and discussion of the standards the models were bench-marked against.
RESPONSE
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The requested information will be provided in the December 11,1998, Nuclear Energy Institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Additional Information on Generic i
Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for Additional Information," Response to Question 4.
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Attachm:nt to l
W3F1-98-0198 Page 4 of 4 NRC REQUESTED INFORMATION i
1.
Provide the latest model susceptibility rankings of CEDM penetration nozzles in CEOG member plants based on the results of the Dominion Engineering susceptibility model analyses of these CEDM and ICI nozzles.
RESPONSE
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The requested information will be provided in the December 11,1998, Nuclear Energy institute submittal to the NRC, entitled " Generic Responses to the NRC Requests for Auditional Information on Generic Letter 97-01," Enclosure 4, "CEOG Responses to NRC Requests for i
Additional Information," Response to Question 6.
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