ML20070C816: Difference between revisions
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| number = ML20070C816 | | number = ML20070C816 | ||
| issue date = 06/27/1994 | | issue date = 06/27/1994 | ||
| title = Informs That NRC Should Refer to B&Wog Rv Working Group Rept BAW-2222, B&Wog Response to Closure Ltrs to NRC GL 92-01, Rev 1 as Util Response to NRC | | title = Informs That NRC Should Refer to B&Wog Rv Working Group Rept BAW-2222, B&Wog Response to Closure Ltrs to NRC GL 92-01, Rev 1 as Util Response to NRC Re Applicability & Accuracy of Info Provided in Response to GL 92-01,Rev 1 | ||
| author name = Link B | | author name = Link B | ||
| author affiliation = WISCONSIN ELECTRIC POWER CO. | | author affiliation = WISCONSIN ELECTRIC POWER CO. | ||
| Line 12: | Line 12: | ||
| case reference number = CON-NRC-94-043, CON-NRC-94-43 | | case reference number = CON-NRC-94-043, CON-NRC-94-43 | ||
| document report number = GL-92-01, GL-92-1, VPNPD-94-064, VPNPD-94-64, NUDOCS 9407070030 | | document report number = GL-92-01, GL-92-1, VPNPD-94-064, VPNPD-94-64, NUDOCS 9407070030 | ||
| title reference date = 03-17-1994 | |||
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | ||
| page count = 2 | | page count = 2 | ||
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y Wisconsin Electnc PONER COMPANY 239 w Mceryn t o tex ?cas uawsoe ne '232012046 M uj;?< 2345 VPNPD-94-064 HRC-94-043 J.tne 27, 1994 Document control Desk U.S. NUCLEAR REG:1LATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen; DOCKETS 50-266 AND 50-301 GENERIC LETTER 92-01, REVISION 1. | y Wisconsin Electnc PONER COMPANY 239 w Mceryn t o tex ?cas uawsoe ne '232012046 M uj;?< 2345 VPNPD-94-064 HRC-94-043 J.tne 27, 1994 Document control Desk U.S. NUCLEAR REG:1LATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen; DOCKETS 50-266 AND 50-301 GENERIC LETTER 92-01, REVISION 1. | ||
" REACTOR VESSE1. STRUCTURAL INTEGRITY" POINT BEACil NUCLEAR 'eLANT, UNITS 1 AND 2 The Nuclear Regulatory Commission (NRC) requested by letter dated March 17, 1994, that Wisconsin Electric (WE) confirm the applicability and accuracy of information previously provided by WE and the Babcox:& Wilcox Owners Group (B&WOG) in response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity." On May 2, 1994, WE provided our response to that request. On May 18, 1994 Ms. Lit.da Gundrum, acting NRC Project l Ma :ager for the Point Beach Nuclear Plant, Mr. Barry'Elliot of l NRR's technical staff, and members of the Wisconsin Electric staff | " REACTOR VESSE1. STRUCTURAL INTEGRITY" POINT BEACil NUCLEAR 'eLANT, UNITS 1 AND 2 The Nuclear Regulatory Commission (NRC) requested by {{letter dated|date=March 17, 1994|text=letter dated March 17, 1994}}, that Wisconsin Electric (WE) confirm the applicability and accuracy of information previously provided by WE and the Babcox:& Wilcox Owners Group (B&WOG) in response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity." On May 2, 1994, WE provided our response to that request. On May 18, 1994 Ms. Lit.da Gundrum, acting NRC Project l Ma :ager for the Point Beach Nuclear Plant, Mr. Barry'Elliot of l NRR's technical staff, and members of the Wisconsin Electric staff | ||
; participated in a conference call.regarding our May 2 submittal. | ; participated in a conference call.regarding our May 2 submittal. | ||
During this conference call, Mr. Elliot requested WE clarify information that was provided in the May 2 submittal. | During this conference call, Mr. Elliot requested WE clarify information that was provided in the May 2 submittal. | ||
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6' | 6' | ||
, Document Control Desk June 27, 1994 Page 2 BAW-2222 regarding Point Beach Nuclear Plant satisfactorily responds to the information requested in your March 17, 1994, letter and in subr'quent discussions. | , Document Control Desk June 27, 1994 Page 2 BAW-2222 regarding Point Beach Nuclear Plant satisfactorily responds to the information requested in your {{letter dated|date=March 17, 1994|text=March 17, 1994, letter}} and in subr'quent discussions. | ||
The fluence values reported in BAW-2222 for the one-quarter thickness vessel wall location are based on an attenuation model for neutrons with energien greater than 1.0 MeV. These fluence values are consistent with those used in the upper shelf energy - | The fluence values reported in BAW-2222 for the one-quarter thickness vessel wall location are based on an attenuation model for neutrons with energien greater than 1.0 MeV. These fluence values are consistent with those used in the upper shelf energy - | ||
equivalent margins analysis for Point Beach. However, they are more conservative than the fluence values reported in our previous correspondence in response to Generic Letter 92-01. The previous fluence values were based on the Regulatory Guide 1.99, Rev. 2 exponential attenuation facter. | equivalent margins analysis for Point Beach. However, they are more conservative than the fluence values reported in our previous correspondence in response to Generic Letter 92-01. The previous fluence values were based on the Regulatory Guide 1.99, Rev. 2 exponential attenuation facter. | ||
Revision as of 08:51, 31 May 2023
| ML20070C816 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/27/1994 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-94-043, CON-NRC-94-43 GL-92-01, GL-92-1, VPNPD-94-064, VPNPD-94-64, NUDOCS 9407070030 | |
| Download: ML20070C816 (2) | |
Text
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. )
y Wisconsin Electnc PONER COMPANY 239 w Mceryn t o tex ?cas uawsoe ne '232012046 M uj;?< 2345 VPNPD-94-064 HRC-94-043 J.tne 27, 1994 Document control Desk U.S. NUCLEAR REG:1LATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen; DOCKETS 50-266 AND 50-301 GENERIC LETTER 92-01, REVISION 1.
" REACTOR VESSE1. STRUCTURAL INTEGRITY" POINT BEACil NUCLEAR 'eLANT, UNITS 1 AND 2 The Nuclear Regulatory Commission (NRC) requested by letter dated March 17, 1994, that Wisconsin Electric (WE) confirm the applicability and accuracy of information previously provided by WE and the Babcox:& Wilcox Owners Group (B&WOG) in response to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity." On May 2, 1994, WE provided our response to that request. On May 18, 1994 Ms. Lit.da Gundrum, acting NRC Project l Ma :ager for the Point Beach Nuclear Plant, Mr. Barry'Elliot of l NRR's technical staff, and members of the Wisconsin Electric staff
- participated in a conference call.regarding our May 2 submittal.
During this conference call, Mr. Elliot requested WE clarify information that was provided in the May 2 submittal.
i The B&WOG Reactor Vessel Working Group, under the direction of Wisconsin Electric and other member utilities, devaloped report l BAW-2222, "B&W Owners Group Response to Closure Letters to NRC.
Generic Letter 92-01, Revision 1," which was transmitted-to the NRC by the B&WOG:on June 23, 1994. This report contains information which updates our-; otter of May'2, 1994, and should be referred to by the NRC as the WE response to your letter of March 17, 1994.
This report provides the information requasted by Mr. Elliot-during the May 18 telephone conference.
p l Wisconsin Electric sponsored and directed the development of l=
BAW-2222 and endorses the data contained in BAw'-2222 regarding our Point Beach Nuclear Plant. We believe the data contained in 9407070000 940627 g-PDR ADOCK 03000266 l p PDR l
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, Document Control Desk June 27, 1994 Page 2 BAW-2222 regarding Point Beach Nuclear Plant satisfactorily responds to the information requested in your March 17, 1994, letter and in subr'quent discussions.
The fluence values reported in BAW-2222 for the one-quarter thickness vessel wall location are based on an attenuation model for neutrons with energien greater than 1.0 MeV. These fluence values are consistent with those used in the upper shelf energy -
equivalent margins analysis for Point Beach. However, they are more conservative than the fluence values reported in our previous correspondence in response to Generic Letter 92-01. The previous fluence values were based on the Regulatory Guide 1.99, Rev. 2 exponential attenuation facter.
If you have any questions or require additional information, please contact us.
Sincerely,
, )
!, /'~ j W ,/ - .
Bob Link Vice President Nuclear Power cc: HRC Regional Administrutor, Region III NRC Hesitant Inspector I
1 .. . . .