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| issue date = 03/26/2009 | | issue date = 03/26/2009 | ||
| title = Cover Letter: Final Safety Evaluation for NEI Topical Report (TR) WCAP-16308-NP, Revision 0, Pressurized Water Reactor Owners Group 10 CFR (Title 10 of the Code of Federal Regulations) 50.69 Pilot Program - Categorization Process - Wolf Cre | | title = Cover Letter: Final Safety Evaluation for NEI Topical Report (TR) WCAP-16308-NP, Revision 0, Pressurized Water Reactor Owners Group 10 CFR (Title 10 of the Code of Federal Regulations) 50.69 Pilot Program - Categorization Process - Wolf Cre | ||
| author name = Blount T | | author name = Blount T | ||
| author affiliation = NRC/NRR/DPR | | author affiliation = NRC/NRR/DPR | ||
| addressee name = Bradley B | | addressee name = Bradley B | ||
| Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:March 26, 2009 | {{#Wiki_filter:March 26, 2009 Mr. Biff Bradley, Director Risk Assessment Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 | ||
Mr. Biff Bradley, Director Risk Assessment Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 | |||
==SUBJECT:== | ==SUBJECT:== | ||
FINAL SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE (NEI) TOPICAL REPORT (TR) WCAP-16308-NP, REVISION 0, | FINAL SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE (NEI) | ||
CATEGORIZATION PROCESS - WOLF CREEK GENERATING STATION | TOPICAL REPORT (TR) WCAP-16308-NP, REVISION 0, PRESSURIZED WATER REACTOR OWNERS GROUP [(PWROG)] 10 CFR [TITLE 10 OF THE CODE OF FEDERAL REGULATIONS] 50.69 PILOT PROGRAM - | ||
CATEGORIZATION PROCESS - WOLF CREEK GENERATING STATION (TAC NO. MD4229) | |||
==Dear Mr. Bradley:== | ==Dear Mr. Bradley:== | ||
By letter dated September 25, 2006, as supplemented by letters dated October 22, 2007, and July 15, 2008, the NEI submitted Topical Report (TR) WCAP-16308-NP, Revision 0, | By letter dated September 25, 2006, as supplemented by letters dated October 22, 2007, and July 15, 2008, the NEI submitted Topical Report (TR) WCAP-16308-NP, Revision 0, Pressurized Water Reactor Owners Group 10 CFR 50.69 Pilot Program - Categorization Process- Wolf Creek Generating Station, to the U.S. Nuclear Regulatory Commission (NRC) staff for review on behalf of the PWROG. By letter dated September 16, 2008, an NRC draft safety evaluation (SE) regarding our approval of TR WCAP-16308-NP was provided for your review and comments. By letter dated October 14, 2008, NEI commented on the draft SE. The NRC staff's disposition of NEI=s comments on the draft SE are discussed in Attachment 2 to the final SE enclosed with this letter. | ||
=s comments on the draft SE are discussed in Attachment 2 to the final SE enclosed with this letter. | The NRC staff has found that TR WCAP-16308-NP is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR. | ||
The categorization process described in TR WCAP-16308-NP and evaluated in the enclosed final SE supports license amendment applications by licensees voluntarily choosing to implement 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. As described in the statement of considerations for 10 CFR 50.69, the treatment processes for structures, systems, and components (SSC) are not subject to NRC review and approval as part of the license amendment process, but rather will be subject to sample inspections at nuclear power plants implementing 10 CFR 50.69. | |||
The NRC staff has found that TR WCAP-16308-NP is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR. | |||
The categorization process described in TR WCAP-16308-NP and evaluated in the | |||
Therefore, the SE does not approve nor endorse any specific treatment process. The NRC recognizes the need for an effective, stable and predictable inspection process regarding treatment requirements and looks forward to a continuing dialogue with NEI to ensure these goals are achieved. | Therefore, the SE does not approve nor endorse any specific treatment process. The NRC recognizes the need for an effective, stable and predictable inspection process regarding treatment requirements and looks forward to a continuing dialogue with NEI to ensure these goals are achieved. | ||
in license applications, our review will ensure that the | B. Bradley Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards. In accordance with the guidance provided on the NRC website, we request that NEI publish an accepted version of this TR within three months of receipt of this letter. The accepted version shall incorporate this letter and the enclosed final SE after the title page. In addition, the accepted version should be modified to incorporate the changes identified in Table 1 of the enclosed SE. Also, they must contain historical review information, including NRC requests for additional information and your responses. The accepted versions shall include an "-A" (designating accepted) following the TR identification symbol. | ||
If future changes to the NRC's regulatory requirements affect the acceptability of this TR, NEI and/or licensees referencing it will be expected to revise the TR appropriately, or justify its continued applicability for subsequent referencing. | |||
If future changes to the NRC's regulatory requirements affect the acceptability of this TR, NEI and/or licensees referencing it will be expected to revise the TR appropriately, or justify its continued applicability for subsequent | Sincerely, | ||
/RA/ | |||
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 689 | |||
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation | |||
Project No. 689 | |||
==Enclosure:== | ==Enclosure:== | ||
Final SE | Final SE cc w/encl: See next page | ||
cc w/encl: | |||
Mr. James H. Riley, Director Engineering Nuclear Energy Institute 1776 I Street, NW Washington, DC 20006-3708 jhr@nei.org}} | ML090280265 (Package); ML090260632 (Cover Letter); ML082140868 (Draft SE); ML090260674 (Final SE) *No major changes to SE input. NRR-043 OFFICE PSPB/PM PSPB/LA DCI/CPTB* DCI/CPNB* DE/EMCB DRA/APLA* PSPB/BC DPR/DD NAME TMensah DBaxley JMcHale TChan KManoly MRubin SRosenberg TBlount DATE 02 /09 /09 02/05 /09 07/08/08 07/08/08 08/22/08 07/22/08 03 /12 /09 03/26/09 Nuclear Energy Institute Project No. 689 cc: | ||
Mr. Anthony Pietrangelo, Vice President Mr. Alexander Marion, Acting Vice President Regulatory Affairs for Nuclear Operations Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 arp@nei.org am@nei.org Mr. Jack Roe, Director Mr. John Butler, Director Security Operations Support Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 jwr@nei.org jcb@nei.org Mr. Charles B. Brinkman Mike Melton, Senior Project Manager Washington Operations 1776 I Street, NW, Suite 400 ABB-Combustion Engineering, Inc. Washington, DC 20006-3708 12300 Twinbrook Parkway, Suite 330 man@nei.org Rockville, MD 20852 brinkmcb@westinghouse.com Dennis Buschbaum PWROG Chairman Mr. James Gresham, Manager Comanche Peak Steam Electric Station Regulatory Compliance and Plant Licensing 6322 North Farm to Marked Rd 56 Westinghouse Electric Company Mail Code E15 P.O. Box 355 Glen Rose, TX 76043 Pittsburgh, PA 15230-0355 Dennis.Buschbaum@luminant.com greshaja@westinghouse.com Mr. James H. Riley, Director Ms. Barbara Lewis Engineering Assistant Editor Nuclear Energy Institute Platts, Principal Editorial Office 1776 I Street, NW 1200 G St., N.W., Suite 1100 Washington, DC 20006-3708 Washington, DC 20005 jhr@nei.org Barbara_lewis@platts.com}} | |||
Latest revision as of 17:51, 12 March 2020
| ML090260632 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 03/26/2009 |
| From: | Blount T Division of Policy and Rulemaking |
| To: | Bradley B Nuclear Energy Institute |
| Mensah T | |
| Shared Package | |
| ML090280265 | List: |
| References | |
| TAC MD4229, WCAP-16308-NP, Rev 0 | |
| Download: ML090260632 (4) | |
Text
March 26, 2009 Mr. Biff Bradley, Director Risk Assessment Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708
SUBJECT:
FINAL SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE (NEI)
TOPICAL REPORT (TR) WCAP-16308-NP, REVISION 0, PRESSURIZED WATER REACTOR OWNERS GROUP [(PWROG)] 10 CFR [TITLE 10 OF THE CODE OF FEDERAL REGULATIONS] 50.69 PILOT PROGRAM -
CATEGORIZATION PROCESS - WOLF CREEK GENERATING STATION (TAC NO. MD4229)
Dear Mr. Bradley:
By letter dated September 25, 2006, as supplemented by letters dated October 22, 2007, and July 15, 2008, the NEI submitted Topical Report (TR) WCAP-16308-NP, Revision 0, Pressurized Water Reactor Owners Group 10 CFR 50.69 Pilot Program - Categorization Process- Wolf Creek Generating Station, to the U.S. Nuclear Regulatory Commission (NRC) staff for review on behalf of the PWROG. By letter dated September 16, 2008, an NRC draft safety evaluation (SE) regarding our approval of TR WCAP-16308-NP was provided for your review and comments. By letter dated October 14, 2008, NEI commented on the draft SE. The NRC staff's disposition of NEI=s comments on the draft SE are discussed in Attachment 2 to the final SE enclosed with this letter.
The NRC staff has found that TR WCAP-16308-NP is acceptable for referencing in licensing applications to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.
The categorization process described in TR WCAP-16308-NP and evaluated in the enclosed final SE supports license amendment applications by licensees voluntarily choosing to implement 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. As described in the statement of considerations for 10 CFR 50.69, the treatment processes for structures, systems, and components (SSC) are not subject to NRC review and approval as part of the license amendment process, but rather will be subject to sample inspections at nuclear power plants implementing 10 CFR 50.69.
Therefore, the SE does not approve nor endorse any specific treatment process. The NRC recognizes the need for an effective, stable and predictable inspection process regarding treatment requirements and looks forward to a continuing dialogue with NEI to ensure these goals are achieved.
B. Bradley Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards. In accordance with the guidance provided on the NRC website, we request that NEI publish an accepted version of this TR within three months of receipt of this letter. The accepted version shall incorporate this letter and the enclosed final SE after the title page. In addition, the accepted version should be modified to incorporate the changes identified in Table 1 of the enclosed SE. Also, they must contain historical review information, including NRC requests for additional information and your responses. The accepted versions shall include an "-A" (designating accepted) following the TR identification symbol.
If future changes to the NRC's regulatory requirements affect the acceptability of this TR, NEI and/or licensees referencing it will be expected to revise the TR appropriately, or justify its continued applicability for subsequent referencing.
Sincerely,
/RA/
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 689
Enclosure:
Final SE cc w/encl: See next page
ML090280265 (Package); ML090260632 (Cover Letter); ML082140868 (Draft SE); ML090260674 (Final SE) *No major changes to SE input. NRR-043 OFFICE PSPB/PM PSPB/LA DCI/CPTB* DCI/CPNB* DE/EMCB DRA/APLA* PSPB/BC DPR/DD NAME TMensah DBaxley JMcHale TChan KManoly MRubin SRosenberg TBlount DATE 02 /09 /09 02/05 /09 07/08/08 07/08/08 08/22/08 07/22/08 03 /12 /09 03/26/09 Nuclear Energy Institute Project No. 689 cc:
Mr. Anthony Pietrangelo, Vice President Mr. Alexander Marion, Acting Vice President Regulatory Affairs for Nuclear Operations Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 arp@nei.org am@nei.org Mr. Jack Roe, Director Mr. John Butler, Director Security Operations Support Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 jwr@nei.org jcb@nei.org Mr. Charles B. Brinkman Mike Melton, Senior Project Manager Washington Operations 1776 I Street, NW, Suite 400 ABB-Combustion Engineering, Inc. Washington, DC 20006-3708 12300 Twinbrook Parkway, Suite 330 man@nei.org Rockville, MD 20852 brinkmcb@westinghouse.com Dennis Buschbaum PWROG Chairman Mr. James Gresham, Manager Comanche Peak Steam Electric Station Regulatory Compliance and Plant Licensing 6322 North Farm to Marked Rd 56 Westinghouse Electric Company Mail Code E15 P.O. Box 355 Glen Rose, TX 76043 Pittsburgh, PA 15230-0355 Dennis.Buschbaum@luminant.com greshaja@westinghouse.com Mr. James H. Riley, Director Ms. Barbara Lewis Engineering Assistant Editor Nuclear Energy Institute Platts, Principal Editorial Office 1776 I Street, NW 1200 G St., N.W., Suite 1100 Washington, DC 20006-3708 Washington, DC 20005 jhr@nei.org Barbara_lewis@platts.com