ML100770137: Difference between revisions
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{{#Wiki_filter:March 29, 2010 Mr. Biff Bradley, Director Risk Assessment Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 | {{#Wiki_filter:March 29, 2010 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 TOPICAL REPORT WCAP-16294-NP, REVISION 0, | FINAL SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE TOPICAL REPORT WCAP-16294-NP, REVISION 0, RISK-INFORMED EVALUATION OF CHANGES TO TECHNICAL SPECIFICATION REQUIRED ENDSTATES FOR WESTINGHOUSE NSSS [NUCLEAR STEAM SUPPLY SYSTEM] PWRs | ||
[PRESSURIZED WATER REACTORS], AUGUST 2005 (TAC NO. MD5134) | |||
==Dear Mr. Bradley:== | ==Dear Mr. Bradley:== | ||
By letter dated September 9, 2005, as supplemented by letters dated December 12, 2007, and November 26, 2008, Nuclear Energy Institute (NEI) submitted Topical Report (TR) WCAP-16294-NP, Revision 0, | By letter dated September 9, 2005, as supplemented by letters dated December 12, 2007, and November 26, 2008, Nuclear Energy Institute (NEI) submitted Topical Report (TR) WCAP-16294-NP, Revision 0, Risk-Informed Evaluation Of Changes To Technical Specification Required Endstates For Westinghouse NSSS PWRs, to the U.S. Nuclear Regulatory Commission (NRC) staff. By letter dated December 10, 2009, an NRC draft safety evaluation (SE) regarding our approval of TR WCAP-16294-NP, Revision 0, was provided for your review and comment. By letter dated January 12, 2010, the NEI commented on the draft SE. The NRC staff's disposition of NEIs comments on the draft SE are discussed in Enclosure 2. | ||
The NRC staff has found that TR WCAP-16294-NP, Revision 0, is acceptable for referencing in licensing applications for Westinghouse designed pressurized water reactors 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 NRC staff has found that TR WCAP-16294-NP, Revision 0, is acceptable for referencing in licensing applications for Westinghouse designed pressurized water reactors 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. | ||
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. | 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. Also, the accepted version must contain historical review information, including NRC requests for additional information (RAI) and your responses after the title page. The accepted version shall include an "-A" (designating accepted) following the TR identification symbol. | 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. Also, the accepted version must contain historical review information, including NRC requests for additional information (RAI) and your responses after the title page. The accepted version shall include an "-A" (designating accepted) following the TR identification symbol. | ||
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs: | B. Bradley As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs: | ||
: 1. The RAIs and RAI responses can be included as an Appendix to the accepted version. | : 1. The RAIs and RAI responses can be included as an Appendix to the accepted version. | ||
: 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR. | : 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR. | ||
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 referencing. | ||
Sincerely, | Sincerely, | ||
/RA/ | |||
Project No.: | Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No.: 689 | ||
==Enclosures:== | ==Enclosures:== | ||
: 1. Final SE 2. Resolution of NEI Comments | : 1. Final SE | ||
: 2. Resolution of NEI Comments cc w/encl: See next page | |||
cc w/encl: | |||
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs: | B. Bradley As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs: | ||
: 1. The RAIs and RAI responses can be included as an Appendix to the accepted version. | : 1. The RAIs and RAI responses can be included as an Appendix to the accepted version. | ||
: 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR. | : 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR. | ||
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 referencing. | ||
Sincerely, | Sincerely, | ||
/RA/ | |||
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No.: 689 | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Final SE 2. Resolution of NEI Comments cc w/encl: | : 1. Final SE | ||
: 2. Resolution of NEI Comments cc w/encl: See next page DISTRIBUTION: | |||
ADAMS ACCESSION NO.: | PUBLIC PSPB Reading File RidsNrrDpr RidsNrrDprPspb RidsNrrPMTMensah RidsNrrLADBaxley RidsOgcMailCenter RidsAcrsAcnwMailCenter RidsNrrDss RidsNrrDra RidsNrrDraApla RidsNrrDssSrxb RidsNrrDssScvb RidsNrrDssSpbc RidsNrrDirs/Tsb RisNrrDirp/Rib RidsNrrDe SRosenberg (HardCopy) | ||
ADAMS ACCESSION NO.: | |||
Final SE Letter: ML100770137 Final SE: ML100770146 Comment Resolution Table: ML100770127 | |||
*No major changes to SE input. NRR-043 OFFICE PSPB/PM PSPB/LA DRA/APLA DSS/SRXB* DSS/SCVB* DSS/SBPB* DIRS/IRIB* | |||
NAME TMensah DBaxley DHarrison GCranston RDenning MWaters TKobetz (Hylton for) (GPurciarelo (JIsom for) for) | |||
DATE 03/25/10 03/25/10 03/23/10 03/18/08 03/18/08 05/ 14 /09 05/ 19 /09 OFFICE DSS/SNPB DE/EEEB* DIRS/ITSB DPR/PSPB DPR NAME AMendiola GWilson RElliott SRosenberg TBlount (w/comment) | |||
DATE 0323/10 05/20 /09 03/23 /10 03/29/10 03/29/10 OFFICIAL RECORD COPY | |||
Mr. | Nuclear Energy Institute Project No. 689 cc: | ||
Mr. Anthony Pietrangelo, Senior Vice President & Chief Nuclear Officer Nuclear Generation Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 arp@nei.org Mr. Jack Roe, Director Security Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 jwr@nei.org Mr. Charles B. Brinkman Washington Operations ABB-Combustion Engineering, Inc. | |||
12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 brinkmcb@westinghouse.com Mr. James Gresham, Manager Regulatory Compliance and Plant Licensing Westinghouse Electric Company P.O. Box 355 Pittsburgh, PA 15230-0355 greshaja@westinghouse.com Ms. Barbara Lewis Assistant Editor Platts, Principal Editorial Office 1200 G St., N.W., Suite 1100 Washington, DC 20005 Barbara_lewis@platts.com | |||
Mr. John Butler, Director Operations Support Nuclear Energy Institute | Mr. Alexander Marion, Vice President Nuclear Operations Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 am@nei.org Mr. John Butler, Director Operations Support Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 jcb@nei.org Dennis Buschbaum PWROG Chairman Comanche Peak Steam Electric Station 6322 North Farm to Marked Rd 56 Mail Code E15 Glen Rose, TX 76043 Dennis.Buschbaum@luminant.com}} | ||
Latest revision as of 20:42, 13 November 2019
| ML100770137 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 03/29/2010 |
| From: | Blount T Division of Policy and Rulemaking |
| To: | Bradley B Nuclear Energy Institute |
| Mensah T, NRR/DPR, 415-3610 | |
| References | |
| TAC MD5134 | |
| Download: ML100770137 (5) | |
Text
March 29, 2010 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 TOPICAL REPORT WCAP-16294-NP, REVISION 0, RISK-INFORMED EVALUATION OF CHANGES TO TECHNICAL SPECIFICATION REQUIRED ENDSTATES FOR WESTINGHOUSE NSSS [NUCLEAR STEAM SUPPLY SYSTEM] PWRs
[PRESSURIZED WATER REACTORS], AUGUST 2005 (TAC NO. MD5134)
Dear Mr. Bradley:
By letter dated September 9, 2005, as supplemented by letters dated December 12, 2007, and November 26, 2008, Nuclear Energy Institute (NEI) submitted Topical Report (TR) WCAP-16294-NP, Revision 0, Risk-Informed Evaluation Of Changes To Technical Specification Required Endstates For Westinghouse NSSS PWRs, to the U.S. Nuclear Regulatory Commission (NRC) staff. By letter dated December 10, 2009, an NRC draft safety evaluation (SE) regarding our approval of TR WCAP-16294-NP, Revision 0, was provided for your review and comment. By letter dated January 12, 2010, the NEI commented on the draft SE. The NRC staff's disposition of NEIs comments on the draft SE are discussed in Enclosure 2.
The NRC staff has found that TR WCAP-16294-NP, Revision 0, is acceptable for referencing in licensing applications for Westinghouse designed pressurized water reactors 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.
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. Also, the accepted version must contain historical review information, including NRC requests for additional information (RAI) and your responses after the title page. The accepted version shall include an "-A" (designating accepted) following the TR identification symbol.
B. Bradley As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
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
Enclosures:
- 1. Final SE
- 2. Resolution of NEI Comments cc w/encl: See next page
B. Bradley As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TR were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
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
Enclosures:
- 1. Final SE
- 2. Resolution of NEI Comments cc w/encl: See next page DISTRIBUTION:
PUBLIC PSPB Reading File RidsNrrDpr RidsNrrDprPspb RidsNrrPMTMensah RidsNrrLADBaxley RidsOgcMailCenter RidsAcrsAcnwMailCenter RidsNrrDss RidsNrrDra RidsNrrDraApla RidsNrrDssSrxb RidsNrrDssScvb RidsNrrDssSpbc RidsNrrDirs/Tsb RisNrrDirp/Rib RidsNrrDe SRosenberg (HardCopy)
ADAMS ACCESSION NO.:
Final SE Letter: ML100770137 Final SE: ML100770146 Comment Resolution Table: ML100770127
- No major changes to SE input. NRR-043 OFFICE PSPB/PM PSPB/LA DRA/APLA DSS/SRXB* DSS/SCVB* DSS/SBPB* DIRS/IRIB*
NAME TMensah DBaxley DHarrison GCranston RDenning MWaters TKobetz (Hylton for) (GPurciarelo (JIsom for) for)
DATE 03/25/10 03/25/10 03/23/10 03/18/08 03/18/08 05/ 14 /09 05/ 19 /09 OFFICE DSS/SNPB DE/EEEB* DIRS/ITSB DPR/PSPB DPR NAME AMendiola GWilson RElliott SRosenberg TBlount (w/comment)
DATE 0323/10 05/20 /09 03/23 /10 03/29/10 03/29/10 OFFICIAL RECORD COPY
Nuclear Energy Institute Project No. 689 cc:
Mr. Anthony Pietrangelo, Senior Vice President & Chief Nuclear Officer Nuclear Generation Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 arp@nei.org Mr. Jack Roe, Director Security Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 jwr@nei.org Mr. Charles B. Brinkman Washington Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 brinkmcb@westinghouse.com Mr. James Gresham, Manager Regulatory Compliance and Plant Licensing Westinghouse Electric Company P.O. Box 355 Pittsburgh, PA 15230-0355 greshaja@westinghouse.com Ms. Barbara Lewis Assistant Editor Platts, Principal Editorial Office 1200 G St., N.W., Suite 1100 Washington, DC 20005 Barbara_lewis@platts.com
Mr. Alexander Marion, Vice President Nuclear Operations Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 am@nei.org Mr. John Butler, Director Operations Support Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 jcb@nei.org Dennis Buschbaum PWROG Chairman Comanche Peak Steam Electric Station 6322 North Farm to Marked Rd 56 Mail Code E15 Glen Rose, TX 76043 Dennis.Buschbaum@luminant.com