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| number = ML090400186 | | number = ML090400186 | ||
| issue date = 02/12/2009 | | issue date = 02/12/2009 | ||
| title = Acceptance Review of Relief Request ISI-04-04-Calvert Cliffs Nuclear Power Plant, Units 1 and 2- | | title = Acceptance Review of Relief Request ISI-04-04-Calvert Cliffs Nuclear Power Plant, Units 1 and 2- | ||
| author name = Pickett D | | author name = Pickett D | ||
| author affiliation = NRC/NRR/DORL/LPLI-1 | | author affiliation = NRC/NRR/DORL/LPLI-1 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 February 12, 2.C'm Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc. Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 ACCEPTANCE REVIEW OF RELIEF REQUEST ISI-04 CALVERT CLIFFS NUCLEAR POWER PLANT (CCNPP), UNIT NOS. 1 AND 2 -(TAC NOS. ME0298 AND ME0299) | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 February 12, 2.C'm Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc. | ||
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 | |||
==SUBJECT:== | |||
ACCEPTANCE REVIEW OF RELIEF REQUEST ISI-04 CALVERT CLIFFS NUCLEAR POWER PLANT (CCNPP), UNIT NOS. 1 AND 2 - (TAC NOS. | |||
ME0298 AND ME0299) | |||
==Dear Mr. Spina:== | ==Dear Mr. Spina:== | ||
By letter dated December 29, 2008, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee), submitted American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI Relief Request ISI-04-04. The proposed relief request would implement a risk-informed safety-based inservice inspection (lSI) program for Class 1 and 2 piping. The relief request is based upon ASME Code Case N-716, "Alternative Piping Classification and Examination Requirements, Section XI Division 1," which is founded on the risk-informed lSI process described in Electric Power Research Institute Topical Report 112657 Rev. B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure." The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | By {{letter dated|date=December 29, 2008|text=letter dated December 29, 2008}}, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee), | ||
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that clarifying information as discussed with your staff during a telephone conversation on February 6, 2009, is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. Specifically, clarification is sought regarding the following sentence found on page 7 of Enclosure 1 to | submitted American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI Relief Request ISI-04-04. The proposed relief request would implement a risk-informed safety-based inservice inspection (lSI) program for Class 1 and 2 piping. The relief request is based upon ASME Code Case N-716, "Alternative Piping Classification and Examination Requirements, Section XI Division 1," which is founded on the risk-informed lSI process described in Electric Power Research Institute Topical Report 112657 Rev. B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure." | ||
[probabilistic risk internal events model is currently being performed by a group J. Spina - | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | ||
The information requested and associated time frames in this letter were discussed with Pat Furio of your staff on February 9, 2009. If you have any questions, please contact me at 301-415-1364. | Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. | ||
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos, 50-317 and 50-318 cc: Distribution via Listserv J. Spina - | The NRC staff has reviewed your application and concluded that clarifying information as discussed with your staff during a telephone conversation on February 6, 2009, is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. Specifically, clarification is sought regarding the following sentence found on page 7 of Enclosure 1 to Attachment 5 of your application: | ||
Sincerely, IRA! Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 cc: Distribution via Listserv Distribution PUBLIC LPLI-1 rtf RidsNrrDraApla RidsNrrDorlLpl1-1 RidsNrrPMDPickett RidsNrrLASLittle RidsOgcMailCenter RidsAcrsAcnwMailCenter GDentel, R1 SDinsmore RidsNrrPMMDavid ADAMS Accession No'.. ML090400186 OFFICE LPLI-1/PM LPLI-1/LA APLAlBC (A) LPLI-1/BC NAME DPickett SLittle AHowe MKowal DATE 02/10/09 02/11/09 02/11/09 02/12/09 OFFICIAL RECORD COpy}} | A gap analysis for the CCNPP PRA [probabilistic risk assessment] | ||
internal events model is currently being performed by a group of vendors. | |||
J. Spina | |||
- 2 In order to make the application complete, the NRC staff requests that the licensee supplement the application by February 20, 2009, to clarify that the above analysis has been performed and that the information contained in the application is complete and reflective of this analysis. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. | |||
The information requested and associated time frames in this letter were discussed with Pat Furio of your staff on February 9, 2009. | |||
If you have any questions, please contact me at 301-415-1364. | |||
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos, 50-317 and 50-318 cc: Distribution via Listserv | |||
J. Spina | |||
- 2 In order to make the application complete, the NRC staff requests that the licensee supplement the application by February 20, 2009, to clarify that the above analysis has been performed and that the information contained in the application is complete and reflective of this analysis. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. | |||
The information requested and associated time frames in this letter were discussed with Pat Furio of your staff on February 9, 2009. | |||
If you have any questions, please contact me at 301-415-1364. | |||
Sincerely, IRA! | |||
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 cc: Distribution via Listserv Distribution PUBLIC LPLI-1 rtf RidsNrrDraApla RidsNrrDorlLpl1-1 RidsNrrPMDPickett RidsNrrLASLittle RidsOgcMailCenter RidsAcrsAcnwMailCenter GDentel, R1 SDinsmore RidsNrrPMMDavid ADAMS Accession No'.. ML090400186 OFFICE LPLI-1/PM LPLI-1/LA APLAlBC (A) | |||
LPLI-1/BC NAME DPickett SLittle AHowe MKowal DATE 02/10/09 02/11/09 02/11/09 02/12/09 OFFICIAL RECORD COpy}} | |||
Latest revision as of 13:19, 14 January 2025
| ML090400186 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/12/2009 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Spina J Calvert Cliffs |
| Pickett D | |
| References | |
| TAC ME0298, TAC ME0299 | |
| Download: ML090400186 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 February 12, 2.C'm Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
ACCEPTANCE REVIEW OF RELIEF REQUEST ISI-04 CALVERT CLIFFS NUCLEAR POWER PLANT (CCNPP), UNIT NOS. 1 AND 2 - (TAC NOS.
ME0298 AND ME0299)
Dear Mr. Spina:
By letter dated December 29, 2008, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee),
submitted American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI Relief Request ISI-04-04. The proposed relief request would implement a risk-informed safety-based inservice inspection (lSI) program for Class 1 and 2 piping. The relief request is based upon ASME Code Case N-716, "Alternative Piping Classification and Examination Requirements,Section XI Division 1," which is founded on the risk-informed lSI process described in Electric Power Research Institute Topical Report 112657 Rev. B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure."
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that clarifying information as discussed with your staff during a telephone conversation on February 6, 2009, is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. Specifically, clarification is sought regarding the following sentence found on page 7 of Enclosure 1 to Attachment 5 of your application:
A gap analysis for the CCNPP PRA [probabilistic risk assessment]
internal events model is currently being performed by a group of vendors.
J. Spina
- 2 In order to make the application complete, the NRC staff requests that the licensee supplement the application by February 20, 2009, to clarify that the above analysis has been performed and that the information contained in the application is complete and reflective of this analysis. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frames in this letter were discussed with Pat Furio of your staff on February 9, 2009.
If you have any questions, please contact me at 301-415-1364.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos, 50-317 and 50-318 cc: Distribution via Listserv
J. Spina
- 2 In order to make the application complete, the NRC staff requests that the licensee supplement the application by February 20, 2009, to clarify that the above analysis has been performed and that the information contained in the application is complete and reflective of this analysis. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frames in this letter were discussed with Pat Furio of your staff on February 9, 2009.
If you have any questions, please contact me at 301-415-1364.
Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 cc: Distribution via Listserv Distribution PUBLIC LPLI-1 rtf RidsNrrDraApla RidsNrrDorlLpl1-1 RidsNrrPMDPickett RidsNrrLASLittle RidsOgcMailCenter RidsAcrsAcnwMailCenter GDentel, R1 SDinsmore RidsNrrPMMDavid ADAMS Accession No'.. ML090400186 OFFICE LPLI-1/PM LPLI-1/LA APLAlBC (A)
LPLI-1/BC NAME DPickett SLittle AHowe MKowal DATE 02/10/09 02/11/09 02/11/09 02/12/09 OFFICIAL RECORD COpy