Letter Sequence Acceptance Review |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
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MONTHYEARML0727706052007-10-16016 October 2007
Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Draft Requests for Additional Information Pertaining to Indian Point Generating Station
Project stage: Draft RAI
NL-08-021, License Renewal Application Amendment 22008-01-22022 January 2008
License Renewal Application Amendment 2
Project stage: Other
ML0735305362008-02-15015 February 2008
IP 71003, Post-Approval Site Inspection for License Renewal
Project stage: Other
ML0806702862008-03-0404 March 2008
Letter from David E. Roth & Kimberly A. Sexton to Atomic Safety and Licensing Board
Project stage: Request
ML0806701252008-03-0606 March 2008
Supplement to NRC Staffs Answer to Entergys Motion to Strike the Reply of Westcan, Et Al. to the Responses Filed by Entergy and the NRC Staff
Project stage: Request
ML0810002692008-03-31031 March 2008
Answer of Entergy Nuclear Operations, Inc. to Riverkeepers Request for Admission of Amended Contention TC-1 (Concerning Environmentally Assisted Metal Fatigue)
Project stage: Request
ML0812603812008-05-0505 May 2008
Notice of Closed Meeting to Discuss the NRCs Assessment of Palisades Nuclear Plant Security Performance for the 2007 Calendar Year
Project stage: Request
ENOC-08-00028, J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report2008-05-0808 May 2008
J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report
Project stage: Request
NL-08-096, Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses2008-07-0808 July 2008
Request for Relief to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses
Project stage: Request
ML0820307962008-07-21021 July 2008
License Amendment Request for License Condition to Support Implementation of Extended In-Service Inspection Interval
Project stage: Request
ML0827603842008-10-0101 October 2008
Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel
Project stage: Request
ML0827603832008-10-0101 October 2008
Attachment 1, Evaluation of the Proposed Change to License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel
Project stage: Request
AEP-NRC-2008-41, Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License - Amendment for Submittal of ISI Information and Analyses2008-10-0909 October 2008
Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License - Amendment for Submittal of ISI Information and Analyses
Project stage: Request
ML0831505562008-11-14014 November 2008
Acceptance Review Letter Relief Request (ISIR-29) for Use of Risk-Informed Extension of the Reactor Pressure Vessel Inservice Inspection (ISI) Interval from 10 to 20 Years
Project stage: Acceptance Review
ML0833100062008-11-26026 November 2008
Draft RAIs Request for Relief to Extend the D.C. Cook Unit 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination (ISIR-29)
Project stage: Draft RAI
ML0834300182008-12-10010 December 2008
Request for Additional Information Relief Request (ISIR-29) for Use of Risk-Informed Extension of the Inservice Inspection Interval for the Reactor Pressure Vessel Weld Examination
Project stage: RAI
ML0904304002009-01-14014 January 2009
Request to Extend Inservice Inspection Interval for the Reactor Vessel Weld Examination and Request for License Amendment for Submittal of ISI Information and Analyses - Response to Request for Additional Information
Project stage: Response to RAI
CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses2009-03-0404 March 2009
Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses
Project stage: Request
ML0907207042009-03-13013 March 2009
E-mail Transmitting Verbal Authorization for Relief Requests ISIR-29 and ISIR-30
Project stage: Approval
ML0912601632009-06-0808 June 2009
Evaluation of Relief Request (ISIR-29) to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination
Project stage: Approval
ML0918907412009-07-0808 July 2009
Withdrawal of License Amendment Request: Reporting of Reactor Vessel Inservice Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel In-Service Inspection Interval
Project stage: Withdrawal
2CAN100902, Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2009-10-29029 October 2009
Request for Alternative ANO2-ISI-004 - Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations
Project stage: Request
TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-022009-10-29029 October 2009
Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02
Project stage: Request
RC-11-0117, Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval2011-08-16016 August 2011
Request to Use Alternatives to ASME Code Requirements in VCSNS 3rd Ten Year Inservice Inspection Interval (RR-III-07) Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval
Project stage: Other
2CAN041303, Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations2013-04-24024 April 2013
Additional Reactor Vessel Closure Head Weld Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations
Project stage: Request
2CAN111305, Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-0042013-11-11011 November 2013
Unit 2, Response to Request for Additional Information Related to Relief Request ANO2-ISI-004
Project stage: Response to RAI
AEP-NRC-2018-51, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-082018-08-0101 August 2018
Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-4-08
Project stage: Request
2008-05-08
[Table View] |
Similar Documents at Cook |
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 14, 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place BriQgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 2 - ACCEPTANCE REVIEW RE:
RELIEF REQUEST (ISIR-29) FOR USE OF RISK-INFORMED EXTENSION OF THE REACTOR PRESSURE VESSEL INSERVICE INSPECTION (lSI)
INTERVAL FROM 10 TO 20 YEARS (TAC NO. MD9934)
Dear Mr. Rencheck:
By letter dated October 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082980354), Indiana Michigan Power Company (I&M) submitted a relief request for the Donald C. Cook Nuclear Plant, Unit 2. The proposed relief request (ISIR-29) pertains to the use of a risk-informed extension of the reactor pressure vessel lSI interval from 10 to 20 years.
The U.S. Nuclear Regulatory Commission (NRC) approved topical report WCAP-6168-NP-A, Revision 2, "Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval,"
dated May 8,2008 (ADAMS Accession No. ML081060051). The WCAP provides for extension of the lSI interval for certain pressure retaining welds in the reactor vessel from 10 to 20 years.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations, 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 purpose of this letter is to provide the final results of the NRC staff's acceptance review of this 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 and make an independent assessment regarding the acceptability of the proposed change. 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 NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review,
M. Rencheck
- 2 you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3049.
Sincerely,
~//~
./
~
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-316 cc: Distribution via ListServ
November 14, 2008 M. Rencheck
- 2 you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3049.
Sincerely, lRAI Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-316 cc: Distribution via ListServ DISTRIBUTION:
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