Letter Sequence Draft RAI |
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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
From:
Terry Beltz Sent:
Wednesday, November 26, 2008 6:42 AM To:
'mkscarpello@aep.com'; 'jrwaters@aep.com' Cc:
Dan Widrevitz; Matthew Mitchell
Subject:
Draft RAI re: Request for Relief to Extend the D.C. Cook Unit 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination (ISIR-29) (TAC No. 9943)
Michael and Joe By letter dated October 9, 2008 (ADAMS Accession No. ML082980354), Indian Michigan Power Company (I&M) submitted a relief request for the Donald C. Cook Nuclear Plant Unit 2 (CNP-2). The proposed relief request pertains to a new inservice inspection (ISI) schedule for the CNP-2 reactor vessel shell welds.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Vessels and Internals Integrity Branch (CVIB) has completed its preliminary review of your submittal. The staff requires additional information to complete the review.
Our technical reviewer, Daniel Widrevitz, has developed the following questions which we would like to discuss with you in a conference call:
RAI 1
In Section 3.4 of the Final Safety Evaluation Report issued 05/09/2008 (ADAMS Accession No. ML081060045), the NRC staff notes that licensees submitting a request for an alternative based on Topical Report (TR) WCAP-16168,Risk-Informed Extension of the Reactor Vessel In-Service Inspection Interval, must submit the following plant-specific information:
- 1. Licensees must demonstrate that the RTmax-x and the shift in the Charpy transition temperature produced by irradiation defined at the 30 ft-lb energy level, T30 must be calculated using the latest approved methodology documented in Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, or other NRC-approved methodology.
Other NRC-approved methodology includes equations 5, 6, and 7 as described in paragraph (g) of the proposed Title 10 of the Code of Federal Regulations (CFR) 50.61a rule as published in the Federal Register, Vol. 72, No. 191, dated October 3, 2007. However, paragraph (f)(6) of the proposed rule contains a prescriptive approach to determining the validity of implementing equations 5 through 7 of paragraph (g) for the calculation of T30 values. Data from a plant-specific or integrated surveillance program shall be evaluated in accordance with 10 CFR 50.61a(f)(6) to validate use of the associated embrittlement model.
The licensee has implemented the use of equations prescribed in proposed 10 CFR 50.61a(g),
NUREG-1874, and WCAP-16168 to determine T30 values for the beltline materials.
The NRC staff requests information consistent with the requirements of proposed rule 10 CFR 50.61a(f)(6) that establishes the applicability of equations 5 through 7 as given in 10 CFR 50.61a(g) for calculating T30 values for their plants beltline materials.
RAI 2
The licensee states that they are bounded by 7 heatup/cooldowns per year in Table 1 of the submittal.
Please cite the plant design basis for heatup/cooldowns per year.
RAI 3
The submittal the licensee cites compositions in terms of Cu, Ni, P, and Mn for Items 1-9 in Table 3 of the submittal. These compositions are not consistent with NRC records in Reactor Vessel Integrity Database (RVID).
Please explain where the Cu, Ni, and P compositions were accepted by the NRC or provide new data. Also, please explain on what basis the reported Mn compositions were determined.
This e-mail aims solely to prepare you and others for the proposed conference call. We can discuss the draft questions and how to disposition them during any subsequent conference call.
This e-mail does not formally convey an NRC staff position, nor does it formally request additional information. With or without the conference call, we plan to issue the formal RAIs to you in the near future and no later than December 12, 2008.
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov cc: Daniel Widrevitz Matthew Mitchell E-mail Properties Mail Envelope Properties ()
Subject:
Draft RAI re: Request for Relief to Extend the D.C. Cook Unit 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination (ISIR-29) (TAC No. 9943)
Sent Date: 11/25/2008 3:11:22 PM Received Date: 11/26/2008 6:42:00 AM From: Terry Beltz
Created By: Terry.Beltz@nrc.gov Recipients:
mkscarpello@aep.com ('mkscarpello@aep.com')
Tracking Status: None jrwaters@aep.com ('jrwaters@aep.com')
Tracking Status: None Dan.Widrevitz@nrc.gov (Dan Widrevitz)
Tracking Status: None Matthew.Mitchell@nrc.gov (Matthew Mitchell)
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 14612 11/25/2008 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:
