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| | number = ML091600307 | | | number = ML091600307 |
| | issue date = 06/09/2009 | | | issue date = 06/09/2009 |
| | title = Calvert Cliffs, Units, 1 & 2 - Response to Request for Additional Information Concerning Relief Request ISI-04-04 | | | title = Units, 1 & 2 - Response to Request for Additional Information Concerning Relief Request ISI-04-04 |
| | author name = | | | author name = |
| | author affiliation = Calvert Cliffs Nuclear Power Plant, Inc, Constellation Energy Group | | | author affiliation = Calvert Cliffs Nuclear Power Plant, Inc, Constellation Energy Group |
Letter Sequence Response to RAI |
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MONTHYEARML0904001862009-02-12012 February 2009
Acceptance Review of Relief Request ISI-04-04-Calvert Cliffs Nuclear Power Plant, Units 1 and 2-(TAC ME0298 and ME0299)
Project stage: Acceptance Review
ML0905401222009-02-24024 February 2009
Acceptance Review of Relief Requests ISI-04-01 Through ISI-04-04-Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2
Project stage: Acceptance Review
ML0910303782009-04-27027 April 2009
Request for Additional Information Concerning the Risk Evaluation for the Fourth Ten-Year Interval Inservice Inspection Program Plan for Calvert Cliffs Nuclear Power Plant Units 1 and 2 (TAC Nos. ME0298 and ME0299)
Project stage: RAI
ML0911802362009-05-0505 May 2009
Request for Additional Information Relief Request No. ISI-04-04 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2
Project stage: RAI
ML0913302472009-05-13013 May 2009
Response to Request for Additional Information - ASME Code Case N-747 Relief Request ISI-04-0 1
Project stage: Response to RAI
ML0915302742009-06-0101 June 2009
Response to Request for Additional Information Concerning Relief Request ISI-04-04, Attachment 1
Project stage: Response to RAI
ML0916003072009-06-0909 June 2009
Units, 1 & 2 - Response to Request for Additional Information Concerning Relief Request ISI-04-04
Project stage: Response to RAI
ML0932200902009-11-19019 November 2009
Relief Requests for the Fourth 10-Year Interval Inservice Inspection Program
Project stage: Other
2009-04-27
[Table View] |
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Category:- No Document Type Applies
MONTHYEARML21211A1522021-10-0404 October 2021
Problem Identification & Resolution Inspection Document Request
ML21194A0632021-07-13013 July 2021
Tabulation of Proposed Changes in License Amendment Request
RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020
Proposed Changes to Decommissioning Trust Agreements
ML19135A1362019-05-15015 May 2019
Aam - Sign in Sheet
ML18096A0102018-04-0404 April 2018
Annual Assessment Meeting 04/04/2018 Sign in Sheet
ML16266A2302016-09-21021 September 2016
ASP Analysis Reject - Calvert Cliffs, Unit 2 Automatic Reactor Trip Due to Loss of Offsite Power to Safety Related Buses (LER-318-2015-002)
ML15327A2242015-12-0101 December 2015
Strainer Head Loss Test 6 Rejection
ML15114A3872015-04-16016 April 2015
4/16/2015 - Calvert Cliffs 2014 Annual Assessment Meeting Sign-In Sheet
ML15051A4102015-02-17017 February 2015
Evaluation of Risk Significance of Permanent ILRT Extension
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IP 95001 Entrance and Exit Meeting Attendance Sheets
ML13364A2832013-12-30030 December 2013
Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013
ML13319A7252013-11-0404 November 2013
CCNPP-CHLE-009 Rev 2 Considerations for Using Marinite in CE Testing
ML12349A2852012-11-0909 November 2012
Seismic Walkdown Checklist, 1A1 Diesel Engine - Page C-150 - Page C-243
ML12349A2842012-11-0909 November 2012
Seismic Wlakdown Checklists, Fuel Oil Storage Tink 21 - Page C-51 - Page C-149
ML12056A0522012-03-12012 March 2012
Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
RS-11-167, Final Effective Joint Proxy Statement/Prospectus Relating to Application for Approval of Indirect Transfer of Control of Licenses2011-10-11011 October 2011
Final Effective Joint Proxy Statement/Prospectus Relating to Application for Approval of Indirect Transfer of Control of Licenses
ML1127100332011-09-28028 September 2011
ROP Tabletop Examples and Results
ML1120201642011-07-21021 July 2011
Operations Plan for Technical Assistance in Calvert Cliffs Independent Spent Fuel Storage Installation License Renewals, Rev. 2, Chg. 0
ML1002615342010-01-26026 January 2010
Attachment (1), SER Restrictions for Calvert Cliffs
ML1001100642009-11-20020 November 2009
Biennial Problem Identification and Resolution Inspection Exit Meeting Roster for 11-20-2009, NRC Inspection Report 2009-007
ML0916003072009-06-0909 June 2009
Units, 1 & 2 - Response to Request for Additional Information Concerning Relief Request ISI-04-04
ML0915302742009-06-0101 June 2009
Response to Request for Additional Information Concerning Relief Request ISI-04-04, Attachment 1
ML0905704862009-02-26026 February 2009
Attachment (1), Summary of Calvert Cliffs, Unit 2 Deviation from MRP-139, Requirements
ML0903706532009-02-0606 February 2009
Enclosure 1 - Problem Specification Sent to ORNL
ML0903706662009-02-0606 February 2009
Enclosure 2 - Detailed Results Received from ORNL
ML0836500592008-12-29029 December 2008
Response to Request for Additional Information Dated October 15, 2008 - Measurement Uncertainty Recapture Power Uprate
ML0831703712008-11-12012 November 2008
Attachment 1, Alternative Pressure Boundary Requirements During Class 1 System Pressure Tests, Request for Alternative Relief Request PT-3-01
ML0817101052008-06-18018 June 2008
Attachment 1, Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
ML0812303862008-05-0101 May 2008
Attachment (1) - Proposed Alternative ISI-020 in Accordance with 10 CFR 50.55a(a)(3)(i) - Alternative Provides Acceptable Level of Quality and Safety
ML0810904932008-04-0808 April 2008
Annual Assessment Meeting Attendance List
ML0734504992007-12-10010 December 2007
Attachment (1) Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0726301142007-09-14014 September 2007
/ P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170
ML0726303192007-09-14014 September 2007
P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List
ML0729901542007-06-21021 June 2007
Inspection Request - Calvert Cliffs PI&R 2007-007
ML0715005442007-05-22022 May 2007
Attendance List for Calvert Cliffs Annual Assessment Meeting
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Differing Professional Opinion from E. Marinos
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Plant Service List
ML0727105902006-06-0101 June 2006
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Inspection Request Summary: Calvert Cliffs PI&R - IR 2005-07
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Ufm Review Status and Anticipated Resolution Process
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72-8 Service List
ML0404104922004-02-20020 February 2004
Order EA-03-009 Service List
ML0331405822003-09-30030 September 2003
License Amendment Request: Increase the Unit 2 Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron and Burnup Credit, Continuation of Attachment 5 Through 6
ML0331405812003-09-30030 September 2003
License Amendment Request: Increase the Unit 2 Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron and Burnup Credit, Attachments 1 Through 5
ML0310504022003-03-31031 March 2003
Calvert Cliffs Annual Assessment Meeting NRC Public Meeting Feedback Form
ML0309903832003-03-31031 March 2003
Annual Assessment Meeting Attendance List
ML0203201882002-01-29029 January 2002
Attachment 1 to Ltr Dated 01/29/02 Re Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Request for Regional Enforcement Discretion
2021-07-13
[Table view] |
Text
Calvert Cliffs Nuclear Power Plant, Inc.
June 9, 2009 ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST ISI-04-04
ATTACHMENT (1) RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST ISI-04-04 1 NRC RAI 1: Section 3.3.1 of your submittal dated December 29, 2008, addresses Additional Examinations. The submittal states in part that, "The process for ordinary flaws is to perform the evaluation using ASME Code,Section XI."
Please explain the term "ordinary flaws" and/or confirm that all flaw evaluations are performed using ASME Code,Section XI.
CCNPP Response
- "Ordinary flaws" refers to the normal process of evaluating flaws and all flaw evaluations are performed using American Society of Mechanical Engineers (ASME) Code,Section XI.
NRC RAI 2: Table IWB-2500-1 of American Society of Mechanical Engineers,Section XI, 2001 Edition with 2004 Addenda requires volumetric and/or surface examination of all Category B-F or B-J Pressure Retaining Dissimilar Metal Welds greater than nominal pipe size (NPS) 1. Based on recent findings of primary water stress-corrosion cracking in Alloy 82/182 dissimilar metal welds, the staff would like more information on your inspection plans for these welds in the 4th Interval ISI Plan for Calvert Cliffs Nuclear Power Plant (CCNPP).
Please describe the inspection plan of Alloy 82/182 dissimilar metal welds greater than NPS 1 in the 4th Interval ISI Plan for CCNPP (e.g., are they included in the RI-ISI program, how many are selected for examination, what examination method(s) are being employed, what is the frequency of examination, disposition of limited coverage (<90%) examinations, etc.).
CCNPP Response
- All Category B-F or B-J Alloy 82/182 dissimilar metal welds greater than NPS 1 included in CCNPP Section XI program were included in CCNPP ASME Code Case N-578 Risk Informed-Inservice Inspection (RI-ISI) program for the current interval, and are also included in the proposed CCNPP ASME Code Case N-716 risk-informed/safety-based inservice inspection (RIS_B) program for the fourth interval. The total population of these welds is 27 for each CCNPP unit. Per the criteria of Code Case N-716, seven of these welds (per unit) were determined to be susceptible to primary water stress corrosion cracking (PWSCC), and six of these welds (per unit) were selected for examination under the RIS_B program.
Per Code Case N-716 (Table 1, Item No. 1.15, "Elements Subject to Primary Water Stress Corrosion Cracking (PWSCC)"), selected butt welds are subject to volumetric examination. Per Note 3 of this Table, the exam includes essentially 100% of the examination location. When the required examination volume or area cannot be examined due to interference by another component or part geometry, limited examinations shall be evaluated for acceptability. Areas with acceptable limited examinations (coverage less than 90%), and their bases, shall be documented and submitted for relief per the requirements of 10 CFR 50.55a.
A plant augmented inspection program has been implemented at CCNPP to meet all the requirements of Materials Reliability Program (MRP)-139, Revision 1, for all butt welds greater than NPS 1. Materials Reliability Program-139, Revision 1, provides requirements for the inspection and management of PWSCC-susceptible welds that are in addition to the requirements of Code Case N-716. Additionally, ATTACHMENT (1) RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST ISI-04-04 2 MRP-139, Revision 1, specifies requirements for welds with limited examinations (coverage less than 90%) such as the consideration of augmented non-destructive examination methods with technical bases, performing a degradation assessment for any volume that remains unexamined due to the limitation and to consider mitigation. Further, per MRP-139, Revision 1, some welds may be required to be examined multiple times during the interval in addition to the examination required by Code Case N-716. The RIS_B program has not and will not be used to eliminate any required MRP-139 examinations or requirements.
NRC RAI 3: On page 10, the licensee provides guidance in Section 3.3.2 "Program Relief Requests." For program relief requests, the licensee refers to the process outlined in Title 10 of the Code of Federal Regulations 50.55a that will be used. Please discuss how the effect on risk of the incomplete examination coverage will be assessed.
CCNPP Response
- Per footnote 3 of Table 1 of Code Case N-716, when the required examination volume or area cannot be examined due to interference by another component or part geometry, limited examinations shall be evaluated for acceptability. Acceptance of limited examinations or volumes shall not invalidate the results of the change-in-risk evaluation (paragraph 5 of Code Case N-716). The change in risk evaluation of Code Case N-716 is consistent with previous risk-informed ISI applications (e.g., EPRI TR-112657) and meets Regulatory Guide 1.174 change in risk acceptance criteria. Areas with acceptable limited examinations, and their bases, shall be documented.
Consistent with previously approved RI-ISI submittals [e.g., Waterford 3 Safety Evaluation (Reference 1)], Constellation will continue to calculate coverage and use additional examinations and techniques in the same manner it has for traditional Section XI examinations.
Experience has shown this process to be weld-specific (e.g., joint configuration). As such the effect on risk, if any, will not be known until that time. Relief requests, if needed, will be submitted per the guidance of 10 CFR 50.55a(g)(5)(iv).
REFERENCE 1. Letter from Mr. T. G. Hiltz (NRC) to Vice President, Operations (Entergy Operations) dated April 28, 2008, Waterford Steam Electric Station, Unit 3 - Request for Alternative W3-ISI-005, Request to use ASME Code Case N-716
