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| {{#Wiki_filter:Enclosure 1 ENCLOSURE 1 Problem Specification Sent to ORNL Problem Statement In a recent application to NRR, the Calvert Cliffs (CC) Nuclear Power Plant (Unit 2) has requested an extension of its in-service-inspection interval from 10 to 20 years. As part of this request, NRR has required that CC assess if flaws found in the RPV beltline are bounded by the flaw tables in 10CFR50.61a. The documents provided by CC demonstrate that one flaw is not bounded by the 10CFR50.61a flaw tables. | | {{#Wiki_filter:ENCLOSURE 1 Problem Specification Sent to ORNL Problem Statement In a recent application to NRR, the Calvert Cliffs (CC) Nuclear Power Plant (Unit 2) has requested an extension of its in-service-inspection interval from 10 to 20 years. As part of this request, NRR has required that CC assess if flaws found in the RPV beltline are bounded by the flaw tables in 10CFR50.61a. The documents provided by CC demonstrate that one flaw is not bounded by the 10CFR50.61a flaw tables. |
| The goal of this analysis is to use the PFM code FAVOR to assess the TWCF contribution of the single flaw found in CC that is not bounded by the 10CFR50.61a flaw tables. | | The goal of this analysis is to use the PFM code FAVOR to assess the TWCF contribution of the single flaw found in CC that is not bounded by the 10CFR50.61a flaw tables. |
| Input Information Indication #1 (see diagram below): Depth, or through wall extent, or 2a: 0.6-inches Length, or 2c: 0.95-inches Distance between clad/base interface & flaw: 0.4-inches Flaw is located in Intermediate Shell Plate 13 Material: A533B Steel Cu: 0.11 weight percent Ni: 0.56 weight percent P: 0.007 weight percent Mn: 1.45 weight percent RTNDT(u): 10°F Operating time: 60 EFPY ID fluence at flaw location: 7.22x10 19 n/cm 2 Enclosure 1 The pressure vessel Manufacturer: Combustion Engineering Inner Diameter 172-inches Thickness (including cladding): 8.625-inches Cladding thickness: 5/16-inch # of clad layers: 2 Operating Temperature: 548 | | Input Information Indication #1 (see diagram below): |
| °F Transients: Use all base-case transients from the Palisades RPV PRA Information: Use the same information as for Palisades
| | Depth, or through wall extent, or 2a: 0.6-inches Length, or 2c: 0.95-inches Distance between clad/base interface & flaw: 0.4-inches Flaw is located in Intermediate Shell Plate 13 Material: A533B Steel Cu: 0.11 weight percent Ni: 0.56 weight percent P: 0.007 weight percent Mn: 1.45 weight percent RTNDT(u): 10°F Operating time: 60 EFPY ID fluence at flaw location: 7.22x1019 n/cm2 Enclosure 1 |
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| Output Information | | The pressure vessel Manufacturer: Combustion Engineering Inner Diameter 172-inches Thickness (including cladding): 8.625-inches Cladding thickness: 5/16-inch |
| | | # of clad layers: 2 Operating Temperature: 548°F Transients: Use all base-case transients from the Palisades RPV PRA Information: Use the same information as for Palisades Output Information Please use the FAVOR code to provide the following information for both fluence case 1 and fluence case 2 |
| Please use the FAVOR code to provide the following information for both fluence case 1 and fluence case 2 | | * Total TWCF (95th percentile) |
| * Total TWCF (95 th percentile) | | * Total Frequency of crack initiation (FCI) (95th percentile) |
| * Total Frequency of crack initiation (FCI) (95 th percentile) TWCF and FCI contributions from each transient analyzed}} | | TWCF and FCI contributions from each transient analyzed Enclosure 1}} |
Latest revision as of 10:09, 14 November 2019
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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 ML15092A3752015-02-0202 February 2015 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 ML0727401082006-12-18018 December 2006 Differing Professional Opinion from E. Marinos ML0634705992006-12-14014 December 2006 Plant Service List ML0727105902006-06-0101 June 2006 Et/Lt Brief on the Status of the Measurement Uncertainty Recapture Issue ML0534604122005-11-18018 November 2005 Inspection Request Summary: Calvert Cliffs PI&R - IR 2005-07 ML0727104842005-11-15015 November 2005 Ufm Review Status and Anticipated Resolution Process ML0424005762004-08-18018 August 2004 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
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ENCLOSURE 1 Problem Specification Sent to ORNL Problem Statement In a recent application to NRR, the Calvert Cliffs (CC) Nuclear Power Plant (Unit 2) has requested an extension of its in-service-inspection interval from 10 to 20 years. As part of this request, NRR has required that CC assess if flaws found in the RPV beltline are bounded by the flaw tables in 10CFR50.61a. The documents provided by CC demonstrate that one flaw is not bounded by the 10CFR50.61a flaw tables.
The goal of this analysis is to use the PFM code FAVOR to assess the TWCF contribution of the single flaw found in CC that is not bounded by the 10CFR50.61a flaw tables.
Input Information Indication #1 (see diagram below):
Depth, or through wall extent, or 2a: 0.6-inches Length, or 2c: 0.95-inches Distance between clad/base interface & flaw: 0.4-inches Flaw is located in Intermediate Shell Plate 13 Material: A533B Steel Cu: 0.11 weight percent Ni: 0.56 weight percent P: 0.007 weight percent Mn: 1.45 weight percent RTNDT(u): 10°F Operating time: 60 EFPY ID fluence at flaw location: 7.22x1019 n/cm2 Enclosure 1
The pressure vessel Manufacturer: Combustion Engineering Inner Diameter 172-inches Thickness (including cladding): 8.625-inches Cladding thickness: 5/16-inch
- of clad layers: 2 Operating Temperature: 548°F Transients: Use all base-case transients from the Palisades RPV PRA Information: Use the same information as for Palisades Output Information Please use the FAVOR code to provide the following information for both fluence case 1 and fluence case 2
- Total TWCF (95th percentile)
- Total Frequency of crack initiation (FCI) (95th percentile)
TWCF and FCI contributions from each transient analyzed Enclosure 1