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Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23241A8432023-08-29029 August 2023 Enclosure 3 - Response to Request for Additional Information - Non-Proprietary Version ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23166A1052023-06-15015 June 2023 Response to Request for Additional Information Related to the License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML23155A0012023-06-0404 June 2023 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (C RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21208A0072021-07-26026 July 2021 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 ML20317A1122020-11-12012 November 2020 Final Response and Close-out to Generic Letter 2004-02 ML20280A5132020-10-0606 October 2020 Response to Request for Additional Information - End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20182A1102020-06-30030 June 2020 Response to Request for Additional Information to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements Voltage ML20107F7652020-04-16016 April 2020 Response to Request for Additional Information to License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19282B7182019-10-0909 October 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 ML19217A3372019-08-0606 August 2019 Response to RAI #6 Regarding the Application to Adopt 10 CFR 50.69 ML19217A1432019-08-0505 August 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19200A2162019-07-19019 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19183A0122019-07-0101 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18316A0342018-11-12012 November 2018 Response to Request for Additional Information: Proposed Changes to Technical Specification 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to 14 ... ML18283A0342018-10-10010 October 2018 Supplement to Final Response to Generic Letter 2004-02, Dated August 13, 2018 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. ML18201A4062018-06-21021 June 2018 Plants, Units 1 and 2 - Exelon'S Response to NRC Questions ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18047A1242018-02-16016 February 2018 Relief Requests Associated with Fifth Ten-Year Lnservice Testing Interval: Supplement 1 - Response to Request for Additional Information ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML18018B3402018-01-18018 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. ML18011A6652018-01-11011 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML17081A3032017-03-22022 March 2017 Response to Request for Additional Information to License Amendment Request - Control Room Emergency Ventilation System RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-003, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-01-0505 January 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML16246A2022016-09-0101 September 2016 Response to Request for Additional Information Regarding Relief Request for Dissimilar Metal Butt Weld Examinations 2023-08-29
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- ..,:;.. '**t .: -7 Exelon Generation Mark Flaherty Plant Manager June 8, 2016 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 '*** 410 495 5205 Office www.exeloncorp.com mark.flaherty@exeloncorp.com 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Supplemental Response to Generic Letter 2004-02
References:
- 1. Letter from Mr. G. H. Gellrich (CCNPP) to Document Control Desk (NRC),
- dated July 23, 2010, Request for Additional Information Regarding Generic Letter 2004-02 2. Letter from Mr. D. V. Pickett (NRC) to Mr. G. H. Gellrich (CCNPP), dated, April 2, 2010, Request for Additional Information Re: Generic Letter 2004-02 Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 -(TAC Nos. MC4672 and MC4673) In Reference 1, Calvert Cliffs provided our response to the Nuclear Regulatory Commission's (NRC) request for additional information (RAI) contained in Reference
- 2. In response to NRC RAI 1 Calvert Cliffs provided revised Zone of Influence (ZOI) information for use in the Debris Generation calculations.
In response to NRC RAI 1 O Calvert Cliffs provided revised debris size distribution information for Nukon insulation.
Calvert Cliffs has discovered additional information on certain materials which we believe will enable us to revise the ZOI and debris size distribution information for these materials.
A description of the revised ZOI and debris size distribution information is provided in Attachment (1 ). This information supersedes the applicable information originally provided in Reference
- 1. This letter contains no regulatory commitments.
Should you have questions regarding this matter, please contact Mr. Larry D. Smith at (410) 495-5219.
Document Control Desk June 8, 2016 Page2 I declare under penalty of perjury that the foregoing is true and correct. Executed on June 8, 2016. Respectfully, Mark Flaherty Pla,nt Manager MDF/KLG/bjm
Attachment:
(1) Supplemental Response to Generic Letter 2004-02, Revised Zone of Influence and Debris Size Distribution Information cc: NRC Project Manager, Ca,lvert Cliffs NRC Regional Administrator, Region I NRC Resident Inspector, Calvert Cliffs S. Gray, MD-DNR ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION Calvert Cliffs Nuclear Power Plant June 8, 2016 ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION In Reference (1) Calvert Cliffs provided Zone of Influence (ZOI) and debris characteristic data for Nukon, Thermal Wrap, mineral wool and generic fiberglass insulation and lead shielding blankets.
We have discovered additional information on certain materials which we believe will enable us to revise the ZOI and/or debris size distributions information for these materials.
A description of the revised ZOI and debris size distribution information is presented below. NUKON AND THERMAL WRAP INSULATION In Reference (2) Calvert Cliffs informed the Nuclear Regulatory Commission (NRC) that we are pursuing a risk-informed resolution to GSl-191 and response to Generic Letter 2004-02. The debris generation calculation for the risk-informed approach uses the BADGER* software to determine debris quantities generated.
This software includes a calculation of the average distance (centroid) from the break to the insulation, which is used with four piecewise functions to calculate debris size fractions.
The functions were derived in a calculation
[Reference (3)] using an approach that is consistent with the methodology set forth in Appendix II of NEI 04-07 Volume 2 [Reference (2)]. The functions provide a size distribution for Nukon and Thermal Wrap Low Density Fiberglass insulation on piping and components based on Air Jet Impact Test (AJIT) data. The average centroid magnitude (C) of the break location relative to the target is an independent variable that is used to calculate a corresponding fraction of fines, small pieces, large pieces, and intact pieces generated for given break. Therefore, the size distribution varies based on the distance of the insulation from the break (i.e., insulation debris generated near the break location would consist of more small pieces than insulation debris generated near the edge of the ZOI). The piecewise functions are summarized in Table 1 below, and will be used as an alternative with the previously approved size distribution data. Table 1 -BADGER Nukon & Thermal Wrap Debris Size Distribution Debris Size Average (Centroid)
Distance from Break Location to Target OD-4DZOI 4D-15DZOI 15D-17D ZOI Fines Fraction Ffines= 0.2 Ftines = -0.01364 X C + 0.2546 Ffines = -0.025 X C + 0.425 (Ftines) Small Pieces Fsma11s= 0.8 Fsma/ls= -0.0682 X C+ 1.0724 Fsmal/s= -0.025 X C+ 0.425 Fraction (Fsma11s)
Large Pieces Fiarge= 0 Fiarge = 0.0393 X C-0.157 F1arge= -0.215 X C+ 3.655 Fraction ( Fiarne) Intact Pieces hntact= 0 hntact= 0.0425 X C-0.170 hntact= 0.265 X C-3.505 Fraction CFintact)
MINERAL WOOL INSULATION The mineral wool at Calvert Cliffs was provided by Transco Products and is encapsulated in stainless steel cassettes.
The mineral wool cassettes are virtually identical to that of the original Transco reflective metal insulation (RMI) installed at Calvert Cliffs but with a different filler material, i.e., mineral wool fibers instead of stainless steel foils. Based on the robust nature of these cassettes, the ZOI for the Transco mineral wool is closer to that of Transco RMI than that of low density fiberglass.
The Transco stainless steel cassette system includes inner and outer sheaths, slotted end panels, and latch & strike closure buckles similar to one of the RMI cassette configurations tested in the air jet impact testing [Reference (6)]. The approved ZOI for Transco RMI of 2.0D 1 ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION
[Reference (4)] was developed from this air jet impact testing. The tested cassettes contained metal foil and produced none or very little transportable debris. The contained material contributes no strength to the cassettes.
Therefore, the destruction pressure for the Transco mineral wool cassettes and RMI cassettes are considered equal. However, to account for the difference in filler material, the ZOI for the mineral wool cassettes will be conservatively increase by a factor of 2 from 2.0D to 4.0D. The debris size for the mineral wool will be conservatively assumed to be 100% fine fibers. GENERIC FIBERGLASS INSULATION The generic fiberglass insulation at Calvert Cliffs does not have a cloth jacket that the Nukon and Thermal Wrap insulation have, and is instead exposed insulation molded of heavy density resin bonded inorganic glass fibers inside the jacketing.
Therefore, there are no undamaged pillows of insulation for this material, and all insulation that would have been characterized as "intact pieces" will be assumed to be "large" pieces. The outer jacket is 0.01 O" stainless steel sheet metal held together with rivets. This fiberglass and has a bulk density generally greater and no lower than Nukon and Thermal Wrap. Calvert Cliffs assumes that the ZOI and debris size distribution for generic fiberglass are the same as that used for Nukon and Thermal Wrap based on the insulation' density. The comparison of debris damage for three insulation types with differing densities shown in Figure 11-8 of Reference (4), Volume 2, supports the assumption of less damage for a higher density material.
This assumption was also accepted in Reference (5) by the NRC. Also note that since there is substantially less generic fiberglass than Nukon and Thermal wrap at Calvert Cliffs, the accurate prediction of the size distribution for generic fiberglass is not nearly as important as it is for Nukon and Thermal Wrap. The n:iass percentage of generic fiberglass relative to total fibrous . debris load is 20% for the bounding break at Calvert Cliffs. LEAD SHIELDING BLANKETS The lead shielding blankets potentially exposed to high energy line break jet are both hanging blankets hung adjacent to piping and wrapped around piping or components.
Typically, there are two lead blankets between the piping and the surrounding area. Blast testing of lead blankets similar to those used at Calvert Cliffs has been performed with both air jets and steam jets. The air jet testing conducted as part of the AJITs is included in the BWR URG for ECCS Suction Strainer Blockage [Reference (6)]. The steam jet testing was performed by Wyle and is documented in WCAP-16727-P
[Reference (7)]. The Wyle testing is not used to quantify ZOI information.
This testing is used to show that open back (freely hanging) blankets will be torn from their grommets and not generate fine debris when near a break jet and that open back blankets are less likely to generate debris than those installed in a strong back configuration.
Furthermore, the inner and outer cover and lead wool on the break side of a lead blanket are sacrificial and provide protection to the inner and outer cover on the opposite side of the blanket. The AJITs subjected rubberized cloth coated lead shielding blankets to a range of surface pressures, the maximum pressure being 40 psig. The lead blankets were wrapped around a 12 inch pipe in these tests, not a free hanging, open-back configuration.
This configuration is similar to the strong back configuration discussed in the Wyle testing, even though the backing in this test was a pipe, not a flat plate. 2 ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION No debris was generated in any of these tests. Since these tests were performed with an air jet, the damage pressures is reduced by 40% to account for potentially enhanced debris generation in a two phase jet, consistent with Reference (2). Therefore, a ZOI corresponding to a damage pressure of 24 psig [= (1-0.4)*40]
is applicable to the lead blankets wrapped around piping and components and it is conservative for the free-hanging lead blankets since the blankets at Calvert Cliffs have an open-back configuration.
This damage pressure corresponds to a PWR ZOI of 5.4 D. Lead Wool Although lead wool debris may be generated, it will not transport to the strainer due to the high density of lead. Lead Blanket Covers In the AJITs, no lead blanket debris was generated for surface pressures corresponding to a ZOI of 5.4 D. In order to determine the size distribution for the lead blanket cover debris which could potentially be generated inside of 5.4 D, other tests performed as part of the AJITs were used. The cloth cover used on NUKON blankets is similar to the lead blanket Alpha Maritex cover materials, except that the NUKON cover uses a plain weave while the Alpha Maritex 3259-2-SS and 8459-2-SS covers use a 4-harness and 8-harness satin weave, respectively.
The NUKON cover cloth is made of 18 oz/yd 2 E-glass. Both Alpha Maritex 3259-2-SS and 8459-2-SS are made with G37 fiberglass yarn, which is also E-glass. The density of Alpha Maritex 3259-2-SS (the inner cover) is 17.5 oz/yd 2 while the density of Alpha Maritex 9459:..2-ss (the outer cover) is 34 oz/yd 2* The primary difference between the NUKON cover and the Alpha Maritex products is the weave type. Typically, a plain weave is the least tear resistant since it has a very tight construction which has the least amount of internal*
slippage/yarn mobility.
In addition, .only one yarn bears the load in a plain weave when the fabric is torn. However, satin weaves have fewer yarn interlacings per area (less tight weave) and therefore allow more internal slippage.
Furthermore, multiple yarns bear the load in a satin weave when the fabric is torn. This results in satin weaves, used in the Alpha Maritex covers, being much more tear resistant than plain weaves, used in NUKON cloth covers. Although the materials of construction are similar for the NUKON cloth cover and the Alpha Maritex products, the plain weave utilized in the NUKON cloth cover is less tear resistant than the satin weave utilized in the Alpha Maritex covers. Therefore, the fiberglass cover used for NUKON is less robust than the lead blanket inner and outer covers. Thus, the debris generation properties for the NUKON cover are conservative for Alpha Maritex 3259-2-SS and Alpha Maritex 8459-2-SS.
The AJITs subjected unjacketed NUKON blankets installed on a 12 inch pipe to a range of pressures with the maximum pressure being 190 psig. In all of these tests, the cloth cover and scrim failed in large intact sections and was determined to be non-transportable.
Since these tests were performed with an air jet, the damage pressure is reduced by 40% to account for potentially enhanced debris generation in a two-phase jet. An air jet damage pressure of 190 psig corresponds to a two-phase damage pressure of 114 psig [= (1-0.4)*190], which 3 ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION corresponds to a ZOI of 2.1 D. Therefore, lead blanket cover debris generated beyond 2.1 D is considered to be large or intact pieces. Within a ZOI of 2.1 D, the lead blanket covers on the break side of the lead wool in the blankets closest to the break are considered to become 20% fines and 80% small pieces. As the lead blanket covers are more robust than NUKON blanket covers, this approach is conservative.
The lead blanket covers on the opposite side of the lead wool in the blankets closest to the break are considered to form large pieces or remain intact, as are the lead blanket covers on the 2nd outboard set of lead blankets where two blankets are essentially "stacked" next to each other. These covers are shielded from the break by the innermost lead wool and inner and outer covers. This approach is reasonable since the lead blankets are freely hanging, and therefore would be torn from their grommets and projected away from the pipe in the event that a break occurs. The size distributions and sub-zone ZOls for lead shielding blankets are shown in Table 2. Table 2 -Lead Shielding Blanket Debris Size Distribution Debris Type Size Size Distribution 2.1DZOI 2.1 D .-5.4D ZOI Lead Blanket Cover Fines 20% 0% Layers Closest to Pipe Break Small Pieces 80% \0% (Open Back Configuration)
LarQe/lntact Pieces 0% 100% Remaining Lead Blanket Cover Layers Fines 0% 0% Small Pieces 0% 0% (Open Back Configuration)
LarQe/I ntact Pieces 10.0% 100% Wrapped Lead Blanket Cover Layers Fines d% 0% Small Pieces 0% 0% (Strong Back Configuration)
Large/Intact Pieces* 100% 100% This size distribution for lead blanket cover material was also accepted by the NRC in Reference (8).
REFERENCES:
(1) Letter from Mr. G. H. Gellrich (CCNPP) to Document Control Desk (NRC), dated July 23, 201 O, Request for Additional Information Regarding Generic Letter 2004-02 (2) Letter from Mr. G. H. Gellrich (Exelon) to Document Control Desk (NRC), dated November 17, 2015, Calvert Cliffs GSl-191 Resolution Plan (3) CA10007, Attachment A, ENERCON Calculation No, GSl191-CALC-001, Revision 1, "Insulation ZOI Size Distribution Report (4) NEI 04-07, Revision 0, December 2004, "Pressurized Water Reactor Sump Performance Evaluation Methodology," Volume 1 and Volume 2 (5) NRG Audit Report, "Indian Point Energy Center Corrective Actions for Generic Letter 2004-02", ADAMS Accession Number ML082050433 4
ATTACHMENT (1) SUPPLEMENTAL RESPONSE TO GENERIC LETTER 2004-02, REVISED ZONE OF INFLUENCE AND DEBRIS SIZE DISTRIBUTION INFORMATION (6) C.D.I. Report No. 96-06, Revision A, "Air Jet Impact Testing of Fibrous and Reflective Metallic Insulation," included in Volume 3 of GE Nuclear Energy Document No. NED0-32686-A, ORF A74-00004, "Utility Resolution Guide for ECCS Suction Strainer Blockage," dated October 1998 (7) WCAP-16727-P, Revision 0, "Evaluation of Jet Impingement and High Temperature Soak Tests of Lead Blankets for Use Inside Containment of Westinghouse Pressurized Water Reactors" (8) Letter from Mr. Carl J. Fricker (PSEG) to Document Control Desk (NRG), dated April 27, 2012, Final Supplemental Response to Generic Letter 2004-02, Attachment 1 5