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| | issue date = 07/20/2010 | | | issue date = 07/20/2010 |
| | title = RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Reactor Vessel Internals | | | title = RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Reactor Vessel Internals |
| | author name = Ferrer N B | | | author name = Ferrer N |
| | author affiliation = NRC/NRR/DLR/RPB2 | | | author affiliation = NRC/NRR/DLR/RPB2 |
| | addressee name = Conway J | | | addressee name = Conway J |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| See Next Page ADAMS Accession No' ML 101880255.. IOFFICE PM:RPB2:DLR LA:DLR BC:RPB2:DLR PM:RPB2:DLR NAME NFerrer IKing DWrona NFerrer DATE 07116110 07116110 07120110 07/20/10 OFFICIAL RECORD COpy Letter to John Conway from Nathaniel Ferrer dated July 20, 2010 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC Nos. ME2896 AND ME2897) -REACTOR VESSEL INTERNALS DISTRIBUTION: | | See Next Page ADAMS Accession No' ML101880255.. IOFFICE PM:RPB2:DLR LA:DLR BC:RPB2:DLR PM:RPB2:DLR NAME NFerrer IKing DWrona NFerrer DATE 07116110 07116110 07120110 07/20/10 OFFICIAL RECORD COpy Letter to John Conway from Nathaniel Ferrer dated July 20, 2010 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC Nos. ME2896 AND ME2897) -REACTOR VESSEL INTERNALS DISTRIBUTION: |
| HARDCOPY: | | HARDCOPY: |
| DLRRF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsOgcMailRoom Resource N. Ferrer K. Green A. Stuyvenberg D. Wrona A. Wang M. Peck, RIV T. Brown, RI G. Miller, RIV N. O'Keefe, RIV I. Couret, OPA V. Dricks, OPA W. Maier, RIV J. Weil, OCA E. Williamson, OGC S. Uttal, OGC R. Rihm, EDO}} | | DLRRF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsOgcMailRoom Resource N. Ferrer K. Green A. Stuyvenberg D. Wrona A. Wang M. Peck, RIV T. Brown, RI G. Miller, RIV N. O'Keefe, RIV I. Couret, OPA V. Dricks, OPA W. Maier, RIV J. Weil, OCA E. Williamson, OGC S. Uttal, OGC R. Rihm, EDO}} |
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MONTHYEARML1007101132010-03-10010 March 2010 Task Order No. 002 Under Delivery Order No. NRC-03-10-070 Project stage: Acceptance Review ML1007101142010-03-10010 March 2010 Task Order No. 002 Under Delivery Order No. NRC-03-10-070 Project stage: Acceptance Review ML1013201872010-05-18018 May 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application Project stage: RAI ML1013806142010-05-24024 May 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening Methodology Project stage: RAI ML1015404192010-06-14014 June 2010 Letter Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1016201872010-06-21021 June 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1016901302010-06-29029 June 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1017601042010-07-0606 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application Project stage: RAI ML1017602432010-07-14014 July 2010 RAI Related to the Review of the DCPP LRA - Aging Management Programs Project stage: RAI ML1018301312010-07-15015 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening and Aging Management Review Project stage: RAI ML1018908322010-07-16016 July 2010 Audit Report Regarding the Diablo Canyon Nuclear Power Plant License Renewal Application Scoping and Screening Methodology Project stage: Other ML1018700882010-07-19019 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1019004702010-07-20020 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 & 2, LRA (Tac Nos. ME2896, and ME2897) - Scoping and Screening Project stage: RAI ML1018802552010-07-20020 July 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Reactor Vessel Internals Project stage: RAI ML1018301442010-07-20020 July 2010 RAI Related to the Review of the DCPP LRA - Aging Management Programs and Aging Management Review Project stage: RAI ML1018900212010-07-22022 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review and Time Limited Aging Analysis Project stage: RAI ML1018807352010-07-22022 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review and Aging Management Programs Project stage: RAI ML1020004882010-08-0303 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Review and Aging Management Programs Project stage: RAI ML1020402512010-08-0909 August 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening and Aging Management Review Project stage: RAI ML1016903212010-08-11011 August 2010 Audit Report for Plant Aging Management Programs for DCPP, Units 1 and 2 Project stage: Other ML1019606442010-08-13013 August 2010 Safety Project Manager Change for the License Renewal Project for Diablo Canyon Nuclear Power Plant (TAC ME2896 and ME2897) Project stage: Other ML1021705242010-08-25025 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Metal Fatigue Project stage: RAI ML1020107002010-08-26026 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analyses and Aging Management Programs Project stage: RAI ML1022402772010-08-26026 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1022905422010-08-30030 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Review and Time Limited Aging Analyses Project stage: RAI ML1023607492010-09-0101 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1024300272010-09-13013 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. Me 2869 and ME2897) - Scoping and Screening Project stage: RAI ML1025202782010-09-17017 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening Project stage: RAI ML1024600502010-09-17017 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 & ME2897) Aging Management Programs Project stage: RAI ML1025102972010-09-23023 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analyses Project stage: RAI ML1024601512010-09-28028 September 2010 Summary of Telephone Conference Call Held on 9/2/10 Between Us NRC and Pacific Gas and Electric Company Concerning the Response to RAIs Related to the Diablo Canyon Nuclear Power Plant Units 1 and 2 LRA Project stage: RAI ML1025202642010-09-29029 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review Project stage: RAI ML1026605412010-09-30030 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Fire Protection Project stage: RAI ML1029806892010-11-0202 November 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analysis Project stage: RAI ML1029306302010-11-0303 November 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Programs Project stage: RAI ML1034810132010-12-20020 December 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Program and Time Limited Aging Analysis Project stage: RAI ML1034104342010-12-20020 December 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC ME2896 and ME2897) - Time Limited Aging Analysis Project stage: RAI ML1034904172011-01-10010 January 2011 12/1/10 Summary of Telephone Conference Call Held Btw the USNRC and Pacific Gas and Electric Company Concerning Draft Request for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: Draft RAI ML1035603212011-01-10010 January 2011 12/8/10 Summary of Telephone Conference Call Held Btw the USNRC and Pacific Gas and Electric Company Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Ap Project stage: RAI ML1034306232011-01-11011 January 2011 Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Request for Additional Information Related Tot the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME2896 & ME2897) Project stage: RAI ML1035506802011-01-11011 January 2011 12/9/10 Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 & M Project stage: RAI ML1101005882011-01-25025 January 2011 Summary of Telephone Conference Call Held on December 16, 2010, Between the NRC and Pacific Gas and Electric Company Concerning RAI Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML1101102612011-01-25025 January 2011 Summary of Telephone Conference Call Held on 12/22/2010, Between the NRC and Pacific Gas and Electric Company Concerning Requests for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME28 Project stage: RAI ML1101204182011-02-0707 February 2011 Summary of Telephone Conference Call Held with NRC and PG&E Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME2896 & ME2897) Project stage: RAI ML1101400082011-02-0707 February 2011 01/04/11 Summary of Telephone Conference Call Held Between the NRC and PG&E Company Concerning Requests for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 Project stage: RAI ML1104105282011-02-14014 February 2011 Summary of Telephone Conference Call Held on 1/19/11 Between the USNRC and PG&E Concerning Open Items Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, Safety Evaluation Report Project stage: Approval ML1104607182011-02-18018 February 2011 January 25, 2011, Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Open Items Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, SER (TAC Nos. ME2896 & 2897) Project stage: Other ML1105907492011-03-17017 March 2011 Summary of Telephone Conference Calls Held on February 2 and 4, 2011, Btw the USNRC and Pacific Gas and Electric Company Concerning RAIs Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML1108404592011-04-11011 April 2011 Summary of Telephone Conference Calls Held on 2/28/11 and 3/17/11 Btw the USNRC and Pacific Gas and Electric Company Concerning RAIs Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML15217A4812015-09-24024 September 2015 Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application Set-38 TAC Nos. ME2896 and ME2897 Project stage: RAI 2010-08-26
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Category:Letter
MONTHYEARDCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment IR 05000275/20243012024-08-26026 August 2024 NRC Examination Report 05000275/2024301; 05000323/2024301 IR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) DCL-24-075, Response to Request for Additional Information for License Amendment Request 23-02, Application to Adopt 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power React2024-08-0808 August 2024 Response to Request for Additional Information for License Amendment Request 23-02, Application to Adopt 10 CFR 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power React IR 05000275/20240022024-08-0606 August 2024 Integrated Inspection Report 05000275/2024002 and 05000323/2024002 DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring ML24187A1352024-07-16016 July 2024 Letter to Paula Gerfen - Diablo Canyon Units 1 and 2 - Summary of June 2024 Audit Related to the License Renewal Application Severe Accident Mitigation Alternatives Review IR 05000275/20240142024-07-11011 July 2024 Age-Related Degradation Inspection Report 05000275/2024014 and 05000323/2024014 IR 05000275/20244012024-07-0808 July 2024 Security Baseline Inspection Report 05000275/2024401 and 05000323/2024401 (Full Report) IR 05000323/20240112024-07-0303 July 2024 License Renewal Phase Report 05000323/2024011 DCL-2024-527, Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant2024-07-0101 July 2024 Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL2024-06-27027 June 2024 Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL ML24155A2182024-06-18018 June 2024 OEDO-23-00350-NRR - (LTR-23-0228-1) - Closure Letter - 10 CFR 2.206 Petition from Mothers for Peace and Friends of the Earth Regarding Diablo Canyon ML24129A1762024-06-14014 June 2024 National Historic Preservation Act Section 106 Consultation – Results of Identification and Evaluation (Docket Number: 72-026) ML24200A2052024-06-0707 June 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project for Diablo Canyon License Renewal ML24099A2192024-05-29029 May 2024 Plants, Units 1 and 2 Issuance of Amendment Nos. 245 and 247 Revision to TSs to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24117A0132024-05-20020 May 2024 Letter to Paula Gerfen-Diablo Canyon Units 1 and 2-Regulatory Audit Regarding Severe Accident Mitigation Alternatives for the License Renewal Application DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report DCL-24-051, One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage ML24127A2042024-05-0202 May 2024 02May2024 Ltr - California Coastal Commission to Pg&E, Coastal Development Permit Needed for Pg&E’S Proposed Relicensing of Diablo Canyon Nuclear Power Plant DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 L-24-004, Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007)2024-04-30030 April 2024 Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007) DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 IR 05000275/20240012024-04-23023 April 2024 Integrated Inspection Report 05000275/2024001 and 05000323/2024001 ML24114A2032024-04-22022 April 2024 Request for Information for EP Program and Performance Indicator Verification Inspection (Wolf Creek Nuclear Generating Station) Inspection Report 05000482/2024003 ML24106A2892024-04-18018 April 2024 Letter to Paula Gerfen - Diablo Canyon Units 1 and 2 - Summary of March 2024 Audit Regarding the Environmental Review of the License Renewal Application ML24106A2882024-04-18018 April 2024 License Renewal Application Environmental Review RCIs and RAIs DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24108A1122024-04-15015 April 2024 License Amendment Request 24-02 Request for Approval of DCPP Early Warning System to Meet 10 CFR 73.55(i)(2) and 10 CFR 73.55(e)(9)(vi)(A) DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant ML24082A2592024-03-25025 March 2024 Notice of Enforcement Discretion for Diablo Canyon Power Plant, Unit 2 (EPID L-2024-LLD-0002) - March 25, 2024 ML24081A0462024-03-22022 March 2024 Audit Summary in Support of the License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability2024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability ML24081A4052024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability ML24065A1312024-03-20020 March 2024 ISFSI Renewal RAI Transmittal Letter IR 05000275/20244032024-03-12012 March 2024 Cyber Security Inspection Report 05000275/2024403 and 05000323/2024403 (Cover Letter) ML24065A3662024-03-0404 March 2024 Notification of Site Inspection for License Renewal and Request for Information Inspection (05000323/2024011) ML24071A1742024-03-0404 March 2024 Email - (External_Sender) Shutdown Petition to NRC Commissioners IR 05000275/20230062024-02-28028 February 2024 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2023006 and 05000323/2023006) DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24250A0532024-09-0606 September 2024 LRA - Requests for Additional Information - Set 1 ML24184C0422024-07-0202 July 2024 NRR E-mail Capture - Request for Additional Information Diablo Canyon 50.69 risk-informed Categorization ML24065A1312024-03-20020 March 2024 ISFSI Renewal RAI Transmittal Letter ML24065A1332024-03-20020 March 2024 Enclosure- Diablo Canyon ISFSI Renewal Request for Additional Information ML24024A2072024-01-24024 January 2024 Inservice Inspection Request for Information IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) ML23249A2782023-09-0606 September 2023 Inservice Inspection Request for Information ML23159A2372023-07-25025 July 2023 ISFSI Renewal RAI Transmittal Letter Enclosure ML23159A2382023-07-25025 July 2023 Request for Additional Information for the Technical Review of the Application for Renewal of the Diablo Canyon Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2022-RNW-0007) ML23096A1792023-04-0606 April 2023 NRR E-mail Capture - Request for Additional Information Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application ML23047A0062023-02-21021 February 2023 Request for Additional Information Alternative Security Measures for Early Warning System (EPID: L-2022-LLA-0029) (Public Version) ML23041A1862023-02-17017 February 2023 Request for Information Regarding Diablo Canyon Power Plant, Units 1 and 2 - December 8, 2022, Public Meeting ML22258A1112022-09-14014 September 2022 2022 Diablo Canyon PIR Request for Information ML22200A2572022-07-19019 July 2022 Notification of In-service Inspection (Inspection Report 05000323/2022004) and Request for Information ML22187A2652022-07-0606 July 2022 NRR E-mail Capture - Request for Additional Information: Diablo Canyon Exemption Request for Part 73 force-on-force Training Due to COVID-19 ML22152A1502022-06-21021 June 2022 Request for Additional Information Regarding License Amendment Request for Technical Specifications and Revised License Conditions for the Permanently Defueled Condition ML22122A1412022-05-0505 May 2022 .02 Doc Request ML22068A2312022-03-17017 March 2022 Notification of NRC Design Bases Assurance Inspection (Team) 05000275/2022011 and 05000323/2022011 and Initial Request for Information ML22061A2192022-03-0202 March 2022 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Changes to Emergency Plan for post-shutdown and Permanently Defueled Condition ML21363A1692021-12-29029 December 2021 Inservice Inspection Request for Information ML22019A0412021-12-29029 December 2021 RFI ML21215A3432021-08-0303 August 2021 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance ML21130A3642021-06-21021 June 2021 DC 2021401 Information Request ML21104A3642021-04-14014 April 2021 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition ML21062A0642021-03-0202 March 2021 NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000) ML20329A0692020-11-23023 November 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend force-on-force Exercise ML20323A4532020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend Firearms Requalification ML20301A2212020-10-27027 October 2020 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000275/2021010 and 05000323/2021010) and Request for Information ML20261H4232020-09-17017 September 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report ML20231A2372020-08-17017 August 2020 NRR E-mail Capture - Diablo Canyon Additional Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G EPID: L-2020-LLA-017 ML20230A0732020-08-14014 August 2020 NRR E-mail Capture - Diablo Canyon Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G ML20280A5432020-06-0303 June 2020 DC 2020 PIR Request for Information ML20041E6012020-02-10010 February 2020 NRR E-mail Capture - Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Request for Additional Information for Post -Shutdown Decommissioning Activities Report (PSDAR) ML19262G7482019-08-0909 August 2019 Request for Information ML19149A6012019-05-28028 May 2019 NRR E-mail Capture - Request for Additional Information (Supplemental) - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation ML19123A2162019-05-0202 May 2019 NRR E-mail Capture - Diablo Canyon Nuclear Power Plant -Request for Exemption from Operator Written Examination and Operating Test - Request for Additional Information ML19084A2572019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation ML19043A9452019-02-20020 February 2019 Notification of Inspection (NRC Inspection Report 05000275/2019002, 05000323/2019002 and Request for Information ML17306A9382017-11-0202 November 2017 NRR E-mail Capture - Request for Additional Information - Request for Approval for Application of Full Weld Overlay REP-RHR-SWOL, Diablo Canyon Power Plant, Units 1 and 2 ML17152A3192017-06-0101 June 2017 NRR E-mail Capture - Request for Additional Information (RAI)- Relief Requests NDE-SLH U2, NDE-LSL U2, NDE-LHC U2, NDE-LHM U2, and NDE-ONV U2 (CAC Nos. MF9386 Through MF9390) ML17102B6072017-04-12012 April 2017 NRR E-mail Capture - Request for Additional Information (RAI) - Revised Emergency Action Level Schemes Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16347A0032016-12-0909 December 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Diablo Canyon Power Plant License Amendment Request for Adoption of NEI 94-01 ML16326A3562016-11-21021 November 2016 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Adopt Nuclear Energy Institute (NEI) 94-01, Revision 2-A for Diablo Canyon Power Plant, Units 1 and 2 - CAC Nos. MF7731 and MF7732 ML16048A2322016-02-17017 February 2016 NRR E-mail Capture - Diablo Canyon 1 and 2 - Met Data Second Round of Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67 (TAC Nos. MF6399 and MF640 ML16011A3652016-02-0202 February 2016 Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application - Set 39 (TAC Nos. ME2896 and ME2897) ML16011A3172016-01-11011 January 2016 NRR E-mail Capture - Diablo Canyon 1 and 2 - Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67 ML15358A0022015-12-23023 December 2015 Request for Additional Information Email (Follow-up Pra), Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML15357A3822015-12-23023 December 2015 Request for Additional Information, Round 4 - Amendment Request to Replace Digital Process Protection System for Reactor Protection System and Engineered Safety Features Actuation System Functions ML15295A3732015-11-0505 November 2015 Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review ML15287A1652015-10-23023 October 2015 Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review - SAMA 2024-09-06
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 20, 2010 John Conway Senior Vice President Generation and Chief Nuclear Officer Pacific Gas and Electric Company 77 Beale Street, MC B32 San Francisco, CA 94105 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. ME2896 AND ME2897) -REACTOR VESSEL INTERNALS
Dear Mr. Conway:
By letter dated November 23, 2009, Pacific Gas &Electric Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses for Diablo Canyon Nuclear Power Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. The request for additional information was discussed with Mr. Terry Grebel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathaniel.ferrer@nrc.gov.
Nathaniel Ferrer, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosure:
As stated cc w/encl: Distribution via Listserv Diablo Canyon Nuclear Power Plant, Units 1 and License Renewal Request for Additional Information Set Reactor Vessel RAI In license renewal application (LRA) Table 3.1.2-1, for component type "RV (Reactor Vessel) Nozzles (Inlet/Outlet Nozzles)," material "Carbon Steel with Stainless Steel Cladding," environment "reactor coolant (int)," and aging effect "loss of fracture toughness," there are two line items. For the first line item, aligned with GALL Report item IV.A2.16, the aging management program (AMP) is "Time-Limited Aging Analysis (TLAA) evaluated for the period of extended operation." For the second line item, aligned with GALL Report item IV.A2.17, the AMP is "Reactor Vessel Surveillance (82.1.15)." The first line item aligns with LRA Table 3.1.1, item 3.1.1.17, which states, in the AMP column: TLAA, evaluated in accordance with Appendix G of 10 CFR Part 50 and RG 1.99. The applicant may choose to demonstrate that the materials of the nozzles are not controlling for the TLAA evaluations.
The second line item aligns with LRA Table 3.1.1, item 3.1.1.18, which states, under the AMP column, "Reactor Vessel Surveillance Program (82.1.15)." Further evaluation is recommended for both Table 3.1.1 items. However, the neutron embrittlement TLAA evaluations, described in LRA Section 4.2, do not discuss how the nozzles were demonstrated not to be controlling, nor are any nozzle materials included among the extended beltline materials that are included in the pressurized thermal shock (PTS) TLAA evaluation (LRA Section 4.2.2) and the Upper Shelf Energy (USE) evaluation (LRA Section 4.2.3). Further, the RV Surveillance Program description does not address any nozzle materials. Describe how the Diablo Canyon Power Plant (DCPP) RV nozzle materials were demonstrated to not be controlling with respect to the neutron embrittlement related TLAAs. This description should include a summary of any fluence evaluations and/or neutron embrittlement projections using the nozzle fluence and chemistry to project the PTS reference temperature (RT PTS) and USE of the nozzle materials. Indicate any changes this may have to the LRA. Describe how the RV Surveillance Program manage loss of fracture toughness of the RV nozzles if specimens of the nozzle materials are not included in the surveillance program.
RAI3.1.2.2.7-1 LRA Section 3.1.2.2.7 and LRA Table 3.1.2 indicate that material of the RV flange O-ring leak monitoring line is nickel alloy. However, in most pressurized-water reactors (PWRs) only the vessel penetration is nickel alloy while the adjoining piping is stainless steel. Clarify whether the adjoining piping of the RV flange O-ring leak monitoring line is stainless steel. If so, clarify whether this piping is included within the scope of license renewal such as under another Table 2 line item such as Class 1 Piping <= 4in, GALL Report item IV.C2-1 in LRA Table 3.1.2-2. RAI3.1.2.2.7-2 In LRA Section 3.1.2.2.7.1, the applicant indicated that for managing aging due to stress corrosion cracking of stainless steel high pressure conduits (flux thimble guide-tubes-to seal table) exposed to reactor coolant, the applicant's Water Chemistry (B2.1.2) AMP will be augmented by their American Society of Mechanical Engineers (ASME) Section Xllnservice Inspection, Subsections IWB, IWC, and IWD (B2.1.1) AMP. For stainless steel flux thimble tubes exposed to reactor coolant, cracking due to stress corrosion cracking (SCC) is managed by the DCPP Water Chemistry (B2.1.2) AMP. The staff notes that in LRA Table 3.1.2, the flux thimble tubes are included as a subcomponent of the RV Bottom Mounted Instrument Guide Tube, which aligns to GALL Report item IV.A2-1(RP-13) for the aging effect cracking.
The staff reviewed LRA Section 3.1.2.2.7.1 against the criteria in NUREG-1800, 'The Standard Review Plan for Review of License Renewal Applications (SRP-LR)," Section 3.1.2.2.7.1, which states cracking due to SCC could occur in the PWR stainless steel reactor vessel flange leak detection lines and bottom-mounted instrument guide tubes. The GALL Report recommends further evaluation to ensure that these aging effects are adequately managed. The SRP-LR further states that the GALL Report recommends that a plant-specific AMP be evaluated because existing programs may not be capable of mitigating or detecting cracking due to SCC. Acceptance criteria are described in Branch Technical Position RLSB-1 (Appendix A.1 of the SPR-LR). Branch Technical Position RLS8-1 states that a plant-specific AMP should include a "detection of aging effects" program element. The DCPP Water Chemistry Program provides mitigation of cracking through control of impurities, but does not provide for detection of aging effects. The ASME Section XI Inservice Inspection Program, Subsections IWB, IWC, and IWD AMP, provides for inspections of components.
The standard examination requirements for flux thimble tubes under the ASME Section XI Inservice Inspection Program, Subsections IWB, IWC, and IWD AMP, is a VT-2 visual inspection per ASME Code Section XI, Table IWB-2500-1, Examination Category B-P, which would not generally be capable of detecting cracking unless a leak is already present, producing visible water and/or boric acid. The program description in LRA Section B.2.1.1 does not describe any augmented inspections for the flux thimble tubes which would be capable of early detection of cracking.
Identify any specific examinations included in the ASME Section XI Inservice Inspection Program, Subsections IWB, IWC, and IWD AMP, which would be capable of detecting cracking in the RV Bottom Mounted Instrument Guide Tubes (High Pressure Conduits, Seals) before a throughwall crack and leakage occurs. If the ASME Section XI Inservice Inspection Program, Subsections IWB, IWC, and IWD AMP does not provide for detection of cracking prior to a leak, provide a plant-specific AMP or combination of existing AMPs that include a "detection of aging effect" program element for managing the aging effect of cracking due to SCC in the RV Bottom Mounted Instrument Guide Tubes (High Pressure Conduits, Seals); and Describe what examination techniques will be used to detect (or confirm the absence of) the aging effect of cracking in the RV Bottom Mounted Instrument Guide Tubes (High Pressure Conduits, Seals), either as part of the ASME Section Xllnservice Inspection Program, Subsections IWB, IWC, and IWD, or an additional plant-specific program. RAI4.2.2-1 As part of its independent evaluation of the RT pTS values, the staff checked the copper, nickel, and initial (unirradiated) reference temperature (RT NOT) values against the corresponding values from the Reactor Vessel Integrity Database (RVID) for each beltline material.
The applicant provided lower copper values for DCPP, Unit 1 intermediate shell plates B4106-1 (Heat No. C2884-1), B4106-2 (Heat No. C2854-2), and 84106-3 (Heat No. C2793-1), and lower nickel values for plates 84106-3 and B4107-3 (Heat No. C3131-1), than the corresponding copper and nickel values in RVID. The copper and nickel values provided in the LRA for plate B4106-3 match the best estimate values provided in the most recent surveillance capsule report for DCPP, Unit 1, and are therefore acceptable.
Provide data for the copper and nickel content for DCPP, Unit 1 Intermediate Shell Plates B4106-1, B4106-2, and B4107-3 as given in LRA Tables 4.2-4 and 4.2-6. RAI4.2.2-2 When using 10 CFR 50.61 to calculate RT pTS , the margin term is defined as Margin =2..J(0/ + ol) 10 CFR 50.61, defines au as the standard deviation for the initial RT NOT. If a measured value of initial RT NOT for the material in question is available, 01 is to be estimated from the precision of the test method. If not, and generic mean values for that class of material are used, 01 is the standard deviation obtained from the set of data used to establish the mean.
The staff performed preliminary confirmatory calculations of RT PTS using the OtJ. term as defined in 10 CFR 50.61. To obtain the margin term for some of the materials listed in LRA Tables 4 and 4.2-5, it appears that a value of 17°F was used for ai, while a 01 value of OaF was used for other materials.
In some cases, the values used for a, appear to be inconsistent with values in RVID. For the materials listed in LRA Tables 4.2-4 and 4.2-5: Identify whether the initial (unirradiated)
RT NOT(u) value cited for the material is based on plant-specific data or on a generic value. For those materials using a generic initial RT NOT(u) value, describe the method of determination and basis for the initial (unirradiated)
RT NOT(u) values for the materials listed in LRA Tables 4.2-4 and 4.2-5, and provide a reference for each value. For those materials in LRA Tables 4.2-4 and 4.2-5 using a generic value for initial RT NOT, provide the a, value used and the basis for the 01 value. Confirm that the appropriate value of a, (O°F vs. 1rF) has been used for all materials listed in LRA Table 4.2-4 and 4.2-5. RAI4.2.2-3 For DCPP, Unit 2, the applicant stated that in accordance with Regulatory Guide 1.99 Revision 2, the Charpy V-Notch Upper Shelf Energy (C v USE) data from Unit 2 Surveillance Capsule V were deemed credible for intermediate shell plate 85454-1 (Heat No. C5161-1).
The applicant stated that the C v USE values were projected to 54 effective full power years (EFPy) of operation using Regulatory Guide 1.99 Position 1.2. If credible surveillance data are available, Regulatory Guide 1.99 Revision 2 Position 2.2 recommends that the decrease in upper-shelf energy may be obtained by plotting the reduced plant surveillance data on Figure 2 of the regulatory guide and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data, and that this line should be used in preference to the existing graph. The staff notes that the most recent surveillance capsule report for DCPP, Unit 2 (Reference 1), indicated that the surveillance data for Plate 85454-1 were credible for both the NOT and USE, and that the surveillance data were used in the end of license extension (EOLE) projection of RT PTS for this material.
The EOLE C v USE values for the Unit 2 beltline and extended beltline materials are provided in LRA Table 4.2-7. Although surveillance data for intermediate shell plate 85454-1 are available, it was not clear whether the surveillance C v USE data were used in the projection for that plate. Clarify if surveillance program data used in the projection of USE for DCPP Unit 2 intermediate shell plate 85454-1 (Heat No. C5161-1).
If surveillance data was not used, provide justification.
RAI 82.1.15-1 In its description of the Reactor Vessel Materials Surveillance Program in LRA Section B2.1.15, the applicant stated that for DCPP Unit 1, the last capsule is expected to be withdrawn during the current operating term after it has accumulated a fluence equivalent to 60 years of operation.
The applicant further stated that the remaining five standby capsules have low lead factors, will remain inside the vessel throughout the vessel lifetime, and will be available for future testing. The latest surveillance capsule withdrawal schedule was submitted by the applicant by letter dated March 12, 2008 (Ref. 4 of the LRA), and approved by a staff safety evaluation dated September 24, 2008 (Ref. 5 of the LRA). This schedule proposed that capsule B, with a lead factor of 3.46, will be withdrawn at 21.9 EFPY. The fluence will be equivalent to 75.8 EFPY which is between one and two times the vessel EOLE fluence (54 EFPY fluence).
This meets the ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," criterion.
The proposed schedule shows four capsules to be left in the vessel, all with lead factors around 1.3. Clarify whether four or five surveillance capsules will remain installed in the vessel during the period of extended operation.
July 20, 2010 John Conway Senior Vice President Generation and Chief Nuclear Officer Pacific Gas and Electric Company 77 Beale Street, MC B32 San Francisco, CA 94105 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE REN EWAL APPLICATION (TAC NOS. IVIE2896 AN D ME2897) -REACTOR VESSEL INTERNALS
Dear Mr. Conway:
By letter dated November 23, 2009, Pacific Gas & Electric Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses for Diablo Canyon Nuclear Power Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. The request for additional information was discussed with Mr. Terry Grebel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1045 or bye-mail at nathaniel.ferrer@nrc.gov. Sincerely, IRA! Nathaniel Ferrer, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
See Next Page ADAMS Accession No' ML101880255.. IOFFICE PM:RPB2:DLR LA:DLR BC:RPB2:DLR PM:RPB2:DLR NAME NFerrer IKing DWrona NFerrer DATE 07116110 07116110 07120110 07/20/10 OFFICIAL RECORD COpy Letter to John Conway from Nathaniel Ferrer dated July 20, 2010 REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC Nos. ME2896 AND ME2897) -REACTOR VESSEL INTERNALS DISTRIBUTION:
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