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MONTHYEARML0223206562002-09-0909 September 2002 Meeting Summary with Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station Proposed Safety-Relief Valve Seismic Analysis Methodology Project stage: Meeting ML0228204672002-09-27027 September 2002 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0226601372002-10-0202 October 2002 Withholding from Public Disclosure, General Electric Proprietary Document, NEDC-33050P, Safety Analysis Report for Pilgrim Nuclear Power Station Thermal Power Optimization, Dated July 2002 Project stage: Other ML0230401802002-10-31031 October 2002 Request for Additional Information, Appendix K Measurement Uncertainty Recovery - 1.5% Power Uprate Request Project stage: RAI ML0231002832002-11-0101 November 2002 Request for Withholding Information from Public Disclosure Pilgrim Nuclear Power Station Project stage: Withholding Request ML0232201472002-11-0606 November 2002 Response to NRC Request for Additional Information, Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0231701742002-11-13013 November 2002 Request for Additional Information, Regarding Appendix K Measurement Uncertainty Recovery, Power Uprate Request Project stage: RAI ML0235400352002-12-20020 December 2002 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0235703862002-12-23023 December 2002 RAI, Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: RAI ML0302204502002-12-30030 December 2002 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0309000992003-04-0202 April 2003 Request for Additional Information Regarding Appendix K Measurement Uncertainty Recovery - 1.5% Power Uprate Request Project stage: RAI 2002-12-20
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Category:Memoranda
MONTHYEARML22321A1042022-12-0101 December 2022 Lessons Learned Recommendations Effectiveness Review ML21060B1152021-03-31031 March 2021 Memo to File: Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Pilgrim ISFSI ML19274B6662019-11-13013 November 2019 Summary of Public Meeting Near the Pilgrim Nuclear Power Station Regarding the Establishment and Operation of Community Advisory Boards ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML18158A1302018-06-0707 June 2018 Evaluation - Memorandum Regarding Licensee Event Report Safety Significance Review in Response to Findings Associated with Inspection Procedure 95003; Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML18157A0402018-06-0606 June 2018 Inspection Procedure 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML18158A1332018-06-0606 June 2018 Extent of Condition Review in Response to Findings Associated with Inspection 95003: Evaluation of NRC Assessment and Inspection Processes at Pilgrim Nuclear Power Station ML16153A2762016-06-20020 June 2016 Memo - Transmittal of the Final Pilgrim Nuclear Power Station Accident Sequence Analysis ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML14294A5712014-11-0404 November 2014 Memo - Transmittal of the Final Pilgrim Nuclear Power Station Accident Sequence Analysis ML14300A0962014-10-28028 October 2014 Staff Review of the Pilgrim Physical Security Plan (Revision 12) for the Independent Spent Fuel Storage Installation Security and Verification of ASM Incorporation (TAC L24940) ML14232A3012014-08-20020 August 2014 Memo s Wastler, Technical Assistance Request - Review of Physical Security Plan for the Pilgrim Nuclear Power Stations (TAC No. L24940) Docket Nos. 72-1044, 50-293 ML14086A2912014-04-22022 April 2014 Summary of Telephone Conference Regarding the Verbal Authorization of Relief Request PRR-25, Revision 1 ML13351A2732014-01-0909 January 2014 G20130846/LTR-13-0911 - James Brett, the New England Council Ltr. Chairman'S Recent Tour and the Council'S Support for the Pilgrim Nuclear Power Station - Response ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13267A2342013-08-30030 August 2013 G20130629 - Pilgrim Watch'S 2.206 Petition to Pilgrim'S Emergency Preparedness Plans (MF2656) ML13108A3282013-04-22022 April 2013 Notice of Forthcoming Meeting with Petitioners Requesting Action Against Entergy Nuclear Operations, Inc., Regarding Operations at FitzPatrick, Pilgrim, and Vermont Yankee Nuclear Power Stations (TAC Nos. MF1092, MF1093, and MF1094) ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML12137A0602012-05-29029 May 2012 Nuclear Regulatory Commission'S Analysis of Entergy Nuclear Operations, Inc. Decommissioning Funding Status Report for Indian Point Nuclear Generating Station, Units 1, 2 & 3; and Pilgrim Nuclear Power Station ML12090A2122012-03-30030 March 2012 Referring Jones River Watershed Association Petition to Intervene and Request to File New Contentions, or in Alternative, Jones River Watershed Association and Pilgrim Water Motion to Reopen the Pilgrim Nuclear Power Station, Docket No. 50- ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML11174A3252011-06-30030 June 2011 Memo Forwarding of Supplement 2 to NUREG-1891, SER Related to the Lr of Pilgrim Nuclear Power Station, Docket No. 50-293, to the Advisory Committee on Reactor Safeguards ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1109700342011-04-19019 April 2011 Summary of Tele Conf Call Held on 4/6/11, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1108206892011-04-19019 April 2011 February 24, 2011, Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1108202082011-04-11011 April 2011 Summary of Telephone Conference Call Held on March 23, 2011, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1100404192011-02-15015 February 2011 Summary of Telephone Conference Call Held on December 6, 2010, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operating, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application (Tac No. MC9669) ML1018900452010-07-0808 July 2010 Notification of Information in the Matter of Pilgrim Nuclear Power Station ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML1029505722009-01-23023 January 2009 Task Interface Agreement - Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim ML0836601742009-01-23023 January 2009 TIA - Task Interface Agreement - Evaluation at Pilgrim of Application of TS 4.0.3, 12/31/08 ML1029505762009-01-23023 January 2009 Task Interface Agreement Evaluation of Application of Technical Specification 4.0.3, Surveillance Requirement Applicability, at Pilgrim ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0718400342007-07-0606 July 2007 ACRS Review of the Pilgrim Nuclear Power Station License Renewal Application - Safety Evaluation Report ML0713100692007-06-0808 June 2007 Summary of Conference Call on May 10, 2007, with Entergy Nuclear Operations, Inc., Regarding the Pilgrim License Renewal Application ML0708104422007-03-15015 March 2007 Request for Additional Information on Time-Limited Aging Analyses for the Reactor Vessel and Internals, Pilgrim Nuclear Power Station, License Renewal Application ML0706402522007-03-0606 March 2007 ACRS Review of the Pilgrim Nuclear Plant Station Renewal Application - Safety Evaluation Report ML0705402052007-03-0101 March 2007 01/24/2007 Summary of Meeting with Pilgrim on the Draft Supplemental Environmental Impact Statement Regarding Pilgrim License Renewal Review ML0700501532007-01-0808 January 2007 01/24/2007 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Pilgrim Nuclear Power Station ML0634800242006-12-13013 December 2006 Drop-In Visit from Entergy (Pilgrim) ML0633406952006-11-28028 November 2006 Memorandum to Levin from Albert, Access to Security, Radiological, Vital and Protected Areas of the Pilgrim Nuclear Station ML0629104322006-11-17017 November 2006 Final Response to Task Interface Agreement 2006-01 Related to the Adequacy of Emergency Diesel Generator and Shutdown Transformer Load Testing at Pilgrim Nuclear Power Station ML0627605082006-11-0707 November 2006 Summary of Conference Call on September 25, 2006, with Entergy Nuclear Operations, Inc ML0628504072006-10-23023 October 2006 2006/10/23-Summary of Conference Call on October 10, 2006 with Entergy Nuclear Operations. Inc., to Clarify Information Sent to the NRC in Response to Requests for Additional Information Regarding the Pilgrim License Renewal Application ML0625801622006-09-15015 September 2006 Audit Trip Report Regarding Entergy Nuclear Operations Inc. License Renewal Application for Pilgrim Nuclear Power Station, Dated January 25, 2006 ML0617000552006-07-13013 July 2006 2006/07/13-Summary of Public Scoping Meetings Conducted Related to the Review of the Pilgrim Nuclear Power Station, License Renewal Application ML0618104242006-06-30030 June 2006 2006/06/30- 07/19/2006 Notice of Forthcoming Exit Meeting with Entergy Nuclear Operations, Inc., on License Renewal Scoping and Screening Methodology and the Aging Management Program / Aging Management Review Audits for Pilgrim Nuclear Powe 2022-12-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML21223A2422021-08-16016 August 2021 Enclosure - Pilgrim Nuclear Power Station - Request for Additional Information Regarding Pilgrim - License Amendment Request Independent Spent Fuel Storage Installation Only Emergency Plan ML21161A1072021-07-0909 July 2021 Request for Additional Information Regarding Pilgrim License Amendment Request ISFSI Only Emergency Plan ML21013A5232021-01-15015 January 2021 Request for Additional Information Regarding the Request to Change the Physical Security Plan - Alternative Measures ML20297A2382020-10-22022 October 2020 Fleet DQAP RAIs - Enclosure ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20142A2422020-05-26026 May 2020 Acceptance of Requested Licensing Action Physical Security Plan Revision and License Amendment Request to Incorporate Additional Independent Spent Fuel Storage Installation with Requests for Additional Information ML20280A1912020-04-17017 April 2020 Request for Additional Information- Clarifying Information for Pilgrim ISFSI Physical Security Amendment Application ML19207B3662019-07-26026 July 2019 NRR E-mail Capture - Pilgrim - RAI Direct and Indirect Transfer of Lic.; Conforming Lic. Amend.; Req. for Exemption 10 CFR 50.82(A)(8)(I)(A) for Holtec Decom. International, Llc ML19154A5242019-06-0303 June 2019 NRR E-mail Capture - RAI - Pilgrim Post-Decommissioning Technical Specifications (PDTS) License Amendment Request (LAR) ML19086A3492019-03-21021 March 2019 NRR E-mail Capture - Pilgrim Power Station - Request for Additional Information Application for Order Consenting to Direct and Indirect Transfers of Control of Licenses and Approving Conforming License Amendment (EPID: L-2018-LL0-0003) ML19036A6512019-02-0404 February 2019 NRR E-mail Capture - RAI - Pilgrim EP Exemption ML18320A1292018-11-16016 November 2018 NRR E-mail Capture - Request for Additional Information (RAI) - Pilgrim Post-Decommissioning Technical Specifications (PDTS) License Amendment Request (LAR) ML18323A1192018-11-15015 November 2018 CAL 5 Document Request #2 ML18317A2202018-11-11011 November 2018 NRR E-mail Capture - (External_Sender) Questions and Comments Regarding Pilgrim EP Exemption RAI, October 16, 2018 ML18317A2192018-11-0808 November 2018 NRR E-mail Capture - (External_Sender) RAI EP 11.06.18-Question ML18310A0212018-11-0606 November 2018 NRR E-mail Capture - RAI - Pilgrim EP Exemption ML18289A4072018-10-16016 October 2018 NRR E-mail Capture - RAIs - Pilgrim EP Exemption ML18285A8182018-10-12012 October 2018 NRR E-mail Capture - for Your Action: RAIs - Pilgrim - LAR - EP and EAL Scheme to Address Permanently Defueled Condition ML18124A1392018-05-0404 May 2018 NRR E-mail Capture - RAI - Pilgrim ERO Staffing License Amendment Request ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18005A5422018-01-0505 January 2018 NRR E-mail Capture - Second Round of RAI for DAEC Fifth Inservice Inspection Interval Program Plan, Relief Request RR-03 - EPID: L-2017-LLR-0110 ML16347A0042016-12-0909 December 2016 NRR E-mail Capture - Pilgrim: Request for Additional Information for Relief Requests on Volumetric Exam Requirements, PNPS-ISI-001, 002 and 003 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15211A6612015-07-30030 July 2015 Licensed Operator Positive Fitness-For-Duty-Test ML15051A0322015-02-25025 February 2015 Request for Additional Information Regarding the Safety Limit Minimum Critical Power Ratio License Amendment Request ML14342A0942014-12-17017 December 2014 Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations ML14042A0432014-02-18018 February 2014 Request for Additional Information Regarding Safety Limits to Resolve Pressure Regulator Fail-Open Transient License Amendment Request ML13333A9102013-12-0505 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool ins ML13323B4702013-11-25025 November 2013 Request for Additional Information Regarding Relief Request PRR-22 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report ML13182A4252013-07-0101 July 2013 Request for Additional Information E-mail from R.Guzman to W.Lobo PR-03 and PR-05 Fifth Ten-Year Inservice Testing (IST) Program ML13165A2762013-06-20020 June 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (NRC Order EA-12-051) ML12278A3862012-10-0404 October 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs ML1209604492012-04-0505 April 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Request for Additional Information, Revise Quality Assurance Program Manual and Staff Qualification Technical Specificat ML1208601472012-03-26026 March 2012 Request for Additional Information - Pilgrim Nuclear Power Station Revision to Condensate Storage Tank Low Level Trip Setpoint ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML1132502282011-11-22022 November 2011 Request for Additional Information, Relief Request No. PRR-21 ML1132202342011-11-21021 November 2011 Request for Additional Information 60-Day Response to Bulletin 2011-01, Mitigating Strategies, ML1114402342011-05-25025 May 2011 Request for Additional Information to Support the Review of 2011 Decommissioning Funding Status Report ML1108202082011-04-11011 April 2011 Summary of Telephone Conference Call Held on March 23, 2011, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1106101872011-03-0303 March 2011 Request for Additional Information to Support the Review of Pilgrim Nuclear Power Station Cyber Security Plan (Id: 2.10.034) ML1105403302011-02-15015 February 2011 Response to Request for Additional Information (Rai), Dated January 5, 2011 on the Cyber Security Plan ML1100900272011-01-10010 January 2011 Request for Additional Information Revision to TS for Setpoint and Setpoint Tolerance Increase for Safety Relief Valves and Spring Safety Valves, and Related Changes (ME3543) ML1034105062011-01-0707 January 2011 December 1, 2010, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application 2021-08-16
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Text
October 31, 2002 MEMORANDUM TO: James W. Andersen, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Travis L. Tate, Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
PILGRIM NUCLEAR POWER STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING APPENDIX K MEASUREMENT UNCERTAINTY RECOVERY - 1.5% POWER UPRATE REQUEST (TAC NO. MB5603)
Attached is a request for additional information transmitted by fax on September 20, 2002, to Mr. Bryan Ford of Entergy Nuclear Operations, Inc. (the licensee), regarding the Nuclear Regulatory Commission (NRC) staffs review of the licensees application dated July 5, 2002, as supplemented August 29, 2002. The questions were transmitted to facilitate a discussion prior to the NRC staffs issuance of a formal request. Following receipt of the attached questions, the licensee informed the staff that they will provide the requested information. This memorandum documents the requested information transmitted to the licensee.
Docket No. 50-293
Attachment:
As stated CONTACT: Travis Tate, NRR/DLPM 301-415-8474
October 31, 2002 MEMORANDUM TO: James W. Andersen, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Travis L. Tate, Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
PILGRIM NUCLEAR POWER STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING APPENDIX K MEASUREMENT UNCERTAINTY RECOVERY - 1.5% POWER UPRATE REQUEST (TAC NO. MB5603)
Attached is a request for additional information transmitted by fax on September 20, 2002, to Mr. Bryan Ford of Entergy Nuclear Operations, Inc. (the licensee), regarding the Nuclear Regulatory Commission (NRC) staffs review of the licensees application dated July 5, 2002, as supplemented August 29, 2002. The questions were transmitted to facilitate discussion prior to the NRC staffs issuance of a formal request. Following receipt of the attached questions, the licensee informed the staff that they will provide the requested information. This memorandum documents the requested information transmitted to the licensee.
Docket No. 50-293
Attachment:
As stated CONTACT: Travis Tate, NRR/DLPM 301-415-8474 DISTRIBUTION:
PUBLIC JAndersen TTate PDI-2 R/F LCox ADAMS Accession Number: ML023040180 OFFICE PDl-2/LA(A) PDI-2/PM PD1-2/SC(A)
NAME LCox TTate JAndersen DATE 10/25/02 10/29/02 10/29/02 OFFICIAL RECORD COPY
Request for Addition Information Pilgrim Nuclear Power Station License Amendment Request Appendix K Measurement Uncertainty Recovery - 1.5% Power Uprate Request
- 1. Since the effects of flow-accelerated corrosion (FAC) on degradation of carbon steel components are plant specific, the values of the parameters affecting FAC; i.e. velocity and temperature changes, must be included. In addition, the corresponding changes in components wear rates due to FAC before and after the power uprate must be provided.
A. Please provide the name and version of the predictive code used to project the need for maintenance/replacement of balance-of-plant (BOP) piping components prior to reaching minimum wall thickness requirements.
B. Please provide the predicted change of wear rates calculated by the revised predictive code for the components most susceptible to flow-accelerated corrosion. Specifically, provide a detailed table with this information as illustrated below in a sample table:
System Description % Change in Change in Predicted Predicted Wear Rate Wear Rate, mils / year Average Max Average Max FW Feedwater (FW) to FW Pump +0.46% +0.19% +0.008 + 0.02 to High Pressure FW Heater
- 2. Attachment 2 to the amendment request, page S-1, second paragraph from the top, states, This report follows the Nuclear Regulatory Commission (NRC)-approved format and content for Boiling Water Reactor (BWR) Thermal Power Optimization (TPO) licensing reports documented in NEDC-32938 P, Generic Guidelines and Evaluations for General electric Boiling Water Reactor Thermal Power Optimization, called TLTR.
The above referenced document, NEDC-32938, has not yet been approved by the staff.
Therefore, the above statement and all related references to NRC approval of this document should be removed from the submittal.
- 3. Please provide information relating to contingencies for an inoperable Crossflow UFM and effect of inoperable Crossflow UFM on thermal power measurement and plant operation. In this regard, also provide the following information:
A. A proposed allowed outage time (AOT) for the feedwater flow instrument, along with the technical basis for the time selected.
B. Proposed actions to reduce power level if the AOT is exceeded, including a discussion of the technical basis for the proposed reduction in the power level.
Attachment
- 4. For all instruments that affect the power calorimetric, provide information to specifically address the following aspects of the calibration and maintenance procedures. The amendment request provides the required information only for the Crossflow UFM.
Please provide it for the remaining instruments.
- c. Maintaining calibration
- d. Controlling software and hardware configuration
- e. Performing corrective actions
- f. Reporting deficiencies to the manufacturer
- g. Receiving and addressing manufacturer deficiency reports.
- 5. In reference to Section 2.5 of Attachment 2 to the amendment request, provide a summary describing the effect of the proposed power uprate on the structural integrity of the control rod drive mechanisms (CRDMs). Confirm that the existing design basis analysis for stress and fatigue cumulative usage of the CRDMs remains unchanged for the proposed 1.5 percent power uprate.
- 6. In Section 3.2.2 of Attachment 2 to the amendment request, you indicated that the effect of Thermal Power Optimization (TPO) was evaluated to ensure that the reactor vessel components continue to comply with the existing structural requirements of the ASME Boiler and Pressure Vessel Code. For the components under consideration, the 1965 Edition of the Code with addenda to and including Summer 1966, which is the construction code of record, was used as the governing Code. You also indicated that if a component underwent a design modification, the governing code for that component was the code used in the stress analysis of the modified component. Provide a summary of the components that were modified and the code editions/code cases (if applicable) other than the code of record that were used for the power uprate evaluation.
- 7. In Table 3-2 of Section 3.1, you indicated that the cumulative fatigue usage factor (CUF) for the feedwater nozzle is less than 0.8 for the current rated condition and less than 1.0 for the power uprate condition. Provide the actual calculated CUFs. Also, provide the allowable stress limits for reactor vessel components listed in Table 3-2. In reference to Section 3.3.2, provide a summary describing the effect of the proposed power uprate on the existing stress and fatigue analysis of the reactor internals. Also, provide comparison of calculated stresses and CUFs (similar to Table 3-2) for the limiting reactor internal components including allowable stress limits.
- 8. In reference to Section 3.5.3, you state that the original code of record for BOP piping and also for most safety related systems was ANSI B31.1. However, in your presentation on July 24, 2002, you indicated that design evaluation for SRV discharge line piping for the power uprate is in accordance with the requirements of ASME B&PV Code Section III 1977 Edition through Summer 1977 addenda. Provide the codes, code editions that were used for the RCPB piping and BOP piping for the power uprate.
- 9. In reference to Section 3.5.1, you indicated that the Response Spectrum Independent Support Motion (ISM) piping analysis methodology was applied for the SRVDL. At the July 24, 2002, meeting with the staff in Rockville, Md., you indicated the need to increase the SRV capacity as a result of the power uprate, and therefore, the current design margins of this piping system are reduced, due to the higher piping loads induced by the increased
SRV flow. The analysis for the SRVDL was therefore performed using the ADLPIPE computer code, the ISM methodology and Regulatory Guide (RG) 1.61 damping values.
The ISM analysis used the square root of sum of squares (SRSS) approach for combining Group responses. This approach does not correspond to the staff position as stated in NUREG 1061, Volume 4. Likewise, the use of damping values in the analysis is not in accordance with the licensing basis for Pilgrim.
- h. Provide the user manual, including the theoretical basis and bench-marking verification problems, for the ISM option in the ADLPIPE computer code.
- i. Provide the justification for using the RG 1.61 damping values instead of the licensing basis damping values, as shown in the FSAR, for application with the ISM approach.
- j. Provide the maximum stresses and CUFs for the SRVDL at critical locations, subjected to the following loading conditions:
(1) Current operating conditions.
(2) Power uprate operating conditions, using the uniform response spectrum piping analysis approach, and licensing basis damping values.
(3) Power uprate operating conditions, using the ISM piping analysis approach based on the Absolute Sum of Group responses, and licensing basis damping values.
(4) Power uprate operating conditions, using the ISM piping analysis approach based on the SRSS combination of Group responses, and licensing basis damping values.
(5) Power uprate operating conditions, using the ISM piping analysis approach based on Absolute Sum of Group responses, and RG 1.61 damping values.
- c. Provide the licensing basis stress allowables.