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MONTHYEARML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML16285A3202016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 13-04 ML16159A4002016-06-16016 June 2016 Iepra Ror for Point Beach SE Section 3.4 ML16159A4022016-06-16016 June 2016 Fpra Ror for Point Beach SE Section 3.4 ML15261A7492015-09-14014 September 2015 NRC Supplement to NRC Letter - Notification of NRC Inspection and Request for Information Dated May 1, 2015 - NextEra Energy Point Beach Nuclear Plant (Msh) ML16072A0362015-06-0303 June 2015 Receipt of Cd Containing Revised I/O Files from NextEra Point Beach Nuclear Plant Flood Hazard Re-Evaluation Report ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14314A5122014-11-13013 November 2014 Enclosure 2 - Frequently Asked Questions (Faqs) Discussed During the October 22 2014 Reactor Oversight Process Public Meeting ML14147A0112014-06-20020 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14149A1532014-05-0101 May 2014 FOIA/PA-2014-0074 - Resp 4 - Partial. Group F (Records Already Publicly Available) ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1017301232010-06-0909 June 2010 Green Ticket Tritium Releases ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726203022007-09-28028 September 2007 Amendment to Indemnity Agreement No. B-41, Amendment No. 14 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0635404332006-12-20020 December 2006 Enclosure 2 - Consent and Hearing Waiver Form - the Nuclear Management Company, LLC ML0634705992006-12-14014 December 2006 Plant Service List ML0627903812006-09-29029 September 2006 Exhibit 26 to Case No. 2-2002-004, Interview Report ML0626801502006-09-22022 September 2006 Escort Ratio for Visitors ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0626504142005-11-0303 November 2005 RIII-2005-A-0062 Closure ML0626802782005-08-29029 August 2005 3rd ARB Action Plan RIII-05-A-0062 (Point Beach) ML0626802752005-08-22022 August 2005 2nd ARB Action Plan, RIII-05-A-0062 (Point Beach) ML0626504072005-07-19019 July 2005 Action Request - Corrective Action Program (CAP) ML0626802642005-07-18018 July 2005 Initial ARB Action Plan RIII-05-A-0062 (Point Beach) ML0518603982005-07-15015 July 2005 NRC Actions Under the Reactor Oversight Process for the Point Beach Nuclear Plant, Units 1 and 2 ML0518903972005-07-0101 July 2005 Log Entries Report ML0518903962005-07-0101 July 2005 U1R28 Outage Risk Plan Ppg Outage Management ML0518903952005-07-0101 July 2005 U1R28 Add/Delete Log ML0626504032005-06-22022 June 2005 Action Request - Corrective Action Program (CAP) (CAP065250) ML0626503992005-06-10010 June 2005 Action Request - Corrective Action Program (CAP) (CAP065041) ML0626504012005-06-10010 June 2005 Action Request - Corrective Action Program (CAP) (CAP065035) ML0515202282005-05-24024 May 2005 EP FFD Questions Not Asked ML0514700842005-05-24024 May 2005 COLR 28 Replaced with COLR 29 Prior to Vessel Removal. Attach: 04/14/2004 Condition Evaluation 013784. Attach: 04/12/2004 CAP 055612. Attach: Undated Bullet Nose Disconnected & Removed with Head ML0515202262005-05-24024 May 2005 2SI-825B Not Full Open with Handwritten Notations ML0515202242005-05-24024 May 2005 Phone Line Through Containment Hatch While Fuel Movement in Progress ML0515202232005-05-24024 May 2005 Loss of SFP Cooling Due to Breaker Miss Alignment ML0515202212005-05-24024 May 2005 2SI-825B Not Full Open with Handwritten Notations ML0515202192005-05-24024 May 2005 U1R28 Interim Exit Meeting Notes ML0515202182005-05-24024 May 2005 Tsac Not Entered When Source Range Audible Count Rate Removed from Service ML0515202072005-05-24024 May 2005 Questions for Followup Based on Last Outage ISI Summary Report ML0514700772005-05-24024 May 2005 Refuel Outage 1R28 Resident Inspector Coverage ML0514700822005-05-24024 May 2005 Mikes 2004-03 IR Section Write Ups, 2T-34A Accumulator Level Indication ML0515201472005-05-24024 May 2005 Phone Line Through Containment Hatch While Fuel Movement in Progress ML0515202132005-05-24024 May 2005 Inservice Inspection Document Request ML0515201492005-05-24024 May 2005 Transient Combustible Materials in Containment & Turbine Building Without Administrative Controls 2022-02-16
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_ID NDE Procedure Related Questions/Requests (3/29/04)
Provide NDE-109 (used for determining weld thickness profiles).
- 1) NDE-163 a) This appears to be a Performance Demonstration Initiative (PDI) qualified procedure.
If so, provide the PDI qualification record.
b) Does this procedure limit transducer selection to 60 degree RL? If so why is this necessary for ferritic material?
c) This procedure lacks Code acceptance criteria (Section Xl, Table IWB(C)-3410-1 and IWB(C)-351 0). Please provide governing procedure which describes who is responsible for applying Code acceptance criteria and how this process is documented.
d) What areas of this procedure deviate from ASME Section V, Article 4 requirements which necessitated use of IWA-2240 procedure demonstration?
- 2) NDE-171, NDE-164 a) These procedures lack Code acceptance criteria (Section XI, Table IWB(C)-341 0-1 and IWB(C)-3514). Please provide governing procedure which describes who is responsible for applying Code acceptance criteria and how this process is documented.
- 3) NDE-172 & 173 a) These procedures lack Code acceptance criteria (Section Xl, Table IWB(C)-341 0-1 and IWB(C)-3514). Please provide governing document which describes who is responsible for applying Code acceptance criteria and how this process is documented b) These procedures require same examination volume for all risk based welds. This appears to be excessive for R1.20 welds not subject to degradation. Please explain basis for using a single examination volume and is this ALARA?
- 4) NDE-350 a) This procedure contains acceptance criteria unlike other NDE procedures why the difference?
b) Procedure does not address demagnetization required by Section V, Article 7 T-750.
Why not? Do you need a Code relief?
- 5) NDE-451 a) Provide the record of qualification at the non-standard temperature range allowed 45-120 F (e.g. below Code minimum 50 F) (required by T-653 of Article 6 of Section V).
b) Has this procedure ever been used at less than 50 degrees F on Code components?
If so provide a copy the examination records.
c) This procedure contains acceptance criteria unlike other NDE procedures why the difference?
- 6) NDE-750 2_
a) Paragraph 5.4.2(g) of this procedure modified Code words from Section Xl, (IWB 3517(h)) to indicate that only leakage near carbon steel bolting was considered a recordable indication. Please provide the NRC approved relief request or Code Case that allows modification to these Code requirements. If no NRC approval, please identify how VT-1 inspectors would confirm bolting was not carbon steel and what actions you will take to meet Code.
b) Procedure does not address or reference surface preparation and pre-cleaning requirements as required by Article 9 of Section V. What actions are being taken to come into compliance with Code?
c) Procedure does not address report or general statement to be completed following the examination as required by Article 9 of Section V. What actions are being taken to come into compliance with Code?
d) This procedures lacks acceptance criteria. Please provide governing document which describes who is responsible for applying acceptance criteria and how this process is documented.
- 7) NDE-753 a) Procedure does not address or reference surface preparation and pre-cleaning requirements as required by Article 9 of Section V. What actions are being taken to come into compliance with Code?
b) Procedure does not incorporate requirements of Section Xl, IWA 5244 with specific instructions applicable to testing of buried Code components. Please explain why these requirements are not in this procedure. Has this procedure been used in conjunction with testing of buried Code components? If so, were the Code requirements followed?
c) This procedures lacks acceptance criteria. Please provide governing document which describes who is responsible for applying acceptance criteria and how this process is documented.
- 8) NDE-757 a) Provide a copy of the lesson plan and training materials on industry experience for RPV leakage given to the NDE inspectors to comply with Section 2.1.4 of this procedure.
- 9) Technical Specification 5.5.8.c "Examination Method and Requirements," incorrectly refers to Appendix IV, of ASME Section Xl as the applicable requirements. The correct section of the Code which contains the requirements which apply to ET of SG tubes is in Section V, Article 8, Appendix II. This requirement comes from the ASME Code 1998 Edition, 2000 Addenda Section XI, Paragraph IWA-2233 "Eddy Current Examination, "
Eddy current examination (ET) shall be conducted in accordance with Section V, Article 8, Appendix II. Please discuss your actions to correct this reference error.