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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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NRC AFW SPECIAL INSPECTION REQUEST FOR INFORMATION I Question # 9 Inspector O'Brien Date 11/06/02 1 Question: (a) When was QA to non-QA boundary extended beyond the recirc AOV?
In 1988 mod, the QA boundary was at the AOV. (b) Should the DP switch to the AOV air control be SR? (3) On M-217 Sh 1, Is the line from DPIS-4002 to 2AF-4002-S safety-related? It is indicated as AQ.
Response
a) The QA boundary was extended in November of 1996 under Q-List Discrepancy 96 058 (copy attached). The change was due to a recognition of the safety related functions to prevent pump runout and to ensure adequate backpressure to provide forward feed capability. These are correct assertions, and the level of documentation provided is consistent with the plant practices at the time.
Concurrent with the Q-List upgrade, a Drawing Change Request (DCN 96-2512; attached) was issued against the Green Line Drawing (GLD M-217 Sht 1; a non-QA document) to show the line from the recirc isolation valve through the flow limiting orifice as a Safety Related line. No explanation was provided other than "Administrative Correction". A check of all DBD Open Items for that DBD found no mention of a concern or open item against the GLD. However, the concurrent timing and a signature in common between this document change and the Q-list change supports indicates they had the same origin.
b) The dP switches to actuate the recirculation flow isolation AOVs are Safety Related as reflected in both CHAMPS and the GLD. Attached are printouts of the CHAMPS database with the safety related classifications highlighted. Note that this was a question asked and answered by the Red Finding investigation team in -August 2002.
c) Investigation into this question resulted in finding a considerably more complicated power and logic scheme than is apparent from the P&ID. Actuation schemes are attached. While the power to the solenoid valve is Safety Related DC power, the power is applied through an interposing AC relay. While that relay and it's power supply are not specifically designated Safety Related, they are powered from a diesel-backed AC power supply. This appears to have been an error in the scope of the modification to upgrade the function of the AOV to open to a Safety function. CAP 30040 has been originated to document this deficiency, and to track resolution. Currently, none of the AFW recirculation lines are credited with functioning under any conditions (due to line blockage concerns). Before these lines can be considered fully Operable, this issue will also have to be resolved.
Prepared By T. C. Kendall Date Reviewed by Licensing ___ _Date P/0'7 Provided to NRC By Date