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| {{#Wiki_filter:}} | | {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 21,2010 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE FEEDWATER LINE BREAK WITH LOSS OF OFFSITE POWER AND SINGLE FAILURE ANALYSIS (TAC NOS. ME4596, ME4597, AND ME4598) |
| | |
| | ==Dear Mr. Edington:== |
| | |
| | By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102510161), Arizona Public Service Company (the licensee), submitted a license amendment request to revise the methodology in the feedwater line break with loss of offsite power and single failure event (FWLB/LOP/SF) analysis summarized in the Palo Verde Nuclear Generating Station Updated Final Safety Analysis Report. The revision would change the credited operator action time to 20 minutes from 30 minutes. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that additional information identified in the enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided to Mr. Russell Stroud of your staff via e-mail on Monday, December 6, 2010. A conference call with Mr. Tom Weber and others of your staff was held on December 16, 2010. During that call, Mr. Weber agreed to provide the responses to the requests for additional information by February 11, 2011. |
| | R. Edington -2 If you have any questions, please contact me at (301) 415-4032 or via e-mail at randy.hall@nrc.gov. |
| | Sincerely, James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE THE FEEDWATER LINE BREAK WITH LOSS OF OFFSITE POWER AND SINGLE FAILURE ANALYSIS PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 ARIZONA PUBLIC SERVICE COMPANY DOCKET NOS. STN-50-528, STN-50-529, AND STN-50-530 By letter dated August 27,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102510161), Arizona Public Service Company (the licensee), submitted a license amendment request (LAR) to revise the methodology in the feedwater line break with loss of offsite power and single failure event (FWLB/LOP/SF) analysis summarized in the Palo Verde Nuclear Generating Station (PVNGS) Updated Final Safety Analysis Report. The revision would change the credited operator action time to 20 minutes from 30 minutes. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the following additional information is needed to complete the review: The LAR states that the current PVNGS emergency operating procedures (EOPs) contain explicit directions to the operators to ensure that the plant is placed in a stable, safe condition following an FWLB event. Opening of the atmospheric dump valve (ADV) that is connected to the unaffected steam generator (SG) is in the EOPs for standard post trip actions (40EP-9E001), excess steam demand (40EP-9E005), loss of all feedwater (40EP-9E006), and LOP/loss of forced circulation events (40EP-9E007). |
| | Please identify the FWLB EOP that directs the opening of this ADV as one of the variable methods. The licensee stated that the assumed operator action of opening an ADV is not mandated by the EOPs. If an operating crew decides to use alternate methods, please explain if the time duration of the various action sequences will be less than or equal to opening an ADV. The table in Insert C of the Enclosure to the letter dated August 27, 2010, indicates that the operators will open the ADV, at 20 minutes, to 10 percent of its full throat area. From this, it is inferred that the intent is to maintain the shell-side water level by relieving only the steam that is generated by boiling off the incoming 650 gallons per minute of auxiliary feedwater flow. Please show that there is a stable SG water level indication available to the operators; Please discuss the effect, if any, upon SG water level indication caused by the Enclosure |
| | -2 FWLB-induced hostile environment in the region of the intact SG; Please confirm that the ADV flow area can be controlled to 10; and Please confirm that, given the LOP, there is a reliable and sufficient source of power to move the ADV, continually, to maintain the desired relief rate, for at least 10 minutes. Please provide an evaluation to show that the 20 minutes includes the time allowed for indication and recognition, diagnosis, operator action, and system response. |
| | Include all documentation required by American National Standards Institute/American Nuclear Society (ANSI/ANS)-58.8, 'Time Response Design Criteria for Nuclear Safety Related Operator Actions' (Le., the required operator action and the manipulations that make up the action, the indications that prompt the operator(s), and the feedback by which the operator verifies that the action succeeded or failed). Also, please provide event analysis chart(s) showing the assumed time interval estimates including time to indication, time to diagnose, time to complete the action, process time until success or failure would be recognized, and safety margin assumed, if any.1 Please provide any available empirical human performance data, such as timed simulator training scenarios, that are available to derive time intervals that could justify crediting the 20-minute assumption. |
| | The NRC staff notes that, in accordance with ANSI/ANS-58.8, such empirical evaluation should be designed to yield results at a 95 percent confidence level.1 Please describe or provide a copy of the procedure for controlling the planfs Time Critical Action Program. The licensee stated in its submittal, "If an error were to occur for any reason there is ample indication of plant status available to the operators to ensure timely recovery:' |
| | Please provide the basis for this statement. |
| | Please state how the recovery time was estimated or determined. |
| | Also, please explain how there can be sufficient time available to recover if the diagnosis takes the full 20 minutes available. |
| | 1 Information provided in response to this request for additional information should provide evidence that PVNGS operators are highly likely (95 percent confidence or higher) to be capable of performing the required actions in the expected control room environment within the assumed time constraints of the analysis. |
| | ----------R. Edington -2 If you have any questions, please contact me at (301) 415-4032 or via e-mail at randy.hall@nrc.gov. |
| | Sincerely, IRA by Lynnea Wilkins fori James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPLIV r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDirslhpb Resource RidsNrrDorlLpl4 Resource RidsNrrDssSrxb Resource RidsNrrPMPaloVerde Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GLapinsky, NRR/DIRS/IHPB SMiranda, NRR/DSS/SRXB NAME LKGibson DATE 12/20/10 OFFICE NRR/DSS/SRXB/BCNAME AUlses* -DATE 12/2/10 ADAMS Accession No ML 103500510 |
| | *via e-mail dated ... |
| | NRR/LPL4/PM NRR/LPL4/LA OFFICE NRR/LPL4/PM |
| | _NRRIDIRSIIHPB/BC JRHall (LWilkins for) 12/20/10 NRR/LPL4/BC MMarkley 12/21/10 -.= JBurkhardt |
| | --------UShoop* 12/17/10 12/6/10 NRR/LPL4/PM |
| | -------------- |
| | JRHall (LWilkins for) ..-. |
| | _12/2 I OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
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MONTHYEARML1025101612010-08-27027 August 2010 Request for Operating License Amendment - Revision of Feedwater Line Break with Loss of Offsite Power and Single Failure Analysis Project stage: Request ML1027102522010-09-28028 September 2010 Acceptance Review E-mail, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Acceptance Review ML1035005102010-12-21021 December 2010 Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: RAI ML1105503232011-02-11011 February 2011 Response to Request for Additional Information Regarding License Amendment Request to Revise the Feedwater Line Break with Loss of Offsite Power and Single Failure Analysis Project stage: Response to RAI ML1109103822011-04-0101 April 2011 Draft Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Draft RAI ML1109103772011-04-0101 April 2011 Email Draft Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Draft RAI ML1111605542011-04-26026 April 2011 E-mail, Revised Draft Request for Additional Information on Revision of Feedwater Line Break with Loss of Offsite Power and Single Failure Analysis Project stage: Draft RAI ML1111605442011-04-26026 April 2011 E-mail, Revised Draft Request for Additional Information on Revision of Feedwater Line Break with Loss of Offsite Power and Single Failure Analysis Project stage: Draft RAI ML11159A0292011-05-25025 May 2011 Response to the Second Request for Additional Information Regarding License Amendment Request to Revise the Feedwater Line Break with Loss of Offsite Power & Single Failure Analysis Project stage: Request ML1117207432011-06-21021 June 2011 Individual Notice of Consideration of Issuance of Amendment, Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Other ML1117206732011-06-21021 June 2011 Letter, Individual Notice of Consideration of Issuance of Amendment, Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Other NRC-2011-0142, Individual Notice of Consideration of Issuance of Amendment, Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis (TAC Nos. ME4596, ME4597, ME4598)2011-06-21021 June 2011 Individual Notice of Consideration of Issuance of Amendment, Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis (TAC Nos. ME4596, ME4597, ME4598) Project stage: Approval ML1118805242011-08-31031 August 2011 Issuance of Amendment Nos. 187, 187, and 187, Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis Project stage: Approval 2011-04-01
[Table View] |
Palo Verde, Units 1, 2, and 3, Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report, Feedwater Line Break Analysis with LOOP and Single Failure Analysis (TAC Nos. ME4596, ME4597, and MML103500510 |
Person / Time |
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Site: |
Palo Verde ![Arizona Public Service icon.png](/w/images/9/93/Arizona_Public_Service_icon.png) |
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Issue date: |
12/21/2010 |
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From: |
Hall J R Plant Licensing Branch IV |
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To: |
Edington R K Arizona Public Service Co |
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Gibson, Lauren, NRR/DORL/LPL4, 415-1056 |
References |
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TAC ME4596, TAC ME4597, TAC ME4598 |
Download: ML103500510 (5) |
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Category:Request for Additional Information (RAI)
MONTHYEARML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23031A3392023-01-31031 January 2023 In-service Inspection Request for Information ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22272A3252022-09-29029 September 2022 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML22209A1752022-07-28028 July 2022 Inservice Inspection Request for Information ML22187A2632022-07-0606 July 2022 Notification of Inspection (NRC IR 05000528/2022004, 05000529/2022004 and 05000530/2022004) and Request for Information ML22067A2292022-03-0202 March 2022 Inservice Inspection Inspection PWR Request for Information ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report ML22035A3302022-02-10010 February 2022 Requests for Confirmation of Information for Exemption to Delete Diverse Auxiliary Feedwater Actuation System Based on Risk-Informed Process for Evaluations ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21245A2222021-09-0101 September 2021 Request for Information ML21200A2392021-07-20020 July 2021 Docs Request AC - AA August 2021 ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21042B9692021-02-18018 February 2021 Notification of NRC Design Bases Assurance Inspection and Initial Request for Information ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML21011A1972021-01-12012 January 2021 Unit 2, and Unit 3 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012) and Request for Information ML20227A0992020-08-14014 August 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20118D1362020-04-28028 April 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20049A0992020-02-14014 February 2020 Notification of Cyber Security Inspection (NRC Inspection Report 05000528/2020401; 05000529/2020401; and 05000530/2020401) and Request for Information ML20049A0252020-02-12012 February 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for License Amendment Request Associated with Changes to Emergency Plan Staffing Requirements ML20021A3172020-01-21021 January 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for Relief Request 64, Impractical Examinations for the Third 10-Year ISI Interval ML19317D0782019-11-13013 November 2019 NRR E-mail Capture - Palo Verde 1 - Requests for Additional Information on Unit 1 21st Refueling Outage Steam Generator Tube Inspection Report ML19234A3202019-08-29029 August 2019 Redacted - Request for Additional Information for Amendment and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194; EPID L-2018-LLE-0010) ML19155A1842019-05-30030 May 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mvib Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19095A6552019-04-0404 April 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mphb Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19044A7342019-02-13013 February 2019 NRR E-mail Capture - Palo Verde1, 2, and 3 - Official Requests for Additional Information for RR 62, Third and Fourth 10-Year ISI Intervals, Proposed Alternative - Pressurizer Heat Sleeve Repairs ML19008A3612019-01-0808 January 2019 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR Associated with Response Time Testing of Pressure Transmitters ML18341A0252018-12-0303 December 2018 Notification of NRC Design Bases Assurance Inspection (Teams)(05000528/2019011, 05000529/2019011, and 05000530/2019011) and Initial Request for Information ML18271A0392018-10-0202 October 2018 Non Proprietary - Supplemental Information Needed for Acceptance of Requested License Amendments and Exemptions Implementation of Framatome High Thermal Performance Fuel (Epids L-2018-LLA-0194 and L-2018-LLE-0010) ML18221A5102018-08-23023 August 2018 Request for Additional Information License Amendment Request to Adopt Risk-Informed Completion Times (CAC Nos. MF6576, MF6577, and MF6578; EPID: L-2015-LLA-0001) ML18229A3132018-08-17017 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 - Second Se ML18227A8672018-08-15015 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 ML18124A0112018-05-0303 May 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official Eeob RAIs for TSTF-505 (4b) LAR (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML18099A0072018-04-0606 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for 10 CFR 50.69 LAR (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML18094B1122018-04-0404 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAIs for TSTF-505 (Initiative 4b) LAR (CAC Nos. MF6576, MF6577, and MF6578: EPID L-2015-LLA-0001) ML18066A7032018-03-0707 March 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) 05000528/2018011, 05000529/2018011, and 05000530/2018011 Initial Request for Information ML17248A0162017-08-31031 August 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAI for RRs PRR-03, PRR-04 and PRR-05, Pump Testing ML17107A0052017-04-14014 April 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Ngf LAR and Exemption RAIs (CAC Nos. MF8076 to MF8081) ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 ML17003A0182017-01-0202 January 2017 NRR E-mail Capture - Palo Verde, Unit 3 - Draft RAIs for the Second Emergency LAR Associated with EDG 3B Failure ML16258A0312016-09-14014 September 2016 PVNGS Units 1-3 - Notif of NRC Insp of the Implementation of Mitigation Strategies and Spent Fuel Pool Instr. Orders and Emer. Prep. Comm./Staffing/Multi-Unit Dose Assessment Plns(05000528/ 2016009;05000529/2016009;and 05000530/2016009) and ML16111B3312016-04-20020 April 2016 Notification of NRC Component Design Bases Inspection (05000528/2016007; 05000529/2016007; 05000530/2016007) and Initial Request for Information ML16083A2502016-03-23023 March 2016 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Official RAIs for EAL LAR 2024-01-10
[Table view] Category:Letter
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 21,2010 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE FEEDWATER LINE BREAK WITH LOSS OF OFFSITE POWER AND SINGLE FAILURE ANALYSIS (TAC NOS. ME4596, ME4597, AND ME4598)
Dear Mr. Edington:
By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102510161), Arizona Public Service Company (the licensee), submitted a license amendment request to revise the methodology in the feedwater line break with loss of offsite power and single failure event (FWLB/LOP/SF) analysis summarized in the Palo Verde Nuclear Generating Station Updated Final Safety Analysis Report. The revision would change the credited operator action time to 20 minutes from 30 minutes. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that additional information identified in the enclosure to this letter is needed in order for the NRC staff to complete its review. The draft copy of the request for additional information was provided to Mr. Russell Stroud of your staff via e-mail on Monday, December 6, 2010. A conference call with Mr. Tom Weber and others of your staff was held on December 16, 2010. During that call, Mr. Weber agreed to provide the responses to the requests for additional information by February 11, 2011.
R. Edington -2 If you have any questions, please contact me at (301) 415-4032 or via e-mail at randy.hall@nrc.gov.
Sincerely, James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE THE FEEDWATER LINE BREAK WITH LOSS OF OFFSITE POWER AND SINGLE FAILURE ANALYSIS PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 ARIZONA PUBLIC SERVICE COMPANY DOCKET NOS. STN-50-528, STN-50-529, AND STN-50-530 By letter dated August 27,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102510161), Arizona Public Service Company (the licensee), submitted a license amendment request (LAR) to revise the methodology in the feedwater line break with loss of offsite power and single failure event (FWLB/LOP/SF) analysis summarized in the Palo Verde Nuclear Generating Station (PVNGS) Updated Final Safety Analysis Report. The revision would change the credited operator action time to 20 minutes from 30 minutes. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee and determined that the following additional information is needed to complete the review: The LAR states that the current PVNGS emergency operating procedures (EOPs) contain explicit directions to the operators to ensure that the plant is placed in a stable, safe condition following an FWLB event. Opening of the atmospheric dump valve (ADV) that is connected to the unaffected steam generator (SG) is in the EOPs for standard post trip actions (40EP-9E001), excess steam demand (40EP-9E005), loss of all feedwater (40EP-9E006), and LOP/loss of forced circulation events (40EP-9E007).
Please identify the FWLB EOP that directs the opening of this ADV as one of the variable methods. The licensee stated that the assumed operator action of opening an ADV is not mandated by the EOPs. If an operating crew decides to use alternate methods, please explain if the time duration of the various action sequences will be less than or equal to opening an ADV. The table in Insert C of the Enclosure to the letter dated August 27, 2010, indicates that the operators will open the ADV, at 20 minutes, to 10 percent of its full throat area. From this, it is inferred that the intent is to maintain the shell-side water level by relieving only the steam that is generated by boiling off the incoming 650 gallons per minute of auxiliary feedwater flow. Please show that there is a stable SG water level indication available to the operators; Please discuss the effect, if any, upon SG water level indication caused by the Enclosure
-2 FWLB-induced hostile environment in the region of the intact SG; Please confirm that the ADV flow area can be controlled to 10; and Please confirm that, given the LOP, there is a reliable and sufficient source of power to move the ADV, continually, to maintain the desired relief rate, for at least 10 minutes. Please provide an evaluation to show that the 20 minutes includes the time allowed for indication and recognition, diagnosis, operator action, and system response.
Include all documentation required by American National Standards Institute/American Nuclear Society (ANSI/ANS)-58.8, 'Time Response Design Criteria for Nuclear Safety Related Operator Actions' (Le., the required operator action and the manipulations that make up the action, the indications that prompt the operator(s), and the feedback by which the operator verifies that the action succeeded or failed). Also, please provide event analysis chart(s) showing the assumed time interval estimates including time to indication, time to diagnose, time to complete the action, process time until success or failure would be recognized, and safety margin assumed, if any.1 Please provide any available empirical human performance data, such as timed simulator training scenarios, that are available to derive time intervals that could justify crediting the 20-minute assumption.
The NRC staff notes that, in accordance with ANSI/ANS-58.8, such empirical evaluation should be designed to yield results at a 95 percent confidence level.1 Please describe or provide a copy of the procedure for controlling the planfs Time Critical Action Program. The licensee stated in its submittal, "If an error were to occur for any reason there is ample indication of plant status available to the operators to ensure timely recovery:'
Please provide the basis for this statement.
Please state how the recovery time was estimated or determined.
Also, please explain how there can be sufficient time available to recover if the diagnosis takes the full 20 minutes available.
1 Information provided in response to this request for additional information should provide evidence that PVNGS operators are highly likely (95 percent confidence or higher) to be capable of performing the required actions in the expected control room environment within the assumed time constraints of the analysis.
R. Edington -2 If you have any questions, please contact me at (301) 415-4032 or via e-mail at randy.hall@nrc.gov.
Sincerely, IRA by Lynnea Wilkins fori James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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_12/2 I OFFICIAL RECORD COpy