Letter Sequence Draft RAI |
---|
|
|
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] |
|
---|
Category:Request for Additional Information (RAI)
MONTHYEARML24297A6212024-10-22022 October 2024 Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300 ML24257A1012024-09-11011 September 2024 Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24011A1002024-01-10010 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) 2024-09-11
[Table view] |
Text
REVISED DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING REVISION OF FEEDWATER LINE BREAK WITH LOSS OF OFFSITE POWER AND SINGLE FAILURE ANALYSIS PALO VERDE UNITS 1, 2, & 3 DOCKET NUMBERS 50-528, 50-529, & 50-530 By a letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML102510161), Arizona Public Service Company (APS) requested a license amendment to Operating Licenses NPF-41, NPF-51, and NPF-74, for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 respectively, to allow credit for reducing the available time for an existing manual operator action to initiate pressurizer level control. The revised analysis would assume that the action is initiated at twenty minutes into the scenario as opposed to the current assumption of thirty minutes. The staff requested additional information in its letter dated December 21, 2010 (ADAMS Accession No.ML103500510). The licensee responded with supplementary information in its submittal dated February 11, 2011 (ADAMS Accession No. ML110550323).
The Health Physics and Human Performance Branch (IHPB) performed a review of the supplementary information associated with the license amendment request. The licensees responses to the following requests for additional information (RAI) with regard to the human performance aspects of the license amendment will allow the staff to complete its review in a timely manner.
The licensee has based its evaluation of the reduced time available to initiate control of pressurizer level on the guidance of ANSI/ANS-58.8 Time Response Design Criteria for Nuclear Safety Related Operator Actions, 1984.
- 1. The current version of ANSI/ANS-58.8 is ANSI/ANS-58.8-1994, reaffirmed on August 25, 2008. Please review your submittals in light of this most current version of ANSI/ANS-58.8 and identify any changes you would like to make based on the review.
Note: The NRC has not endorsed ANSI/ANS-58.8. The IHPB staff uses IN 97-78 and NUREG-1764, in addition to the Standard Review Plan (NUREG-0800), for its review of changes to operator response times.
- 2. In its submittals, the licensee requests credit for operator action at 20 minutes.
This terminology implies a start time rather than a duration. Use of this terminology is vague and could mean that the action (including recognition and diagnosis) is initiated at 20 minutes, or that the physical act of opening an ADV (NOT including recognition and diagnosis) is initiated at 20 minutes, or that the entire action from recognition to successful completion of the safety function takes place in 20 minutes or less.
Examples from the licensees submittal dated August 27, 2010 are:
- the analysis assumes operator action to open an ADV (on the intact steam generator) to preclude a direct challenge to the RCS Inventory Control and RCS Pressure Control Safety Functions twenty (20) minutes after the event initiation.
- The FWLB/LOP/SF event analysis is revised such that operator action is now credited after 20 minutes (1200 seconds) of the transient instead of the previous 30-minute (1800 seconds) time frame.;
- The assumption of operator action within 20 minutes after the first few alarms are triggered is based on ANSI/ANS Standard 58.8, Time Response Design Criteria for Nuclear Safety Related Operator Actions (Reference 6.5). ;
- 20 minutes is considered by the industry as a reasonable length of time for the operators to determine what has happened, assess the current conditions, and initiate required actions to mitigate the conditions.
Please clarify what is meant by at 20 minutes; is it a start time or a duration?
- 3. Please provide more information on the simulator verification. For example, what were the makeups of the crews, and how many times was the scenario run?
Furthermore, are the required actions also part of a more frequently performed set of procedures that the individuals have more experience performing? If so, please describe whether that experience supports the basis for the time associated with the actions.
- 4. Although the licensee believes that it has addressed all credible errors, the staff would like the licensee to consider the case where an operator inadvertently sets the ADV thumbwheel for open/close demand at 10% closed (90% open) instead of 10%
open. How long would it take the operator(s) to recognize the mistake (based on instrument responses or annunciator alarms) and correct the setting? Are there any adverse consequences if the operators do not recognize the error?