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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 2R24 ML23013A0912023-01-13013 January 2023 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R23 ML22189A1432022-07-0808 July 2022 Fourth 10-Year Interval, First Period Owners Activity Report Number 1R23 ML22018A2022022-01-18018 January 2022 Fourth 10-Year Interval, First Period Owners Activity Report Number 2R23 ML21341A5522021-12-0303 December 2021 Snubber Program for the Fourth 10-Year Testing Interval ML21292A1842021-10-19019 October 2021 Nd Refueling Outage Steam Generator Tube Inspection Report ML21197A2052021-07-16016 July 2021 Fourth 10-Year Interval, First Period Owner'S Activity Report Number 3R22 ML21047A4972021-02-16016 February 2021 Twenty-Second Refueling Outage Owner'S Activity, Report 1R22 ML20288A2982020-10-13013 October 2020 Refueling Outage 22 Steam Generator Inspection Report ML20203M2042020-07-17017 July 2020 Fourth 10-Year Interval, First Period Owner'S Activity Report Number 2R22 ML20054A2692020-02-19019 February 2020 Response to Request for Additional Information - Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML20028D5402020-01-24024 January 2020 Owner'S Activity Report Number U3R21 ML19291F5762019-10-18018 October 2019 Generator (Pvggs), Unit 1 - Steam Generataor Tube Inspection Ruport ML19205A2642019-07-24024 July 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U1R21 ML19198A3402019-07-17017 July 2019 Relief Request 64 - Unit 1 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19179A3312019-06-28028 June 2019 Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML19017A3452019-01-17017 January 2019 Fourth 10-Year Interval Pump and Valve Inservice Testing Program ML19010A3072019-01-10010 January 2019 Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML18306A9992018-11-0202 November 2018 Steam Generator Tube Inspection Report ML18277A2972018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 1 of 7 ML18277A3192018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 5 of 7 ML18277A3032018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 2 of 7 ML18277A3102018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update. (Part 3 of 7) ML18277A3122018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 4 of 7 ML18277A3232018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 7 of 7 ML18277A3212018-09-21021 September 2018 Third 10-Year Interval Inservice Inspection Program Update, Part 6 of 7 ML18102B6842018-04-12012 April 2018 Third 10-Year Interval, Third Period: Owner'S Activity Report Number 1R20 Correction ML18093A3352018-03-30030 March 2018 Palo Verde, Units 1, 2 and 3 - Fourth 10-Year Interval Pump and Valve Inservice Testing Program ML18030B1382018-01-26026 January 2018 Third 10-Year Interval, Third Period: Owner'S Activity Report Number 1R20 ML17270A4242017-09-26026 September 2017 Transmittal of 20th Refueling Outage Steam Generator Tube Inspection Report ML17181A5202017-06-30030 June 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R20 ML17248A5232017-05-30030 May 2017 3INT-ISI-1, Revision 5, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 1, Enclosure 1 to 102-07551-MDD/MSC ML17248A5252017-05-26026 May 2017 3INT-ISI-2, Revision 6, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 2, Enclosure 2 to 102-07551-MDD/MSC ML17054D6872017-02-23023 February 2017 Fourth 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests GRR-01, GRR-02, PRR-01, PRR-02, PRR-03, PRR-04, PRR-05, and PRR-06 ML16308A2322016-10-26026 October 2016 Steam Generator Tube Inspection Report - Refueling Outage 19 ML16180A4462016-06-24024 June 2016 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U1R19 ML16015A4542016-01-15015 January 2016 Submittal of Owner'S Activity Report (Form OAR-1) Refueling Outage 19 (U2R19) ML15267A2692015-09-23023 September 2015 Steam Generator Tube Inspection Report ML14035A4042013-08-29029 August 2013 3INT-ISI-3, Rev. 3, Palo Verde, Unit 3, 3rd Interval: Inservice Inspection Program Summary Manual ML14035A4022013-08-28028 August 2013 3INT-ISI-2, Rev. 4, Palo Verde, Unit 2, 3rd Interval: Inservice Inspection Program Summary Manual ML14035A4002013-08-22022 August 2013 INT-ISI-1, Rev. 3, 3rd Interval, Inservice Inspection Program Summary Manual ML13182A0152013-06-26026 June 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R17 ML14035A3992013-05-31031 May 2013 INT-ISI-1, Rev. 2, 3rd Inspection Interval, Inservice Inspection Program Summary Manual ML14035A4012013-05-31031 May 2013 INT-ISI-2, Rev. 3, 3rd Inspection Interval, Inservice Inspection Program Summary Manual ML14035A4032013-05-31031 May 2013 3INT-ISI-3, Rev. 2, Palo Verde, Unit 3, 3rd Interval: Inservice Inspection Program Summary Manual ML12242A2492012-08-0707 August 2012 Steam Generator Tube Inspection Report ML11287A0142011-10-0404 October 2011 Revised Third 10 Year Interval Inservice Inspection Plans ML11136A1062011-05-0505 May 2011 Submittal of Steam Generator Tube Inspection Report 2024-07-11
[Table view] Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 2024-09-27
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10 CFR 50.55a LA M A subsidiaryof Pinnacle West CapitalCorporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06009-DCM/GAM May 22, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Pump Relief Request PRR-08 Pursuant to 10 CFR 50.55a(a)(3)(ii), Arizona Public Service Company (APS) hereby requests NRC approval of the following request for relief from the comprehensive pump testing requirements of ASME/ANSI OM Code 2001 Edition, 2003 Addenda. The details of the 10 CFR 50.55a request are enclosed.
APS requests verbal authorization for this relief request by May 22, 2009. Verbal authorization is requested due to the unforeseen circumstances described below that would delay the timely resumption of PVNGS Unit 3 operation without this relief.
On May 20, 2009, during preparations to enter Mode 4 following the Unit 3 refueling outage, excessive seal leakage was discovered in the train B high pressure safety injection (HPSI) pump outboard seal. The HPSI B pump has been repaired. The post maintenance test required by the Code is a Comprehensive/Full Flow Test to demonstrate design basis capability. However, this comprehensive pump test would necessitate the removal of the reactor head to create the flow path needed to achieve the comprehensive flow rate. This test is normally performed with the reactor in the defueled state. The proposed relief would permit the alternative use of the HPSI pump recirculation path as the post maintenance test to demonstrate the HPSI pump design capability to support operability. Restoration of HPSI pump operability is required in order for Unit 3 to resume operation.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon 0 Palo Verde 9 San Onofre
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Relief Request PRR-08 Page 2 No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
Sincerely, DCM/SAB/GAM/gat
Enclosure:
Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing - Relief Request PRR-08 cc: E. E. Collins Jr. NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector
Enclosure Inservice Testing Relief Request for High Pressure Safety Injection Pump Testing Relief Request PRR-08
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
- 1. ASME Code Component(s) Affected Pump 3MSIBPO2 is the train B high pressure safety injection (HPSI) pump in Palo Verde Nuclear Generating Station (PVNGS) Unit 3. This is a safety-related centrifugal pump model 4X1 1CA-8 manufactured by Ingersol-Rand.
2. Applicable Code Edition and Addenda
ASME/ANSI OM Code 2001 Edition, 2003 Addenda.
- 3. Applicable Code Requirements ISTB-3310 Effect of Pump Replacement, Repair, and Maintenance on Reference Values. When a reference value or set of values may have been affected by repair, replacement, or routine servicing of a pump, a new reference value or set of values shall be determined in accordance with ISTB-3300, or the previous value reconfirmed by a comprehensive or Group A test run, before declaring the pump operable. The Owner shall determine whether the requirements of ISTB-3100, to reestablish reference values, apply. Deviations between the previous and new set of reference values shall be evaluated, and verification that the new values represent acceptable pump operation shall be placed in the record of tests (see ISTB-9000).
ISTB-3510 General (a) Accuracy - Instrument accuracyshall be within the limits of Table ISTB-3500-1. If a parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table ISTB-3500-1 (e.g., flow rate determination shall be accurate to within +/- 2% of actual). For individual analog instruments, the required accuracy is percent of fullscale. For digital instruments, the required accuracy is over the calibrated range. For a combination of instruments, the required accuracy is loop accuracy.
, Table ISTB-3500-1 Required Instrument Accuracy - Flow Rate for Comprehensive and Preservice Tests, +/- 2%.
- 4. Reason for Request During the current PVNGS Unit 3 refueling outage, the HPSI B pump outboard mechanical seal was replaced, which required the removal of the outboard bearing. A full flow comprehensive test was performed following that maintenance. During preparations to enter Mode 4 following the refueling outage, problems with the new mechanical seal were encountered, which required the installation of another new mechanical seal. Mechanical seal 1
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii) replacement required removal of the outboard pump bearing. Palo Verde installed a new outboard bearing at the recommendation of the pump vendor, Flowserve.
This pump falls under the Group B categorization in the applicable ASME OM Code. ISTB-3310 requires that a comprehensive pump test be performed when a reference value may have been affected. In this case, vibration is the only reference value that is potentially impacted by the maintenance performed.
Since the bearing and outboard mechanical seal are new, it is expected that vibration performance will change to some degree. It is unknown how much performance will change, if at all. Arizona Public Service Company (APS) is unable to determine, without creating a hardship, if the vibration parameter may be affected by the change to the degree necessary to require reestablishment of the reference values at the comprehensive test flow point.
APS is in the process of restarting PVNGS Unit 3 from a refueling outage and is presently in Mode 5. The HPSI pump comprehensive flow test would necessitate the removal of the reactor head to create an adequate flow path to achieve the comprehensive test flow rate. This test is normally performed with the reactor defueled. To perform the comprehensive flow rate test in the current plant conditions would require a temporary procedure change that would enable the test to be performed without removing the reactor head and defueling. The test would require a unique alignment. The control room operators would be required to quickly react in the event of an imbalance in the flow to the Reactor Coolant System (RCS) and letdown from the RCS in the event of a mismatch to prevent low temperature overpressurization.
The concern is that the risk of performing the test under the present conditions exceeds the safety benefit that the pump retest at full flow would provide if performed in strict accordance with the ASME OM Code rules. The purpose of performing the comprehensive pump test following maintenance is to determine if the vibration reference value has been impacted to the degree necessary that the acceptance criteria needs to be adjusted. Testing at lower flow values other than the comprehensive test flow rate can yield vibration information that will provide sufficient assurance that the pump would be able to perform its safety function if it were called upon. This is a one-time request until the comprehensive test is performed again in the next refueling outage.
- 5. Proposed Alternative and Basis for Use The pump can be run on a larger (non-orifice) recirculation line to the Refueling Water Tank (RWT) safely during the present mode of operation. The flow rate using this path is at least 750 gpm. The flowmeter on this line has an accuracy of +/- 5.0%, which is the best that can presently be achieved given the piping 2
Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii) geometry and technological limitations of the equipment available. The comprehensive pump test reference flow is 1040 gpm.
The pump will be run for a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period at normal recirculation flow (approximately 130 gpm) to verify acceptable seal operation. The oil will then be changed and the pump will be run for another 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on the larger recirculation flow path of at least 750 gpm. The oil will then be changed a second time and the pump will be run for another 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on the larger recirculation flow path to provide additional assurance of trouble free operation. Vibration data will be collected at initial start-up after stable flow conditions are achieved. During the subsequent pump runs data will be collected in the same manner.
The vibration data will be analyzed to ensure there are no indications of unacceptable pump performance and to ensure that the performance data is within the expected range. This will provide assurance that the equipment will continue to be operationally ready for the duration of the Unit 3 fuel cycle. During the next Unit 3 refueling outage, the comprehensive pump test will be run in*
accordance with ISTB-3310.
During the operating cycle, the quarterly Group B surveillance tests will be performed. Vibration data will be collected and spectrum analyses will be performed to provide assurance of continued pump operability.
- 6. Duration of Proposed Alternative The duration of the proposed alternative will be for the fifteenth operating cycle of PVNGS Unit 3.
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