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| | number = ML102180239 | | | number = ML102180239 |
| | issue date = 08/05/2010 | | | issue date = 08/05/2010 |
| | title = Palo Verde - Followup of License Renewal Unresolved Item - Inspection Report 05000528; 05000529; 05000530-10-010 | | | title = Followup of License Renewal Unresolved Item - Inspection Report 05000528; 05000529; 05000530-10-010 |
| | author name = O'Keefe N F | | | author name = O'Keefe N |
| | author affiliation = NRC/RGN-IV/DRS/EB-2 | | | author affiliation = NRC/RGN-IV/DRS/EB-2 |
| | addressee name = Edington R K | | | addressee name = Edington R |
| | addressee affiliation = Arizona Public Service Co | | | addressee affiliation = Arizona Public Service Co |
| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES NUC LE AR RE G UL AT O RY C O M M I S S I O N ust 5, 2010 |
| [[Issue date::August 5, 2010]]
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| Randall K. Edington, Executive Vice President, Nuclear/CNO Mail Station 7602 Arizona Public Service Company P.O. Box 52034, Mail Stop 7602 Phoenix, AZ 85072-2034
| | ==SUBJECT:== |
| | | PALO VERDE NUCLEAR GENERATING STATION - FOLLOWUP OF LICENSE RENEWAL UNRESOLVED ITEM - INSPECTION REPORT 05000528; 05000529; 05000530/2010010 |
| SUBJECT: PALO VERDE NUCLEAR GENERATING STATION - FOLLOWUP OF LICENSE RENEWAL UNRESOLVED ITEM - INSPECTION REPORT 05000528; 05000529; 05000530/2010010 | |
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| ==Dear Mr. Edington:== | | ==Dear Mr. Edington:== |
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| As a result of our review we have concluded that the accelerated reviews to identify the current condition of your structures and the changes that increased the frequency of monitoring of structures provided reasonable assurance that you had established processes that would manage the effects of aging of your structures. Further, we have concluded the failure of the metal enclosed bus ducts resulted in no required changes to your management programs. | | As a result of our review we have concluded that the accelerated reviews to identify the current condition of your structures and the changes that increased the frequency of monitoring of structures provided reasonable assurance that you had established processes that would manage the effects of aging of your structures. Further, we have concluded the failure of the metal enclosed bus ducts resulted in no required changes to your management programs. |
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's document system (ADAMS). ADAMS | | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (ADAMS). ADAMS |
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| Arizona Public Service Company - 2 - | | Arizona Public Service Company -2-is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |
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| Sincerely,/RA/ Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety | | Sincerely, |
| | | /RA/ |
| Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74 NRC Inspection Report 50-528; 50-529; 50-530/2010010 | | Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74 NRC Inspection Report 50-528; 50-529; 50-530/2010010 |
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| ===w/Attachment:=== | | ===w/Attachment:=== |
| Supplemental Information cc w/enclosure Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007 | | Supplemental Information |
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| Mr. Douglas K. Porter, Esq Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770
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| Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003
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| Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, AZ 85040 Mr. Dwight C. Mims Vice President Regulatory Affairs and Plant Improvement Palo Verde Nuclear Generating Station Mail Station 7605 P.O. Box 52034 Phoenix, AZ 85072-2034
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| Chairman, Board of Supervisors 301 W. Jefferson, 10 th Floor Phoenix, AZ 85040
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| Ronald A. Barnes, Director Regulatory Affairs Palo Verde Nuclear Generating Station MS 7638 P.O. Box 52034 Phoenix, AZ 85072-2034
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| Arizona Public Service Company - 3 -
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| Mr. Jeffrey T. Weikert Assistant General Counsel El Paso Electric Company Mail Location 167 123 W. Mills El Paso, TX 79901
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| Michael S. Green Senior Regulatory Counsel Pinnacle West Capital Corporation P.O. Box 52034, MS 8695 Phoenix, AZ 85072-2034
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| Mr. Eric Tharp Los Angeles Department of Water & Power Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100
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| Mr. James Ray Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224
| | REGION IV== |
| | | Docket: 05000528; 050000529; 05000530 License: NPF-41; NPF-51; NPF-74 Report: 05000528/2010010; 05000529/2010010; 05000530/2010010 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station Location: 5951 S. Wintersburg Rd Tonopah, Arizona Dates: May 1 through July 29, 2010 Inspector: G. Pick, Senior Reactor Inspector Approved By: Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety-1- Enclosure |
| Mr. Geoffrey M. Cook Southern California Edison Company 5000 Pacific Coast Hwy. Bldg. D21 San Clemente, CA 92672
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| Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251
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| Mr. Brian Almon Public Utility Commission William B. Travis Building P.O. Box 13326 Austin, TX 78701-3326
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| Environmental Program Manager City of Phoenix Office of Environmental Programs 200 West Washington Street Phoenix, AZ 85003
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| Mr. John C. Taylor Director, Nuclear Generation El Paso Electric Company 340 East Palm Lane, Suite 310 Phoenix, AZ 85004
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| Chief, Technological Hazards Branch FEMA Region IX 1111 Broadway, Suite 1200 Oakland, CA 94607-4052 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000528; 050000529; 05000530 License: NPF-41; NPF-51; NPF-74 Report: 05000528/2010010; 05000529/2010010; 05000530/2010010 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station Location: 5951 S. Wintersburg Rd Tonopah, Arizona Dates: May 1 through July 29, 2010 Inspector: G. Pick, Senior Reactor Inspector Approved By: Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000528/2010010; 05000529/2010010; 05000530/2010010; 05/01/2010 - 07/29/2010; Palo Verde Nuclear Generating Station, Followup of License Renewal Unresolved Items | | IR 05000528/2010010; 05000529/2010010; 05000530/2010010; 05/01/2010 - 07/29/2010; Palo |
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| The report covered a 3-month period of inoffice review and evaluation by a senior regional inspector. | | Verde Nuclear Generating Station, Followup of License Renewal Unresolved Items The report covered a 3-month period of inoffice review and evaluation by a senior regional inspector. |
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| ===A. NRC-Identified and Self-Revealing Findings=== | | ===NRC-Identified and Self-Revealing Findings=== |
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| ===Cornerstone: Mitigating Systems=== | | ===Cornerstone: Mitigating Systems=== |
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| No findings were identified. | | No findings were identified. |
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| ===B. Licensee-Identified Violations=== | | ===Licensee-Identified Violations=== |
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| No findings were identified. | | No findings were identified. |
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| ==4OA5 Other - License Renewal== | | ==4OA5 Other - License Renewal== |
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| ===.1 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-01:=== | | ===.1 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-01: Impact of=== |
| Impact of Recent Operating Experience on Metal-Enclosed Bus Program
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| | Recent Operating Experience on Metal-Enclosed Bus Program Subsequent to completing the onsite portion of the license renewal inspection, on March 7, 2010, Unit 1 tripped when a ground fault occurred on Bus 1E-NAN-A03 connecting the Nonclass 1E 13.8 kV Bus 1E-NAN-S01 to Breaker 1E-NAN-S03B. |
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| Subsequent to completing the onsite portion of the license renewal inspection, on March 7, 2010, Unit 1 tripped when a ground fault occurred on Bus 1E-NAN-A03 connecting the Nonclass 1E 13.8 kV Bus 1E-NAN-S01 to Breaker 1E-NAN-S03B. Because of heavy rains, water intruded past the cover protecting the nonsegregated bus. The applicant preliminarily concluded the fault resulted from an improperly installed bus duct cover and a breakdown in the Noryl insulation because of aging mechanisms.
| | Because of heavy rains, water intruded past the cover protecting the nonsegregated bus. The applicant preliminarily concluded the fault resulted from an improperly installed bus duct cover and a breakdown in the Noryl insulation because of aging mechanisms. |
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| The applicant had not completed their evaluation of this event, which included the cause(s). | | The applicant had not completed their evaluation of this event, which included the cause(s). |
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| This unresolved item is closed. | | This unresolved item is closed. |
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| ===.2 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-02:=== | | ===.2 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-02: Structures=== |
| Structures Monitoring Frequency and Scope
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| During the onsite inspection, the license renewal inspection team had identified concerns related to the proposed inspection frequency and scope of the structures inspections. The applicant had not established an inspection program that reflected the frequencies specified in American Concrete Institute 349.3R-96, "Evaluation of Existing Nuclear Safety-Related Concrete Structures," and NUREG-1801, "Generic Aging Lessons Learned (GALL) Report - Tabulation of Results," Volume 2, Revision 1. These standards specified that structures exposed to the elements and those inside primary containment should be inspected every 5 years, and that other interior structures should be inspected every 10 years. In addition, the license renewal inspection team had | | Monitoring Frequency and Scope During the onsite inspection, the license renewal inspection team had identified concerns related to the proposed inspection frequency and scope of the structures inspections. The applicant had not established an inspection program that reflected the frequencies specified in American Concrete Institute 349.3R-96, Evaluation of Existing Nuclear Safety-Related Concrete Structures, and NUREG-1801, Generic Aging Lessons Learned (GALL) Report - Tabulation of Results, Volume 2, Revision 1. These standards specified that structures exposed to the elements and those inside primary containment should be inspected every 5 years, and that other interior structures should be inspected every 10 years. In addition, the license renewal inspection team had |
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| concerns because the applicant had not completed a 100 percent inspection of all structures to establish a baseline for comparison to future inspection results. The applicant documented these concerns in Condition Report Disposition Request 3441953. | | concerns because the applicant had not completed a 100 percent inspection of all structures to establish a baseline for comparison to future inspection results. The applicant documented these concerns in Condition Report Disposition Request 3441953. |
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| In response to the team's concern, the applicant provided a supplemental response to Request for Additional Information B2.1.32-1, as documented in License Renewal Application Amendment 13, dated April 1, 2010. The applicant revised Commitment 34 in Table A.4-1, "License Renewal Commitments," to state that prior to the period of extended operation, the Palo Verde Structures Monitoring program will be enhanced to inspect structures within the scope of license renewal at 10-year intervals. The team concluded that the applicant had provided an appropriate response for internal structures, excluding primary containment. However, the team continued to have concerns with the applicant's assessment regarding external structures and structures inside containment and concerns with a lack of baseline inspection. | | In response to the teams concern, the applicant provided a supplemental response to Request for Additional Information B2.1.32-1, as documented in License Renewal Application Amendment 13, dated April 1, 2010. The applicant revised Commitment 34 in Table A.4-1, License Renewal Commitments, to state that prior to the period of extended operation, the Palo Verde Structures Monitoring program will be enhanced to inspect structures within the scope of license renewal at 10-year intervals. The team concluded that the applicant had provided an appropriate response for internal structures, excluding primary containment. However, the team continued to have concerns with the applicants assessment regarding external structures and structures inside containment and concerns with a lack of baseline inspection. |
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| During this inspection, the inspector reviewed the applicant's supplemental responses, reviewed corrective action documents and discussed plans for completing the baseline inspections with the applicant. | | During this inspection, the inspector reviewed the applicants supplemental responses, reviewed corrective action documents and discussed plans for completing the baseline inspections with the applicant. |
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| As reflected in Letter 102-06194, "Responses to April 28, 2010, Request for Additional Information (RAI) and Follow-up RAIs, for the Review of the PVNGS [Palo Verde Nuclear Generating Station] License Renewal Application, and License Renewal Application Amendment No. 15," dated May 21, 2010, the applicant revised their structures monitoring program commitment to inspect external structures and those structures inside containment at 5-year intervals with the exception of a specific list of nonsafety-related structures. The inspector found this response satisfied the original concerns regarding the inspection frequency. | | As reflected in Letter 102-06194, Responses to April 28, 2010, Request for Additional Information (RAI) and Follow-up RAIs, for the Review of the PVNGS [Palo Verde Nuclear Generating Station] License Renewal Application, and License Renewal Application Amendment No. 15, dated May 21, 2010, the applicant revised their structures monitoring program commitment to inspect external structures and those structures inside containment at 5-year intervals with the exception of a specific list of nonsafety-related structures. The inspector found this response satisfied the original concerns regarding the inspection frequency. |
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| The inspector reviewed the applicant's plans to complete the inspection and evaluation of their structures onsite prior to the period of extended operation. In Condition Report Disposition Request 3439970, the applicant established an action plan to inspect the remaining structures by the end of 2015. In addition, the applicant established a plan to complete a second 100 percent inspection of the onsite structures during the subsequent 10-year period that would end in 2025 prior to entry into the period of extended operation. | | The inspector reviewed the applicants plans to complete the inspection and evaluation of their structures onsite prior to the period of extended operation. In Condition Report Disposition Request 3439970, the applicant established an action plan to inspect the remaining structures by the end of 2015. In addition, the applicant established a plan to complete a second 100 percent inspection of the onsite structures during the subsequent 10-year period that would end in 2025 prior to entry into the period of extended operation. |
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| The inspector found that these corrective actions appropriately addressed the identified concerns. | | The inspector found that these corrective actions appropriately addressed the identified concerns. |
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| ===Exit Meeting Summary=== | | ===Exit Meeting Summary=== |
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| On July 29, 2010, the inspector presented the results of the in-office inspection of the structural inspection program reviews to Ms. A. Krainik, Project Manager, License Renewal and other members of the applicant's staff. The applicant acknowledged the issues presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified. | | On July 29, 2010, the inspector presented the results of the in-office inspection of the structural inspection program reviews to Ms. A. Krainik, Project Manager, License Renewal and other members of the applicants staff. The applicant acknowledged the issues presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified. |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ===Licensee Personnel=== | | ===Licensee Personnel=== |
| : [[contact::A. Krainik]], Project Manager, License Renewal | | : [[contact::A. Krainik]], Project Manager, License Renewal |
| : [[contact::F. Oreshack]], Licensing Engineer | | : [[contact::F. Oreshack]], Licensing Engineer |
| : [[contact::K. Schrecker]], Section Leader | | : [[contact::K. Schrecker]], Section Leader |
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| ==LIST OF ITEMS== | | ==LIST OF ITEMS== |
| CLOSED | | CLOSED |
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| ===Closed=== | | ===Closed=== |
| : 05000528, | | : 05000528, |
| : 05000529, | | : 05000529, URI Impact of Recent Operating Experience on |
| : [[Closes finding::05000530/FIN-2010007-01]] URI Impact of Recent Operating Experience on Metal-Enclosed Bus Program (Section 4OA5.1)
| | : 05000530/2010007-01 Metal-Enclosed Bus Program (Section 4OA5.1) |
| : 05000528, | | : 05000528, |
| : 05000529, | | : 05000529, URI Structures Monitoring Frequency and Scope |
| : [[Closes finding::05000530/FIN-2010007-02]] URI Structures Monitoring Frequency and Scope (Section 4OA5.2)
| | : 05000530/2010007-02 (Section 4OA5.2) |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| 4OA5.1 Impact of Recent Operating Experience on Metal Enclosed Bus Program Aging Management Program for Metal Enclosed Bus - B2.1.36, Revision 4
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| : Drawing
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| : LR-PVNGS-ELEC-E-MAA-001, "Main Single Line Diagram," Revision 0
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| : Significant Root Cause Investigation Report of the Unit 1 Calvert Bus 1ENANA03 Bus Failure and Reactor Trip
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| : Test Report
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| : APS-90390, "Testing of Sections of the 13.8kV Calvert 1E-NAN-A03 Bus and Insulation"
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| : 4OA5.2 Structures Monitoring Frequency and Scope Correspondence Letter 102-06194, "Responses to April 28, 2010, Request for Additional Information (RAI) and Follow-up RAIs, for the Review of the PVNGS [Palo Verde Nuclear Generating Station] License Renewal Application, and License Renewal Application Amendment No. 15," dated May 21, 2010
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| : Letter 102-06160, "Response to March 2, 2010, Request for Additional Information Regarding Settlement, Tendons, Liner, Water Structures, for the Review of the PVNGS License Renewal Application, and License Renewal Application Amendment No. 13," dated April 1, 2010
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| : Attachment Letter 102-06134, "Responses to December 29, 2009, Request for Additional Information Regarding the Aging Management Program (AMP) Audit for the Review of the PVNGS License Renewal Application, and License Renewal Application Amendment No. 9," dated February 19, 2010
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| ===Condition Report===
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| : Disposition Requests
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| : 3439969
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| : 3439970
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| : 3441953
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| ===Miscellaneous===
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| : ACI [American Concrete Institute] 349.3R-96, "Evaluation of Existing Nuclear Safety-Related Concrete Structures"
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| : ASTM C 33, "Standard Specification for Concrete Aggregates," Figure 1, "Location of Weathering Regions"
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| : NUREG-1801, "Generic Aging Lessons Learned (GALL) Report - Tabulation of Results," Volume 2, Revision 1
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| ===Procedure===
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| : 81DP-0ZZ01, "Civil System, Structure, and Component Monitoring Program," Revision 16
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 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 IR 05000528/20243012024-04-22022 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) ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) 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 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) IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 IR 05000528/20233012023-06-0505 June 2023 NRC Examination Report 05000528/2023301, 05000529/2023301 and 05000530/2023301 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 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) IR 05000528/20220062023-03-0101 March 2023 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Report 05000528/2022006, 05000529/2022006, and 05000530/2022006) IR 05000528/20234012023-02-27027 February 2023 NRC Security Inspection Report 05000528/2023401, 05000529/2023401, 05000530/2023401, and 07200044/2023401 (Full Report) IR 05000528/20220042023-01-30030 January 2023 Integrated Inspection Report 05000528/2022004 and 05000529/2022004 and 05000530/2022004 IR 05000528/20220102023-01-17017 January 2023 Design Basis Assurance Inspection (Teams) Inspection Report 05000528/2022010 and 05000529/2022010 and 05000530/2022010 IR 05000528/20220032022-10-24024 October 2022 Units, 1, 2 and 3 Integrated Inspection Report 05000528/2022003, 05000529/2022003, and 05000530/2022003 IR 05000528/20224032022-10-14014 October 2022 Security Baseline Inspection Report 05000528/2022403 and 05000529/2022403 and 05000530/2022403 IR 05000528/20220052022-08-23023 August 2022 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2022005 and 05000529/2022005 and 05000530/2022005) ML22235A6662022-08-23023 August 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000528/2022010, 05000529/2022010, and 05000530/2022010) and Request for Information IR 05000528/20224022022-08-0808 August 2022 Cover Letter Only - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 NRC Security Inspection Report 05000528 2022402, 05000529 2022402, 05000530 2022402, and 07200044 2022402 IR 05000520/20220022022-08-0505 August 2022 Integrated Inspection Report 05000528/2022002 and 05000529/2022002 and 05000520/2022002 IR 05000528/20223012022-06-21021 June 2022 NRC Examination Report 05000528/2022301, 05000529/2022301, and 05000530/2022301 IR 05000528/20220012022-05-0909 May 2022 Integrated Inspection Report 05000528/2022001, 05000529/2022001 and 05000530/2022001 ML22105A0512022-04-19019 April 2022 Review of the 2021 Steam Generator Tube Inspections During Refueling Outage 22 IR 05000528/20224202022-03-0808 March 2022 Security Baseline Inspection Report 05000528/2022420, 05000529/2022420 and 05000530/2022420, Cover Letter IR 05000528/20210062022-03-0202 March 2022 Annual Assessment Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021006, 05000529/2021006, and 05000530/2021006) IR 05000528/20210042022-02-0707 February 2022 Integrated Inspection Report 05000528/2021004, 05000529/2021004, and 05000530/2021004 IR 05000528/20210032021-11-12012 November 2021 Integrated Inspection Report 05000528/2021003, 05000529/2021003 and 05000530/2021003 IR 05000528/20210152021-10-27027 October 2021 Temporary Instruction 2515/194 Report 05000528/2021015 and 05000529/2021015 and 05000530/2021015 ML21273A3172021-10-0404 October 2021 Station. NON-SENSITIVE IR 05000528/20214042021-09-23023 September 2021 NRC Security Inspection Report 05000528/2021404, 05000529/2021404, 05000530/2021404 and 07200044/2021401 IR 05000528/20214012021-09-14014 September 2021 Security Baseline Inspection Report 05000528/2021401 and 05000529/2021401 and 05000530/2021401 IR 05000528/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021005, 05000529/2021005, and 05000530/2021005) IR 05000528/20210022021-08-0909 August 2021 Integrated Inspection Report 05000528/2021002, 05000529/2021002, and 05000530/2021002 and Exercise of Enforcement Discretion IR 07200044/20214012021-07-21021 July 2021 ISFSI, Information Request, Security Inspection Report 07200044/2021401 IR 05000528/20210142021-07-14014 July 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000528/2021014, 05000529/2021014 and 05000530/2021014 IR 05000528/20213012021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 IR 05000528/20214032021-05-28028 May 2021 Security Baseline Inspection Report 05000528/2021403; 05000529/2021403 and 05000530/2021403 (Public) IR 05000528/20210012021-05-12012 May 2021 PV 2021001, Palo Verde Nuclear Generating Station - Integrated Inspection Report 05000528/2021001 and 05000529/2021001 and 05000530/2021001 IR 05000528/20210122021-05-0404 May 2021 Triennial Fire Protection Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012 IR 05000528/20210102021-04-28028 April 2021 Biennial Problem Identification and Resolution Inspection Report 05000528/2021010 and 05000529/2021010 and 05000530/2021010 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 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) 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 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 ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 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 IR 05000528/20243012024-04-22022 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 ML24019A2012024-01-19019 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 05000528/20230102023-08-22022 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 2024-08-08
[Table view] |
Text
UNITED STATES NUC LE AR RE G UL AT O RY C O M M I S S I O N ust 5, 2010
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - FOLLOWUP OF LICENSE RENEWAL UNRESOLVED ITEM - INSPECTION REPORT 05000528; 05000529; 05000530/2010010
Dear Mr. Edington:
On July 29, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed review of two unresolved items documented in Inspection Report 05000528; 05000529; 05000530/2010007.
These unresolved items related to concerns regarding whether your staff had accounted for industry operating experience related to metal-enclosed bus ducts and the frequency and scope of your structures monitoring program. The enclosed report documents the inspection findings which were discussed with Ms. A. Krainik, Project Manager, License Renewal, and other members of your staff.
This inspection examined activities related to your application for a renewed license for Palo Verde Nuclear Generating Station. The inspection evaluated the completion of baseline structural inspections and the frequency for performing these inspections. In addition, the inspection evaluated whether a recent failure of your metal-enclosed bus ducts should have resulted in a change to your aging management programs. As part of the inspection, the NRC examined procedures and representative records and interviewed personnel.
As a result of our review we have concluded that the accelerated reviews to identify the current condition of your structures and the changes that increased the frequency of monitoring of structures provided reasonable assurance that you had established processes that would manage the effects of aging of your structures. Further, we have concluded the failure of the metal enclosed bus ducts resulted in no required changes to your management programs.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosure, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (ADAMS). ADAMS
Arizona Public Service Company -2-is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74 NRC Inspection Report 50-528; 50-529; 50-530/2010010
w/Attachment:
Supplemental Information
REGION IV==
Docket: 05000528; 050000529; 05000530 License: NPF-41; NPF-51; NPF-74 Report: 05000528/2010010; 05000529/2010010; 05000530/2010010 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station Location: 5951 S. Wintersburg Rd Tonopah, Arizona Dates: May 1 through July 29, 2010 Inspector: G. Pick, Senior Reactor Inspector Approved By: Neil O'Keefe, Chief Engineering Branch 2 Division of Reactor Safety-1- Enclosure
SUMMARY OF FINDINGS
IR 05000528/2010010; 05000529/2010010; 05000530/2010010; 05/01/2010 - 07/29/2010; Palo
Verde Nuclear Generating Station, Followup of License Renewal Unresolved Items The report covered a 3-month period of inoffice review and evaluation by a senior regional inspector.
NRC-Identified and Self-Revealing Findings
Cornerstone: Mitigating Systems
No findings were identified.
Licensee-Identified Violations
No findings were identified.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other - License Renewal
.1 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-01: Impact of
Recent Operating Experience on Metal-Enclosed Bus Program Subsequent to completing the onsite portion of the license renewal inspection, on March 7, 2010, Unit 1 tripped when a ground fault occurred on Bus 1E-NAN-A03 connecting the Nonclass 1E 13.8 kV Bus 1E-NAN-S01 to Breaker 1E-NAN-S03B.
Because of heavy rains, water intruded past the cover protecting the nonsegregated bus. The applicant preliminarily concluded the fault resulted from an improperly installed bus duct cover and a breakdown in the Noryl insulation because of aging mechanisms.
The applicant had not completed their evaluation of this event, which included the cause(s).
During this inspection, the inspector reviewed the laboratory evaluation report of the remaining portions of the bus duct and the applicants root cause evaluation report. The inspector interviewed the team leader and personnel responsible for the Metal-Enclosed Bus Aging Management Program.
The inspector concluded that the causes identified for the failure in this bus duct would not have changed the methods employed by the applicant to monitor for the effects of aging since aging was not a contributing cause of the fault. Further, from review of the root cause analysis report planned corrective actions, the inspector determined that the applicant had corrective maintenance work orders scheduled to be implemented during future refueling outages to replace the Noryl insulation.
This unresolved item is closed.
.2 (Closed) Unresolved Item 05000528; 05000529; 05000530/2010007-02: Structures
Monitoring Frequency and Scope During the onsite inspection, the license renewal inspection team had identified concerns related to the proposed inspection frequency and scope of the structures inspections. The applicant had not established an inspection program that reflected the frequencies specified in American Concrete Institute 349.3R-96, Evaluation of Existing Nuclear Safety-Related Concrete Structures, and NUREG-1801, Generic Aging Lessons Learned (GALL) Report - Tabulation of Results, Volume 2, Revision 1. These standards specified that structures exposed to the elements and those inside primary containment should be inspected every 5 years, and that other interior structures should be inspected every 10 years. In addition, the license renewal inspection team had
concerns because the applicant had not completed a 100 percent inspection of all structures to establish a baseline for comparison to future inspection results. The applicant documented these concerns in Condition Report Disposition Request 3441953.
In response to the teams concern, the applicant provided a supplemental response to Request for Additional Information B2.1.32-1, as documented in License Renewal Application Amendment 13, dated April 1, 2010. The applicant revised Commitment 34 in Table A.4-1, License Renewal Commitments, to state that prior to the period of extended operation, the Palo Verde Structures Monitoring program will be enhanced to inspect structures within the scope of license renewal at 10-year intervals. The team concluded that the applicant had provided an appropriate response for internal structures, excluding primary containment. However, the team continued to have concerns with the applicants assessment regarding external structures and structures inside containment and concerns with a lack of baseline inspection.
During this inspection, the inspector reviewed the applicants supplemental responses, reviewed corrective action documents and discussed plans for completing the baseline inspections with the applicant.
As reflected in Letter 102-06194, Responses to April 28, 2010, Request for Additional Information (RAI) and Follow-up RAIs, for the Review of the PVNGS [Palo Verde Nuclear Generating Station] License Renewal Application, and License Renewal Application Amendment No. 15, dated May 21, 2010, the applicant revised their structures monitoring program commitment to inspect external structures and those structures inside containment at 5-year intervals with the exception of a specific list of nonsafety-related structures. The inspector found this response satisfied the original concerns regarding the inspection frequency.
The inspector reviewed the applicants plans to complete the inspection and evaluation of their structures onsite prior to the period of extended operation. In Condition Report Disposition Request 3439970, the applicant established an action plan to inspect the remaining structures by the end of 2015. In addition, the applicant established a plan to complete a second 100 percent inspection of the onsite structures during the subsequent 10-year period that would end in 2025 prior to entry into the period of extended operation.
The inspector found that these corrective actions appropriately addressed the identified concerns.
This unresolved item is closed.
4OA6 Meetings
Exit Meeting Summary
On July 29, 2010, the inspector presented the results of the in-office inspection of the structural inspection program reviews to Ms. A. Krainik, Project Manager, License Renewal and other members of the applicants staff. The applicant acknowledged the issues presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- A. Krainik, Project Manager, License Renewal
- F. Oreshack, Licensing Engineer
- K. Schrecker, Section Leader
LIST OF ITEMS
CLOSED
Closed
- 05000528,
- 05000529, URI Impact of Recent Operating Experience on
- 05000530/2010007-01 Metal-Enclosed Bus Program (Section 4OA5.1)
- 05000528,
- 05000529, URI Structures Monitoring Frequency and Scope
- 05000530/2010007-02 (Section 4OA5.2)
LIST OF DOCUMENTS REVIEWED