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Category:Memoranda
MONTHYEARML24297A6392024-10-30030 October 2024 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21061A3202021-03-10010 March 2021 Summary of February 25, 2021, Public Meeting with Nuclear Energy Institute to Further Discuss the Inclusion of TSTF-425 Under the Risk-Informed Process for Evaluations Initiative ML21006A3242021-01-0707 January 2021 Approval of the Risk-Informed Process for Evaluations ML19120A1972019-04-26026 April 2019 Memo to File Environmental Assessment and Finding of No Significant Impact for Arizona Public Service Company'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 73.30(b) and 10 CFR 72.30(c) for Palo Verde ISFSI ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML17128A4522017-05-0808 May 2017 Lessons Learned from Modeling the Flex Steam Generator Feed Pump for Palo Verde Nuclear Generating Station ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 ML17027A2842017-01-27027 January 2017 Charter for the NRC Special Inspection Team at Palo Verde Nuclear Generating Station-Review of Licensee Actions Related to the Failure of the Unit 3 Train B Emergency Diesel Generator ML17018A1232017-01-17017 January 2017 Management Directive 8.3 Evaluation for Palo Verde Unit 3 Emergency Diesel Generator Failure ML17003A0832017-01-0303 January 2017 Safety Evaluation Input Regarding Changes to Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML17004A2092017-01-0303 January 2017 Safety Evaluation Input for Palo Verde Nuclear Generating Station, Unit 3, Llcense Amendment Request for a One-Time Extension of the 3B Emergency Diesel Generator Completion Time ML17003A3892017-01-0303 January 2017 Safety Evaluation Input Regarding the Palo Verde Nuclear Generating Station Unit 3 Emergency Request to Extend Diesel Generator 3B Completion Time ML16358A4152016-12-23023 December 2016 Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15205A3602015-07-24024 July 2015 Assessment of Cyber Security Program Draft Temporary Instruction (Ti) Performed at Palo Verde Nuclear Generating Station ML15117A0422015-04-29029 April 2015 Memorandum to File Summarizing 4/24/15 Telephone Conference Granting Verbal Relief for Relief Request 53, Request for Approval of an Alternative to ASME Code, Section XI, Requirements for Flaw Removal ML14115A0452014-06-25025 June 2014 Issuance of Amendment Nos. 193, 193, and 193, Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 ML13238A0352014-04-22022 April 2014 Memo from P. 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Markley Palo Verde RAI Memorandum ML13330A5732013-12-0505 December 2013 Verbal Authorization of Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval ML13324A4942013-11-19019 November 2013 Deferral of Baseline Inspection Activities ML13294A3732013-10-21021 October 2013 11/4/13 Notice of Meeting with Arizona Public Service Company to Discuss Non-destructive Examination Efforts, Repairs, and Progress on Root Cause Identified During Inspection of Bottom-Mounted Instrumentation Nozzles at Palo Verde, Unit 3 ML13281A2032013-10-0909 October 2013 11/5/2013 Notice of Preapplication Meeting to Discuss License Amendment Request to Incorporate Nuclear Energy Institute NEI-11-04 Quality Assurance Program at Palo Verde, Units 1, 2, and 3 ML13199A0082013-07-22022 July 2013 Meeting Notice with Arizona Public Service Company Low Pressure Safety Injection Pump Single Failure Analysis for Minimum Required Refueling Water Tank Transfer Volume at Palo Verde, Units 1, 2, and 3 ML13154A4832013-06-0404 June 2013 Rai'S Following Ifib Analysis of Ap'S 2013 Decommissioning Funding Status Report for Palo Verde Units 1, 2 and 3 ML13143A0892013-05-23023 May 2013 Meeting Notice with Arizona Public Service Company to Discuss the U.S. Nuclear Regulatory Commission (NRC) Staff'S Draft Request for Additional Information Relating to the February 28, 2013, Submittal ML13105A0182013-05-16016 May 2013 Request for Additional Information Regarding APS Overall Integrated Plan in Response to Order EA-12-049 ML13127A2432013-05-0808 May 2013 5/29/13 Meeting Via Conference Call with Arizona Public Service Company to Discuss Palo Verde Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 (TAC ME8160-ME81 ML12227A8562012-08-17017 August 2012 Notice of Meeting with Arizona Public Service Company to Discuss Relief Request 48 - Alternative to ASME Section III, Phased Array Ultrasonic Examination Techniques for Palo Verde, Units 1, 2, and 3 ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1104604622011-02-15015 February 2011 Minutes Meeting of Palo Verde Nuclear Generating Station Units 1, 2, and 3 License Renewal Subcommittee, September 8, 2010, in Rockville, Maryland ML1030105232010-11-16016 November 2010 Summary of Teleconference Held on Between the U.S. NRC and Arizona Public Service Company, Concerning Draft Follow-Up Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2 and 3, LRA ML1029905302010-11-16016 November 2010 Summary of Telephone Conference Call Held on October 22, 2010, Btw the USNRC and Arizona Public Service Company, Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, LRA ML1030900182010-11-0505 November 2010 Notice of Meeting with Arizona Public Service Company to Discuss Palo Verde, Units 1, 2, and 3 License Amendment Request to Revise Technical Specification 3.7.4, Atmospheric Dump Valves. 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November 3, 2003 MEMORANDUM TO: Nancy L. Salgado, Senior Resident Inspector FROM: Arthur T. Howell III, Director, Division of Reactor Projects /RA/
SUBJECT:
CHARTER FOR THE NRC SPECIAL INSPECTION TEAM AT PALO VERDE NUCLEAR GENERATING STATION (PVNGS) -
REVIEW OF LICENSEE ACTIONS RELATED TO THE JULY 28 GRID DISTURBANCE AND CONSEQUENT TRIP OF UNIT 3 In response to our initial evaluation of impact of the July 28 grid disturbance, a Special Inspection Team is being chartered. The inspection team is being dispatched to better understand the response of all three units to the grid disturbance. You are hereby designated as the Special Inspection Team leader.
A. Basis On July 28, 2003, Unit 3 of the PVNGS tripped due to an offsite power perturbation caused by a maintenance error in a nearby electrical switchyard. On the basis of the offsite power configuration of the facility, all three units sensed the disturbance, but only Unit 3 tripped. Unit 3 reactor coolant pumps lost power during the transient, resulting in reduced reactor coolant system flow and the automatic reactor trip due to a low departure from nucleate boiling ratio. During restoration of forced flow, the licensee discovered that the third stage seal for Reactor Coolant Pump 2A was leaking. The grid disturbance also caused a loss of power and lock-out of instrument air compressors and normal chilled water chillers on Units 1, 2, and 3.
This significant operational event was evaluated for risk because: it potentially involved operations that did not meet the design basis as described in General Design Criteria 17; there are potential generic implications associated with the seal failure; there were potential unexpected system interactions in the form of loss of power and equipment lock-outs on all three units and anomalous turbine trip annunciation on Unit 1; and there may be design errors associated with the transmission system protective relaying.
The turbine trip/reactor trip that resulted from the loss of secondary power in Unit 3 on July 28, 2003, was an event of moderate risk significance. At the request of the NRC senior reactor analyst, the licensee evaluated the risk associated with this event and estimated the conditional core damage probability (CCDP) as 1.5E-5. As such, in accordance with Management Directive 8.3, either a special inspection or an augmented inspection is warranted.
Nancy L. Salgado We reviewed the characteristics for considering the formation of an incident investigation team (IIT) or an augmented inspection team (AIT) found in Management Directive 8.3. Our initial review concluded that this event did not meet the criteria for consideration of an IIT or AIT response. Office of Nuclear Reactor Regulation management has agreed that an AIT is not warranted. We have determined that a special inspection in accordance with Inspection Procedure 93812 is appropriate.
B. Scope Specifically, the team is expected to perform data gathering and fact-finding in order to address the following:
- 1. Develop a sequence of events related to the plant response to the July 28, 2003, grid disturbance.
- 2. Evaluate operator response to the trip. Specifically, evaluate human factor and procedural issues related to the measures necessary to restore power and return equipment to service, including the procedure to isolate control bleedoff when nuclear cooling water is lost to the reactor coolant pump seal packages. Confirm the adequacy of available staff and procedures.
- 3. Obtain the dominant cutsets from the Senior Reactor Analyst and evaluate the response and availability of risk significant mitigation equipment, including:
- a. The availability of the auxiliary feedwater system
- b. The adequacy of the protective relay schemes associated with the nonclass switchgear that deenergized during the trip
- 4. Evaluate the response of affected equipment. Develop a list of equipment that did not respond as designed, including:
- a. The seal package for Unit 3 Reactor Coolant Pump 2A
- b. The turbine trip annunciation on Unit 1
- 5. Evaluate the protective relay schemes related to the offsite power supplies to confirm compliance with General Design Criteria 17. Also review the adequacy of the protective relaying as it relates to preferentially tripping Unit 3, then Unit 2, then Unit 1 in response to grid disturbances.
- 6. Review the licensees posttrip review and root cause evaluation determination for independence, completeness, and accuracy, including the risk analysis of the event.
- 7. For identified failures and degradations, review the extent of the condition, potential generic implications, and the corrective actions proposed by the licensee.
Nancy L. Salgado 8. Review precursor events, if any, to assess the acceptability of the licensees previous corrective actions.
- 9. If any new information is identified that would affect the risk analysis, provide it to the Senior Reactor Analyst.
C. Team Members Nancy Salgado, Senior Resident Inspector (Team Leader)
Greg Warnick, Resident Inspector Joseph Taylor, Reactor Inspector D. Guidance Inspection Procedure 93812, "Special Inspection," provides additional guidance to be used by the inspection team.
This memorandum designates you as the Special Inspection Team leader. Your duties will be as described in Inspection Procedure 93812. The team composition will consist of yourself; Gregory Warnick, Resident Inspector, Project Branch D, Division of Reactor Projects; and Joseph Taylor, Reactor Inspector, Engineering and Maintenance Branch, Division of Reactor Safety. During performance of the Special Inspection, the designated team members are separated from normal duties and report directly to you.
You will continue to report to the Chief, Project Branch D and your normal duties will be performed by Jim Melfi, Resident Inspector, Project Branch D, Division of Reactor Projects.
The team is to emphasize fact-finding in its review of the circumstances surrounding the event. It is not the responsibility of the team to examine the regulatory process. Safety concerns identified that are not directly related to the event should be reported to the Region IV office for appropriate action.
The Team will report to the site, conduct an entrance meeting, and begin inspection on or before September 15, 2003. Related information that was gathered by the resident inspectors during initial followup of the grid disturbance and consequent Unit 3 trip will also be included in this inspection report as appropriate. Tentatively, the inspection should be completed by the close of business on September 19, 2003. A formal exit meeting will be scheduled following completion of the on-site inspection. A report documenting the results of the inspection will be issued within 30 days following the exit meeting. While the team is active, you will provide periodic status briefings to Region IV management.
This Charter may be modified should the team develop significant new information that warrants review. Should you have any questions concerning this Charter, contact me at (817) 860-8248.
Nancy Dockets: 50-528 50-529 50-530 Licenses: NPF-41 NPF-51 NPF-74 cc via E-mail:
T. Gwynn D. Chamberlain A. Howell G. Good C. Marschall L. Smith D. Powers N. Salgado J. Clark G. Warnick J. Melfi D. Loveless A. Boland, OEDO H. Berkow, NRR T. Reis, NRR
Nancy L. Salgado ADAMS: Yes
Publicly Available
- Sensitive Non-Sensitive S:\DRP\DRPDIR\CHARTER\PV AUGUST 2003.wpd RIV:SRI:DRP/A C:DRP/D D:DRP DPDIV:NRR ADRA NLSalgado;mjs LJSmith ATHowell HNBerkow DDChamberlain T - LJSmith /RA/ GMGood for E - LSmith /RA/
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