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Category:Memoranda
MONTHYEARML22147A0932022-06-0606 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 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 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 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. Lee to M. 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. ML1020305002010-10-15015 October 2010 Summary of Tele Conf Call Held on 7/21/10, Btw the USNRC and Arizona Public Service Company, Concerning Draft Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal App ML1019401422010-10-15015 October 2010 July 8, 2010, Summary of Telephone Conference Call Held Between USNRC and Arizona Public Service Company Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1027801622010-10-13013 October 2010 9/15/10 Summary of Public Meeting to Discuss the Draft Supplemental Environmental Impact Statement for Palo Verde Nuclear Generating Station ML1028003402010-10-13013 October 2010 Final Response to Task Interface Agreement - Requirements for Degraded Voltage Relay Setpoints at Palo Verde Nuclear Generating Station (TIA 2010-005 ML1024303382010-10-0505 October 2010 Letter Summary of Telephone Conference Call Held on 8/31/10 Btw the USNRC and Arizona Public Service Company, Concerning Draft Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Lr ML1023102542010-08-24024 August 2010 Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement (Dseis) for Palo Verde Nuclear Generating Station ML1021606502010-08-0909 August 2010 Transmittal Letter Advisory Committee on Reactor Safeguards Review of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application - Safety Evaluation Report ML1017600272010-07-19019 July 2010 Summary of Telecon Calls Held on May 5, May 19, and June 16, 2010 Between the USNRC and Arizona Public Service Company, Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1013407882010-06-0202 June 2010 Summary of Tele Conf Call Held on 4/14/10, Btw USNRC and APS, Concerning D-RAI Pertaining to the PVNGS, Units 1,2 and 3, License Renewal Application ML1013302522010-06-0202 June 2010 4-13-2010, Telecon Summary Re Draft Request for Additional Information Pertaining to the License Renewal Application ML1013302862010-06-0202 June 2010 04/23/10 Summary of Telepone Conference Call Held Between NRC and Arizona Public Service Co., Concerning Palo Verde, Units 1, 2 & 3 License Renewal Application ML1013406662010-06-0202 June 2010 Summary of Tele Conf Call Held on 4/12/10, Btw the USNRC and APS, Concerning the PVNGS, Units 1, 2, and 3, License Renewal Application ML1013407042010-06-0202 June 2010 License Renewal, May 14, 2010 Conference Call Summary ML1010606402010-04-27027 April 2010 Summary of Tele Conference Call Held on 4/9/10, Btw the USNRC and Arizona Public Service Company, Concerning Draft Requests for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1,2, and 3, License Renewa ML1009804822010-04-20020 April 2010 05/06/10 Notice of Public Working Meeting with Arizona Public Service to Discuss Issues Related to the Palo Verde Nuclear Generating Station License Renewal Application 2022-06-06
[Table view] Category:MD 8.3 Reactive Inspection Evaluation
MONTHYEARML0627201202006-09-29029 September 2006 Management Directive 8.3 Evaluation for Palo Verde Nuclear Generating Station (PV 06-19) ML0422405792004-08-11011 August 2004 Management Direct 8.3 Evaluation for Palo Verde Nuclear Generating Station 2006-09-29
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August 11, 2004 MEMORANDUM TO: Arthur T. Howell, Director, Division of Reactor Projects FROM: Troy W. Pruett, Chief, Reactor Project Branch D /RA/
SUBJECT:
MANAGEMENT DIRECT 8.3 EVALUATION FOR PALO VERDE NUCLEAR GENERATING STATION Pursuant to Regional Office Policy Guide 0801, Documenting Management Directive 8.3 Reactive Team Inspection Decisions, the attached table provides the evaluation for determining that a special inspection should be conducted at the Palo Verde Nuclear Generating Station.
cc w/
Attachment:
B. Mallett, RIV D. Chamberlain, RIV V. Ordaz, RIV C. Marschall, RIV N. Salgado, RIV C. Paulk, RIV J. Clark, RIV M. Hay, RIV G. Miller, RIV J. Shea, NRR T. McMurtray, NRR R. Laura, NRR
Arthur T. Howell III ADAMS: W Yes G No Initials: __TWP__
W Publicly Available G Non-Publicly Available G Sensitive W Non-Sensitive R:\_MD8.3Decisions04-001.wpd ML042240579 RIV:SRA:DRS C:DRP/D D:DRP RBywater TPruett ATHowell III T- TWPruett /RA/ CSMarschall for 8/11/2004 8/6/2004 8/11/2004 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
MD 8.3 DECISION DOCUMENTATION FORM PLANT - Palo Verde Nuclear Generating Station EVENT DATE - July 29, 2004 RESPONSIBLE BRANCH CHIEF - Troy Pruett EVALUATION DATE - August 4, 2004 BRIEF DESCRIPTION OF THE SIGNIFICANT OPERATIONAL EVENT OR DEGRADED CONDITION - The internal volume of the emergency core cooling system (ECCS) piping sections between the closed inboard containment isolation valve and the sump recirculation check valves is void of water and occupied with air (115 cubic feet). Upon a recirculation actuation signal (RAS), the potential exists for the trapped air volume to be forced into the suction of the safety injection pumps. This action could lead to cavitation of the pumps, air binding, or a water hammer event.
The licensee completed a Froude correlation and determined that for a 24 inch diameter pipe, a volumetric flow rate of greater than 5200 gpm would be needed to relocate the air pocket from the horizontal run of piping and 8300 gpm for the vertical run of piping. The combined minimum flow to pump run-out flow for the high pressure safety injection and containment spray pumps is in the range of 4800 to 6900 gpm per recirculation train.
Therefore, the possibility exists that a significant portion of the total air volume could be drawn into the suction of the safety injection pumps as a diffused air/water mixture.
Y/N DETERMINISTIC CRITERIA No a. Involved operations that exceeded, or were not included in, the design bases of the facility Remarks - As of August 2, 2004, the licensee had not identified information associated with the acceptability of an air filled suction line from the containment sump.
Yes b. Involved a major deficiency in design, construction, or operation having potential generic safety implications Remarks - Key factors associated with a design deficiency involve the total volume of air, the expected flow rates of the safety injection pumps, and the size and orientation of the sump suction piping. This issue is applicable to plants with air voided suction lines.
No c. Led to a significant loss of integrity of the fuel, primary coolant pressure boundary, or primary containment boundary of a nuclear reactor - significant loss applies to each boundary.
Remarks - None Yes d. Led to the loss of a safety function or multiple failures in systems used to mitigate an actual event Remarks - On July 31, 2004, the licensee made a 50.72(b)(3)(v)(B) and (D) report due to a loss of safety function for residual heat removal and mitigating systems. Specifically, following a recirculation actuation signal, the safety functions associated with the high pressure safety injection and containment spray systems could be lost.
No e. Involved possible adverse generic implications
Remarks - None No f. Involved significant unexpected system interactions Remarks - None No g. Involved repetitive failures or events involving safety-related equipment or deficiencies in operations Remarks - None No h. Involved questions or concerns pertaining to licensee operational performance Remarks - None No x. Involved one or more of the radiological or materials criterion provided in MD 8.3 guidance Remarks - None
CONDITIONAL RISK ASSESSMENT IF IT IS DETERMINED THAT A RISK ANALYSIS IS NOT REQUIRED - ENTER NA BELOW AND CONTINUE TO THE DECISION BASIS BLOCK RISK ANALYSIS BY - Russ Bywater DATE - August 4, 2004 THE ESTIMATED CONDITIONAL CORE DAMAGE PROBABILITY (CCDP) IS 6E-5 AND PLACES THE RISK IN THE RANGE OF A SPECIAL OR AUGMENTED INSPECTION PROCEDURE.
The analyst modeled the degraded condition using the Palo Verde SPAR model assuming a loss of high and low pressure recirculation following a recirculation actuation signal. The condition was assumed to exist for a year with average test and maintenance. No operator recovery was credited and all accident initiators were considered. The core damage frequency result was 6E-5/yr. Since the condition was assumed to exist for a year, this result was directly comparable to the CCDP table in MD 8.3. The approach and results were confirmed by headquarters senior reactor analyst (SRA) Rick Rasmussen. The result was also consistent with the licensees result.
The NRC and licensee analysts results were reliant on the assumption that the air in the containment sump suction lines directly caused the pumps to fail. Therefore, the result of this analysis is considered an upper maximum bound. This is a critical assumption which will require engineering analysis of bubble transport and effect on pump performance.
Large early release was not considered as part of this analysis, but since the containment spray pumps also take suction from the sump following a RAS, containment spray pump performance and potential for containment failure should be considered during the followup inspection and significance determination process evaluation.
DECISION BASIS USING THE ABOVE INFORMATION AND OTHER KEY ELEMENTS OF CONSIDERATION, AS APPROPRIATE, THE BASIS FOR THE DECISION SHALL BE PROVIDED BELOW Details of the basis for the decision -
A special inspection for the review of air voiding in the emergency core cooling system piping between the containment sump and the safety injection pumps is warranted. The principle factor in favor of the special inspection involves the potential generic safety implications for the industry. No immediate safety concern exists given the licensees compensatory measures to fill the effected piping with borated water.
The special inspection should evaluate: (1) existing operating experience and compare the data to activities implemented at Palo Verde, (2) calculations used to evaluate the condition, (3) Technical Specification Implications, (4) compensatory measures implemented following discovery of the condition, and (5) circumstances associated with the influential assumptions in the risk analysis (degree to which the pumps are affected, recovery of failed pumps, and event sequences of concern).
COMPLETED BY - Troy Pruett DATE - August 5, 2004 BRANCH CHIEF REVIEW - Troy Pruett DATE - August 5, 2004 DIVISION DIRECTOR APPROVAL - Arthur T. Howell III DATE - August 11, 2004