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| ==SUBJECT:== | | ==SUBJECT:== |
| POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, EVALUATION S OF CHANGES, TESTS, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS); 05000301/2012007(DRS) | | POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS); |
| | 05000301/2012007(DRS) |
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| ==Dear Mr. Meyer:== | | ==Dear Mr. Meyer:== |
| On May 3, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on May 3, 2012 , with you and other members of your staff | | On May 3, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on May 3, 2012, with you and other members of your staff. |
| . The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
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| | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| Based on the results of this inspection, no findings of significance were identified | | Based on the results of this inspection, no findings of significance were identified. |
| . In accordance with Title 10, Code of Federal Regulations (CFR), Part 50, Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC w ebsite at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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| | In accordance with Title 10, Code of Federal Regulations (CFR), Part 50, Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Sincerely, | | Sincerely, |
| /RA/ | | /RA/ |
| Hironori Peterson , Acting Chief Engineering Branch 3 Division of Reactor Safety Docket No s.: 50-266; 50-301 License No s.: DPR-24; DPR-27 | | Hironori Peterson, Acting Chief Engineering Branch 3 Division of Reactor Safety Docket Nos.: 50-266; 50-301 License Nos.: DPR-24; DPR-27 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000 266/20 12 0 07(DRS); 05000301/201 2007(DRS) w/Attachment: Supplemental Information | | Inspection Report 05000266/2012007(DRS); 05000301/2012007(DRS) |
| | w/Attachment: Supplemental Information |
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| REGION III Docket No s.: 50-266; 50-301 License No s.: DPR-24; DPR-27 Report No: | | REGION III== |
| 05000266/2012007(DRS); 05000301/2012007(DRS) | | Docket Nos.: 50-266; 50-301 License Nos.: DPR-24; DPR-27 Report No: 05000266/2012007(DRS); 05000301/2012007(DRS) |
| Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Unit s 1 and 2 Location: Two Rivers, WI Dates: April 16, 2012, through May 3, 201 2 Inspectors: | | Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: April 16, 2012, through May 3, 2012 Inspectors: Alan Dahbur, Senior Reactor Inspector (Lead) |
| Alan Dahbur, Senior Reactor Inspector (Lead) | | George Hausman, Senior Reactor Inspector Dariusz Szwarc, Reactor Inspector Approved by: Hironori Peterson, Acting Chief Engineering Branch 3 Division of Reactor Safety Enclosure |
| George Hausman , Senior Reactor Inspector Dariusz Szwarc | |
| , Reactor Inspector Approved by: | |
| Hironori Peterson , Acting Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure | |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000266/201 2007(DRS), 05000301/2012007(DRS) | | IR 05000266/2012007(DRS), 05000301/2012007(DRS); 04/16/2012 - 05/03/2012; Point Beach |
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| | Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications. |
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| ; 04/16/2012 - 05/03/2012; Point Beach Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.
| | This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. Based on the results of this inspection, no findings of significance were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, |
| | Revision 4, dated December 2006. |
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| This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. Based on the results of this inspection, no findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
| | ===NRC-Identified=== |
| -1649, "Reactor Oversight Process," Revision 4, dated December 2006. A. | | and Self-Revealed Findings |
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| ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== | | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== |
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| N RC-Identified and Self-Revealed Findings No significance f i n d i n g s were identified.
| | No significance findings were identified. |
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| B. No violations of significance were identified.
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| === | | ===Licensee-Identified Violations=== |
| Licensee-Identified Violations=== | |
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| 1. REACTOR SAFETY
| | No violations of significance were identified. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation=== | | ==REACTOR SAFETY== |
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| s of Changes, Tests, or Experiments and Permanent Plant Modifications
| | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== |
| | {{a|1R17}} |
| | ==1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications== |
| | {{IP sample|IP=IP 71111.17}} |
| | ===.1 Evaluation of Changes, Tests, or Experiments=== |
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| ===.1 === | | ====a. Inspection Scope==== |
| {{IP sample|IP=IP 71111.17}}
| | From April 16, 2012, through May 3, 2012, the inspectors reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 16 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. |
| a. Evaluation of Changes, Tests, or Experiments From April 16, 2012, through May 3, 2012, the inspectors reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 1 6 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
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| Inspection Scope the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; the safety issue requiring the change, tests or experiment was resolved; the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 1 0 CFR 50.59; and the design and licensing basis documentation was updated to reflect the change.
| | The inspectors reviewed these documents to determine if: |
| | * the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required; |
| | * the safety issue requiring the change, tests or experiment was resolved; |
| | * the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and |
| | * the design and licensing basis documentation was updated to reflect the change. |
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| The inspectors used, in part, Nuclear Energy Institute (NEI)96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, " | | The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments. |
| 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments." | |
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| This inspection constituted seven samples of evaluations a nd 1 6 samples of changes as defined in IP 71111.17-04. b. No findings of significance were identified. | | This inspection constituted seven samples of evaluations and 16 samples of changes as defined in IP 71111.17-04. |
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| Findings | | ====b. Findings==== |
| | No findings of significance were identified. |
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| ===.2 a. Permanent Plant Modifications=== | | ===.2 Permanent Plant Modifications=== |
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| From April 16, 2012, through May 3, 2012, the inspectors reviewe d eight permanent plant modifications that had been installed in the plant during the last three years. Inspection Scope | | ====a. Inspection Scope==== |
| | From April 16, 2012, through May 3, 2012, the inspectors reviewed eight permanent plant modifications that had been installed in the plant during the last three years. |
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| 3 Enclosure This review included in-plant walkdowns for portions of the emergency diesel generators G-01 and G-02 heat exchanger s replacement modification; the removal of boric acid heat trace equipment; the removal of racks RK
| | This review included in-plant walkdowns for portions of the emergency diesel generators G-01 and G-02 heat exchangers replacement modification; the removal of boric acid heat trace equipment; the removal of racks RK-52J and RK-52-L and reroute of transformer 1X04 low voltage side power cables modification. The modifications were selected based upon risk-significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if: |
| -52J and RK L and reroute of transformer 1X04 low voltage side power cables modification | | * the supporting design and licensing basis documentation was updated; |
| . The modifications were selected based upon risk | | * the changes were in accordance with the specified design requirements; |
| -significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if: | | * the procedures and training plans affected by the modification have been adequately updated; |
| the supporting design and licensing basis documentation was updated; the changes were in accordance with the specified design requirements; the procedures and training plans affected by the modification have been adequately updated; the test documentation as required by the applicable test programs has been updated; and post-modification testing adequately verified system operability and/or functionality. | | * the test documentation as required by the applicable test programs has been updated; and |
| | * post-modification testing adequately verified system operability and/or functionality. |
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| The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report. | | The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report. |
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| This inspection constitut ed eight permanent plant modification samples as defined in IP 71111.17-04. b. No findings of significance were identified. | | This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04. |
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| Findings | | ====b. Findings==== |
| | No findings of significance were identified. |
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| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES (OA)== |
| (OA) | |
| {{a|4OA2}} | | {{a|4OA2}} |
| ==4OA2 == | | ==4OA2 Problem Identification and Resolution== |
| ===.1 Problem Identification and Resolution===
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| a. Routine Review of Condition Reports From April 16, 2012, through May 3, 2012, the inspectors reviewe d various corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to evaluations of changes, tests, or experiments and permanent p lant modifications. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the Attachment to this report.
| | ===.1 Routine Review of Condition Reports=== |
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| Inspection Scope b. No findings of significance were identified. | | ====a. Inspection Scope==== |
| | From April 16, 2012, through May 3, 2012, the inspectors reviewed various corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to evaluations of changes, tests, or experiments and permanent plant modifications. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the Attachment to this report. |
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| Findings 4 Enclosure | | ====b. Findings==== |
| {{a|4OA5}} | | No findings of significance were identified. {{a|4OA5}} |
| ==4OA5 Power Uprate== | | ==4OA5 Power Uprate== |
| | {{IP sample|IP=IP 71004}} |
| | ===.1 Evaluation of Changes, Tests, or Experiments (2 Samples)=== |
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| ===.1 === | | ====a. Inspection Scope==== |
| {{IP sample|IP=IP 71004}}
| | The inspectors reviewed safety evaluations for those implemented for the extended power uprate. |
| a. Evaluation of Changes, Tests, or Experiments (2 Samples) The inspectors reviewed safety evaluations for those implemented for the extended power uprate
| | * Safety Evaluation 2011-003, Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent - Radiological Consequences; and |
| . | | * Safety Evaluation 2011-004, Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent - Ctmt Pressure and Temp. |
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| | ====b. Findings==== |
| | No findings of significance were identified. |
| | {{a|4OA6}} |
| | ==4OA6 Meetings== |
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| Inspection Scope Safety Evaluation 2011
| | ===.1 Exit Meeting Summary=== |
| -003 , "Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
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| - Radiological Consequences
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| "; and Safety Evaluation 2011
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| -004 , "Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
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| - Ctmt Pressure a n d Temp." b. No findings of significance were identified.
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| Findings
| | On May 3, 2012, the inspectors presented the inspection results to Mr. Meyer and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. |
| {{a|4OA6}}
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| ==4OA6 ==
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| ===.1 Meetings On May 3, 2012, the inspectors presented the inspection results to===
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| Mr. Meyer and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. Exit Meeting Summary ATTACHMENT:
| | ATTACHMENT: |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| Attachment
| | ==KEY POINTS OF CONTACT== |
| SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
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| T
| | Licensee |
| : [[contact::L. Meyer]], Site Vice President | | : [[contact::L. Meyer]], Site Vice President |
| Licensee
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| : [[contact::C. Trezise]], Engineering Director | | : [[contact::C. Trezise]], Engineering Director |
| : [[contact::P. Wild]], Design Engineering Manager | | : [[contact::P. Wild]], Design Engineering Manager |
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Line 158: |
| : [[contact::C. Ford]], Maintenance Supervisor | | : [[contact::C. Ford]], Maintenance Supervisor |
| : [[contact::J. Niffenegger]], Electrical Design Engineering | | : [[contact::J. Niffenegger]], Electrical Design Engineering |
| | Nuclear Regulatory Commission |
| : [[contact::S. Burton]], Senior Resident Inspector | | : [[contact::S. Burton]], Senior Resident Inspector |
| Nuclear Regulatory Commission
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| LIST OF ITEMS OPENED, CLOSED AND DISCUSS
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| ED None.Opened, Closed and Discussed
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| Attachment
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| LIST OF DOCUMENTS REVIEWED The following is a list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
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| CFR 50.59 EVALUATIONS
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| Number Description or Title
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| 2011-003 Date or Revision
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| Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
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| - Radiological Consequences
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| May 29, 2011 2011-00 4 Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
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| - Ctmt Pressure & Temp.
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| May 29, 2011 2009-009 EC 11682, Modifications for Flow Control to Prevent RHR Pump Excessive Flow with Containment Spray Aligned During the Recirculation Phase (Unit 1)
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| August 20, 2009
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| 2010-003 EC 15413 "Control Room Alternate Cooling"
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| November 1, 2010
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| 2009-014-02 Use of ECCS Suction Line Vent Valves Within Procedures 1
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| -TS-ECCS-002 Train A, 1
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| -TS-ECCS-002 Train B, 2
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| -TS-ECCS-002 Train A, 2
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| -TS-ECCS-002 Train B, OI
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| -128E and OI-129E June 10, 2010
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| 2010-002 Reroute of 1X04 Low Voltage Power Cables to FAÇADE
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| November 10, 2010
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| 2011-001 1A-01 and 1A-02 Loss of Voltage Relay Setpoint Changes
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| April 13, 2011
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| CFR 50.59 SCREENINGS
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| Number Description or Title
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| 201 0-0 24 3 Date or Revision
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| NAMS E C 263219 Temporary Re location of the H
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| Supp l y (formerly
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| E C-16851) February 1, 2011 2011-0093 AST Related RWST EOP Setpoint
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| Changes May 28, 2011 2011-0332 Disable FS
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| -4909 & FS-4910 in Battery Rooms D
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| -105 & D-I06 December 13, 2011
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| 2010-0169 Change Stated Capacity of Relief Valve RH
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| -861C From 990 GPM to 1106 GPM in FSAR 9.2 per USAR 1149992
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| August 4, 2010
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| 2010-0152 Normal Ingress and Egress via HELB Barrier Doors
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| July 1, 2010
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| 2011-0061 Development of New Limiting Value of Full Stroke Time for 1SC-959 April 9, 2011
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| 2009-0186 Development of New Limiting Value of Full Stroke Time for 2RH-625 October 6, 2009
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| 2008-0163-02 EC 11683 - Modifications for Flow Control to Prevent RHR Pump Excessive Flow with Containment Spray Aligned During the Recirculation Phase
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| April 29, 2010
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| 2010-0170 Change to 2P
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| -10A RHR Pump IST Acceptance Criteria Based on Calculation 96
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| -0229 Revision
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| August 14, 2010 2010-0228 EC 14350 - Demolition of Boric Acid Heat Trace Circuitry
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| November 30, 2010
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| 2010-0145-01 Temporary Cooling for Unit 1 and Unit 2 Steam Generator Feed Pump Motors 1(2)P
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| -028A-M and 1(2)P
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| -028B-M July 14, 2010
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| 2009-0166 Install Test Switches for 4.16 KV Bus Loss of Voltage Relays
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| October 09, 2009
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| | ==LIST OF ITEMS== |
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| | ===OPENED, CLOSED AND DISCUSSED=== |
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| | Opened, Closed and |
| | ===Discussed=== |
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| | None. |
| Attachment | | Attachment |
| CFR 50.59 SCREENINGS
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| Number Description or Title
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| 2009-0196 Date or Revision
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| Temporary Power to B
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| -21 During 2B
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| -04 / 2B-03 Cross Tie Bus Inspection
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| October 23, 2009
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| 2011-0085 1/2 SI-860A/C Acceptance Criteria for Stroke Time to Closed Position May 11, 2011
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| 2010-0065 Revise the Pickup and Time Delay Tolerances for the 50D Protective Relays for 1(2) P
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| -15B Safety Injection Pumps in Calculation 2004
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| -009 and 1(2)RMP 9329
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| -2 June 15, 2010
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| 2010-0133 USAR 1167033 Reverse USAR 1145362
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| June 15, 2010
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| CALCULATIONS
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| Number Description or Title
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| 2000-0036 Date or Revision
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| ph of Post
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| -LOCA Sump and Containment Spray
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| May 19, 2011 2000-0036 ph of Post
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| -LOCA Sump and Containment Spray
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| May 28, 2011 2010-08891 Tube Freeze Calculation
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| December 29, 21 10 PBNP-IC-02 RWST Instrument Uncertainty/Setpoint Calculation, Section 8.1.66, Process Error
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| (PE) 4 WE-000 5-13 Evaluation of Heat Tracing for Appendix R Fire Protection Safe Shutdown
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| April 6, 1999 M-11165-112-RH.1 Relief Valve 1/2RH
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| -00861C Setpoint
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| and Capacity Determination
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| Revision 0
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| 96-0229 Minimum Allowable IST Acceptance Criteria for RHR Pump Performance
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| Revision 3
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| CORRECTIVE ACTION PROGRAM DOCUMENTS ISSUED DURING INSPECTION
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| Number Description or Title
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| 01762646 Date or Revision
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| 2012 Mod/50.59 Inspection SCR 2010
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| -0243 Clarification
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| May 2, 2012 01762041 0-SOP-VNCR-100 Ladder Label
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| May 1, 2012
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| 01759471 2012 Mod/50.59 Inspection Evaluation 2010
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| -002 Clarification
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| May 2, 2012
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| CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
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| Number Description or Title
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| 01328399 Date or Revision
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| RWST Temp Found High OOS on Logs Temp Found at 105 Degrees by PAB Operator
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| September 18, 2007 01655745 AST FSAR Update Deficiencies
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| July 30, 2011 01657526 AST - FSAR Change Request for Final Modification Configuration
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| May 15, 2012 01687323 Request to Add Ventilation Cross Connect Hoses Used by 0
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| -SOP-VNCR-100 to the Monthly Inventory
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| September 17, 2011 01394223 Revision to Calculation 96
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| -229 Affects IST AC
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| August 5, 2010
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| 01378236 NRC Inspection: TS Bases
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| 3.8.1 Not Supported by Calculation
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| December 4, 2009
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| 01671481 Multiple Inadequate 50.59 Screenings for EPU Unit 2 Modifications
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| July 22, 2011
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| Attachment
| | ==LIST OF DOCUMENTS REVIEWED== |
| CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
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| Number Description or Title
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| 01382670 Date or Revision
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| AR 01162577 Documents that the 50.59 Used to Support USAR Change 01145362 was Fatally Flawed
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| February 22, 2010 DRAWINGS Number Description or Title
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| MCVK000062
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| Date or Revision
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| P&ID Chemical & Volume Control Point Beach NP Unit 1
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| Revision E
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| L-23944-4 Assembly and Details of 20'
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| -0" I.D. x 24' High Over Str Shell Condensate Storage Tanks
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| Revision 6
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| 499B466 Sh.207 4160 Switchgear 2A01, Cub. 18 Bus Tie From 2A
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| -03 at 2A52-44 Revision 19
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| MODIFICATIONS
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| Number Description or Title
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| EC-263279 Date or Revision
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| Temporary Relocation of the H
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| Supply 0 EC 250861 G-01 and G-02 Emergency Diesel Generator Heat Exchanger Replacement (HX
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| -55A1/A2 and HX 55B1/B2)
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| June 27, 2007
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| EC 260778 Modification for Removal of Boric Acid Heat Trace Equipment and the Removal of Racks RK52
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| -J and RK52
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| -L for Access to Valves
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| Revision 0
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| EC 273685 Add Interposing Relays in the Starting Diesel Governor Pull-in Coil Circuit to Reduce Voltage Drop
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| September 2, 2011
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| EC 254337 Repower EDG
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| -01 Fuel Oil Valve FO
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| -3930 PROCEDURES
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| Number Description or Title
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| 0-SOP-VNBI-003 Date or Revision
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| White/Yellow Battery and Inverter Room Ventilation Normal Operation
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| ARB C01 B 1-9 PBNPP Alarm Response Procedure
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| - 1T13 RWST Low Level Alert
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| ARB C01 B 2-9 PBNPP Alarm Response Procedure
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| - 1T13 RWST Level
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| Low 5 ARB C01 B 3-9 PBNPP Alarm Response Procedure
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| - 1T13 RWST Level
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| Low-Low 5 REFERENCES
| |
| Number Description or Title
| |
| DG-I01 Date or Revision
| |
| Instrument Setpoint Methodology
| |
| Revision 6
| |
| Bulletin No.
| |
| L-151-B McDonnell No. AF1 Air Flow Switch for Duct Installations
| |
| 1973
| |
| Attachment
| |
| WORK ORDERS(WOs) Number Description or Title
| |
| 25352 Date or Revision
| |
| Need to Remove Debris from Bottom of [RWST] Tank
| |
| October 16, 1992 930474 In Support of U1R20, U1 RWST Mini
| |
| -SU March 26, 1993 9945054 1T-013 [RWST] Repair Weld
| |
| October 7, 2002 00267870 2T-013 [RWST] Inspect Tank Internals for Debris
| |
| October 30, 2006 00279479 1T-013 [RWST] Inspect Tank Internals for Debris
| |
| April 14, 2007 00380254 2T-013 [RWST] Inspect Tank Internals for Debris
| |
| March 19, 2011 00387773 1T-013 [RWST] Inspect Tank Internals for Debris
| |
| October 18, 2011
| |
| Attachment
| |
| LIST OF ACRONYMS USED ADAMS Agencywide Documents Access and Management System
| |
| AST Alternate Source Term
| |
| ATTN Attention BOP Balance of Plant
| |
| CARD Condition Assessment Resolution Document
| |
| CCDP Conditional Core Damage Probability
| |
| CFR Code of Federal Regulations
| |
| DRP Division of Reactor Project
| |
| DRS Division of Reactor Safety
| |
| EC Engineering Change
| |
| EDG Emergency Diesel Generator
| |
| EOP Emergency Operating Procedure
| |
| EPU Extended Power Uprate
| |
| EQ Environmental Qualification
| |
| FS Flow Switch
| |
| GPM Gallons Per Minute
| |
| HELB High Energy Line Break
| |
| HX Heat Exchanger
| |
| IMC Inspection Manual Chapter
| |
| IN Information Notice
| |
| IP Inspection Procedure
| |
| IR Inspection Report
| |
| NCV Non-Cited Violation
| |
| NEI Nuclear Energy Institute
| |
| NGR Neutral Grounding Resistor
| |
| NRC U.S. Nuclear Regulatory Commission
| |
| NSR Non-Safety-Related NUREG NRC Technical Report Designation
| |
| OLNC On-Line NobleChem
| |
| TM OOS Out-of-Service OPR Operability Recommendation
| |
| PARS Public Available Records System
| |
| PBNPP Point Beach Nuclear Power Plant
| |
| RHR Residual Heat Removal
| |
| RWST Refueling Water Storage Tank
| |
| SP Surveillance Procedure
| |
| TS Technical Specification
| |
| USAR Updated Safety Analysis Report
| |
| WO Work Order
| |
|
| |
|
| Mr. Larry Meyer
| |
| Senior Vice President
| |
| NextEra Energy Point Beach, LLC
| |
| 6610 Nuclear Road Two Rivers, WI 54241
| |
| SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS); 05000301/2012007 (DRS) Dear Mr. Meyer:
| |
| On May 3, 2012, the
| |
| : [[contact::U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes]], Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The
| |
| enclosed inspection report documents the inspection results which were discussed on May 3, 2012, with you and other members of your staff
| |
| . The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your
| |
| license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
| |
| Based on the results of this inspection, no findings of significance were identified
| |
| . In accordance with Title 10, Code of Federal Regulations
| |
| (CFR), Part
| |
| 50, Section
| |
| 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS)
| |
| component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
| |
| -rm/adams.html
| |
| (the Public Electronic Reading Room).
| |
| Sincerely, /RA/ Hironori Peterson, Acting Chief
| |
| Engineering Branch
| |
| Division of Reactor Safety
| |
| Docket Nos.: 50
| |
| -266; 50-301 License Nos.: DPR-24; DPR-27 Enclosure:
| |
| Inspection Report 05000266/2012007(DRS); 05000301/2012007(DRS) w/Attachment: Supplemental Information
| |
| cc w/encl:
| |
| Distribution via ListServŽ
| |
|
| |
| }} | | }} |
|
|---|
Category:Inspection Report
MONTHYEARIR 05000266/20240032024-11-0505 November 2024
Integrated Inspection Report 05000266/2024003 and 05000301/2024003
IR 05000266/20240112024-09-18018 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011
IR 05000266/20240052024-08-21021 August 2024
Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005)
IR 05000266/20240022024-08-13013 August 2024
Integrated Inspection Report 05000266/2024002 and 05000301/2024002
IR 05000266/20244012024-07-23023 July 2024
Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401
IR 05000266/20240102024-07-10010 July 2024
Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010
IR 05000266/20244202024-06-0505 June 2024
Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420
IR 05000266/20243012024-04-29029 April 2024
NRC Initial License Examination Report 05000266/2024301; 05000301/2024301
IR 05000266/20240012024-04-11011 April 2024
Integrated Inspection Report 05000266/2024001 and 05000301/2024001
IR 05000266/20230062024-02-28028 February 2024
Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006)
IR 05000266/20230042024-02-0101 February 2024
Integrated Inspection Report 05000266/2023004 and 05000301/2023004
IR 05000266/20234022023-11-14014 November 2023
Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402
IR 05000266/20230032023-10-16016 October 2023
Integrated Inspection Report 05000266/2023003 and 05000301/2023003
IR 05000266/20235012023-08-29029 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501
IR 05000266/20230052023-08-24024 August 2023
Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005)
IR 05000266/20230022023-07-18018 July 2023
Integrated Inspection Report 05000266/2023002 and 05000301/2023002
IR 05000266/20234012023-07-13013 July 2023
Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401
IR 05000266/20230012023-05-0101 May 2023
Integrated Inspection Report 05000266/2023001 and 05000301/2023001
IR 05000266/20233012023-03-28028 March 2023
NRC Initial Examination Report 05000266/2023301 and 05000301/2023301
IR 05000266/20220062023-03-0101 March 2023
Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022006 and 05000301/2022006)
IR 05000266/20230102023-02-23023 February 2023
Comprehensive Engineering Team Inspection Report 05000266/2023010 and 05000301/2023010
IR 05000266/20220042023-01-24024 January 2023
Integrated Inspection Report 05000266/2022004 and 05000301/2022004
ML23009B7002023-01-24024 January 2023
Review of the Spring 2022 Steam Generator Tub Inspections Report
IR 05000266/20224012022-12-0808 December 2022
Security Baseline Inspection Report 05000266/2022401 and 05000301/2022401
IR 05000266/20224042022-12-0202 December 2022
Cyber Security Inspection Report 05000266/2022404 and 05000301/2022404
IR 05000266/20220032022-11-0707 November 2022
Integrated Inspection Report 05000266/2022003 and 05000301/2022003
ML22298A2972022-10-27027 October 2022
Review of the Fall 2021 Steam Generator Tube Inspections Report
IR 05000266/20220122022-09-29029 September 2022
Biennial Problem Identification and Resolution Inspection Report 05000266/2022012 and 05000301/2022012
IR 05000266/20220052022-08-26026 August 2022
Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022005 and 05000301/2022005)
IR 05000266/20220112022-08-0303 August 2022
Triennial Fire Protection Inspection Report 05000266/2022011 and 05000301/2022011
IR 05000266/20220022022-07-27027 July 2022
Integrated Inspection Report 05000266/2022002 and 05000301/2022002
IR 05000266/20220012022-05-0404 May 2022
Integrated Inspection Report 05000266/2022001 and 05000301/2022001
IR 05000266/20210062022-03-0202 March 2022
Annual Assessment Letter for Point Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021006 and 05000301/2021006)
IR 05000266/20220102022-02-0909 February 2022
Design Basis Assurance Inspection (Programs) Inspection Report 05000266/2022010 and 05000301/2022010
IR 05000266/20210042022-01-28028 January 2022
Integrated Inspection Report 05000266/2021004 and 05000301/2021004 and Exercise of Enforcement Discretion
IR 05000266/20214022021-11-10010 November 2021
Security Baseline Inspection Report 05000266/2021402 and 05000301/2021402
IR 05000266/20210032021-10-20020 October 2021
Integrated Inspection Report 05000266/2021003 and 05000301/2021003
IR 05000266/20215012021-10-0505 October 2021
Emergency Preparedness Biennial Exercise Inspection Report 05000266/2021501 and 05000301/2021501
IR 05000266/20213012021-09-14014 September 2021
NRC Initial License Examination Report 05000266/2021301; 05000301/2021301, and 07200005/2021301
IR 05000266/20210052021-09-0101 September 2021
Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021005 and 05000301/2021005)
IR 05000266/20214032021-08-0404 August 2021
Security Baseline Inspection Report 05000266/2021403 and 05000301/2021403
IR 05000266/20210022021-07-29029 July 2021
Integrated Inspection Report 05000266/2021002, 05000301/2021002, and 07200005/2021001
IR 05000266/20210102021-07-0101 July 2021
Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000266/2021010 and 05000301/2021010
IR 05000266/20210012021-04-21021 April 2021
Integrated Inspection Report 05000266/2021001 and 05000301/2021001
IR 05000266/20214012021-03-16016 March 2021
Security Baseline Inspection Report 05000266/2021401; 05000301/2021401; Independent Spent Fuel Storage Security Inspection Report 07200005/2021401
IR 05000266/20200062021-03-0404 March 2021
Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020006 and 05000301/2020006)
IR 05000266/20200902021-02-0909 February 2021
Final Significance Determination of a Green Finding; NRC Inspection Report 05000266/2020090 and 05000301/2020090
IR 05000266/20200042021-02-0808 February 2021
Integrated Inspection Report 05000266/2020004 and 05000301/2020004
IR 05000266/20204022020-12-14014 December 2020
Security Baseline Inspection Report 05000266/2020402 and 05000301/2020402
IR 05000266/20200032020-11-0404 November 2020
Integrated Inspection Report 05000266/2020003 and 05000301/2020003
2024-09-18
[Table view]
Category:Letter
MONTHYEARIR 05000266/20240032024-11-0505 November 2024
Integrated Inspection Report 05000266/2024003 and 05000301/2024003
ML24295A1142024-10-31031 October 2024
Suppl Env Audit Summary Letter W/Enclosure 1
L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024
Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
ML24295A0862024-10-21021 October 2024
Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002
L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024
Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)
L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes
L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024
Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)
L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024
LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000266/20240112024-09-18018 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024
Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency
ML24207A0202024-08-28028 August 2024
Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301)
IR 05000266/20240052024-08-21021 August 2024
Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005)
IR 05000266/20240022024-08-13013 August 2024
Integrated Inspection Report 05000266/2024002 and 05000301/2024002
L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024
Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
ML24214A3092024-08-0202 August 2024
Confirmation of Initial License Examination
L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024
License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections
ML24194A1802024-07-24024 July 2024
– Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000266/20244012024-07-23023 July 2024
Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024
Preparation and Scheduling of Operator Licensing Examinations
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
IR 05000266/20240102024-07-10010 July 2024
Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010
L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024
License Amendment Request 300, Modify Containment Average Air Temperature Requirements
L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024
Schedule for Subsequent License Renewal Environmental Review
ML24176A2242024-06-24024 June 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024
Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision
IR 05000266/20244202024-06-0505 June 2024
Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420
ML24149A1922024-05-28028 May 2024
Notification of NRC Baseline Inspection and Request for Information
ML24141A1382024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000266/20243012024-04-29029 April 2024
NRC Initial License Examination Report 05000266/2024301; 05000301/2024301
L-2024-067, Annual Monitoring Report2024-04-26026 April 2024
Annual Monitoring Report
ML24116A0402024-04-23023 April 2024
Periodic Update of the Updated Final Safety Analysis Report
ML24071A0912024-04-22022 April 2024
Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval
IR 05000266/20240012024-04-11011 April 2024
Integrated Inspection Report 05000266/2024001 and 05000301/2024001
L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024
Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements
L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024
Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules
L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024
And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
IR 05000266/20230062024-02-28028 February 2024
Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006)
ML24053A3732024-02-22022 February 2024
Operator Licensing Examination Approval Point Beach, March 2024
L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024
Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections
ML24036A2652024-02-0505 February 2024
Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010
IR 05000266/20230042024-02-0101 February 2024
Integrated Inspection Report 05000266/2023004 and 05000301/2023004
ML24030A0352024-01-30030 January 2024
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
2024-09-09
[Table view] |
Text
May 10, 2012
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, EVALUATIONS OF CHANGES, TESTS, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS);
05000301/2012007(DRS)
Dear Mr. Meyer:
On May 3, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on May 3, 2012, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with Title 10, Code of Federal Regulations (CFR), Part 50, Section 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Hironori Peterson, Acting Chief Engineering Branch 3 Division of Reactor Safety Docket Nos.: 50-266; 50-301 License Nos.: DPR-24; DPR-27
Enclosure:
Inspection Report 05000266/2012007(DRS); 05000301/2012007(DRS)
w/Attachment: Supplemental Information
REGION III==
Docket Nos.: 50-266; 50-301 License Nos.: DPR-24; DPR-27 Report No: 05000266/2012007(DRS); 05000301/2012007(DRS)
Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: April 16, 2012, through May 3, 2012 Inspectors: Alan Dahbur, Senior Reactor Inspector (Lead)
George Hausman, Senior Reactor Inspector Dariusz Szwarc, Reactor Inspector Approved by: Hironori Peterson, Acting Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000266/2012007(DRS), 05000301/2012007(DRS); 04/16/2012 - 05/03/2012; Point Beach
Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. Based on the results of this inspection, no findings of significance were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 4, dated December 2006.
NRC-Identified
and Self-Revealed Findings
No significance findings were identified.
Licensee-Identified Violations
No violations of significance were identified.
REPORT DETAILS
REACTOR SAFETY
1R17 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications
Main article: IP 71111.17
.1 Evaluation of Changes, Tests, or Experiments
a. Inspection Scope
From April 16, 2012, through May 3, 2012, the inspectors reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed 16 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary.
The inspectors reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issue requiring the change, tests or experiment was resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
This inspection constituted seven samples of evaluations and 16 samples of changes as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
.2 Permanent Plant Modifications
a. Inspection Scope
From April 16, 2012, through May 3, 2012, the inspectors reviewed eight permanent plant modifications that had been installed in the plant during the last three years.
This review included in-plant walkdowns for portions of the emergency diesel generators G-01 and G-02 heat exchangers replacement modification; the removal of boric acid heat trace equipment; the removal of racks RK-52J and RK-52-L and reroute of transformer 1X04 low voltage side power cables modification. The modifications were selected based upon risk-significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification have been adequately updated;
- the test documentation as required by the applicable test programs has been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report.
This inspection constituted eight permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA2 Problem Identification and Resolution
.1 Routine Review of Condition Reports
a. Inspection Scope
From April 16, 2012, through May 3, 2012, the inspectors reviewed various corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to evaluations of changes, tests, or experiments and permanent plant modifications. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
4OA5 Power Uprate
.1 Evaluation of Changes, Tests, or Experiments (2 Samples)
a. Inspection Scope
The inspectors reviewed safety evaluations for those implemented for the extended power uprate.
- Safety Evaluation 2011-003, Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent - Radiological Consequences; and
- Safety Evaluation 2011-004, Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent - Ctmt Pressure and Temp.
b. Findings
No findings of significance were identified.
4OA6 Meetings
.1 Exit Meeting Summary
On May 3, 2012, the inspectors presented the inspection results to Mr. Meyer and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- L. Meyer, Site Vice President
- C. Trezise, Engineering Director
- P. Wild, Design Engineering Manager
- B. Woyak, Design Engineering Supervisor
- F. Hennessy, Excellence Manager
- B. Scherwinski, Licensing
- B. Hennessy, Licensing
- V. Kanal, Engineering Supervisor
- C. Ford, Maintenance Supervisor
- J. Niffenegger, Electrical Design Engineering
Nuclear Regulatory Commission
- S. Burton, Senior Resident Inspector
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed and
Discussed
None.
Attachment
LIST OF DOCUMENTS REVIEWED
