|
---|
Category:Letter type:NRC
MONTHYEARNRC 2024-0007, Ile Post-Exam Submittal Letter2024-03-18018 March 2024 Ile Post-Exam Submittal Letter NRC-2024-0026, Ile Proposed Exam Submittal Letter2023-12-20020 December 2023 Ile Proposed Exam Submittal Letter NRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary 2024-03-18
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-03-25025 March 2019 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications NRC-2017-0012, Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result2017-02-24024 February 2017 Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach2016-06-17017 June 2016 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach NRC 2016-0015, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2016-04-0606 April 2016 Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report NRC 2014-0086, 10 CFR 50.46 30-Day Report2014-12-11011 December 2014 10 CFR 50.46 30-Day Report NRC 2014-0029, CFR 50.46 Annual Report/30-Day Report2014-04-18018 April 2014 CFR 50.46 Annual Report/30-Day Report NRC 2014-0012, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2014-02-13013 February 2014 Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report NRC 2013-0081, Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report2013-08-23023 August 2013 Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum2012-05-30030 May 2012 ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum NRC-2007-0055, Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.462007-07-0303 July 2007 Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.46 ML0508303282004-05-0606 May 2004 Event Notification 40728 for Point Beach NRC 2003-0042, Reporting of Fire Barriers Degraded for More than Seven Days2003-05-0909 May 2003 Reporting of Fire Barriers Degraded for More than Seven Days NRC 2002-0095, Reporting of Fire Barriers Degraded for More than Seven Days2002-10-22022 October 2002 Reporting of Fire Barriers Degraded for More than Seven Days NRC 2002-0083, Reporting of Fire Barriers Degraded for More than Seven Days2002-09-26026 September 2002 Reporting of Fire Barriers Degraded for More than Seven Days ML0307702772002-08-0707 August 2002 2-page Abnormal Occurrence Writeup for 11/29/2001 Event Potential Loss of All Auxiliary Feedwater at Point Beach Plant 2019-03-25
[Table view] Category:Written Event Report (30 or 60 day)
[Table view] |
Text
4 Nuclear Management Company, LLC Point Beach Nuclear Plant NaM C Committed to Nuclear Excellence 6610 Nuclear Road Two Rivers, WI 54241 NRC 2002-0083 10 CFR 50.48 September 26, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Dockets 50-266 and 50-301 Point Beach Nuclear Plant, Units 1 and 2 Reportinq Of Fire Barriers Degraded For More Than Seven Days Enclosed is a 30-day report for Point Beach Nuclear Plant (PBNP), Unit 1 and Unit 2. This report is provided in accordance with the PBNP Fire Protection Evaluation Report (FPER),
Section 8.1.5. That section requires the submittal of a report to the U. S. Nuclear Regulatory Commission when degradation of fire protection systems or components exceeds the time listed in FPER Section 8.1.3. Paragraph C.1.b(4) of that section requires a report if an inoperable fire barrier is not restored to an operable status within a seven day period.
As discussed in the enclosure to this letter, several potential fire barrier degradations have recently been identified which involved two fire doors, a spancrete ceiling slab, and six penetration seals. The barriers containing these components have been conservatively declared to be degraded for a period exceeding seven days. Appropriate compensatory measures have been initiated and will continue until corrective actions, as discussed in the enclosure to this letter, are completed.
This report contains no new commitments.
If you have any questions concerning our plans, please contact Norm Hoefert at 920-755-7590.
Sincere y, T. H. Taylor/
Plant Manager CWK/kmd Enclosure cc: NRC Regional Administrator NRC Project Manager NRC Resident Inspector PSCW
NRC 2002-0083 Enclosure Page 1 of 4 DEGRADED FIRE BARRIERS 30-DAY REPORT POINT BEACH NUCLEAR PLANT, UNITS I AND 2
. :11 NRC 2002-0083 Enclosure Page 2 of 4 Purpose This report is submitted in accordance with the PBNP Fire Protection Evaluation Report (FPER)
Section 8.1.5, "Reportability," which requires a report when specified fire protection features or equipment, including fire barriers and fire barrier components, are degraded or inoperable in excess of program requirements. As required by the FPER, this report includes a description of action(s) taken, or to be taken, the cause of the inoperability or degradation, and the plans and schedule for restoring the system to operable status.
The approved fire protection program described in the PBNP FPER, Section 8.1.1, "Applicability," specifies that fire protection components, which provide fire protection capability for equipment required for safe plant shutdown shall be operable whenever the equipment protected by the fire protection system is required to be operable. Fire barriers (Section 8.1.3.C) are included in the fire protection features identified in the FPER. PBNP Operations Manual procedure OM 3.27, "Control of Fire Protection and Appendix R Safe Shutdown Equipment," clarifies the requirement for fire barriers at Section 5.1.3. That procedure states that all fire barriers and fire barrier components (i.e. walls, floors and ceiling barriers, penetration seals, fire doors, fire dampers and electrical raceway fire barriers) protecting safe shutdown areas shall be operable. A fire barrier, penetration seal or other barrier component may be inoperable provided that:
"* The immediate area on each side of the fire barrier is inspected to assure that potential fire hazards are minimized,
"* Activities in the immediate area on each side of the fire barrier are restricted to that which is necessary for continued operation and to enable restoration of the barrier operability, and
"* An hourly fire watch inspection shall be performed on each side of the fire barrier.
Degradation of AFW Pump Room Tunnel Ceiling Assembly Description During performance of Nuclear Oversight (NOS) Assessment 2002-003-3, NMC engineers identified that the auxiliary feedwater (AFW) Pump Room Tunnel spancrete ceiling slab has through openings along its width. This called into question the ceiling slab's 3-hour fire barrier requirement. This ceiling construction provides 2-hour Underwriters Laboratories (UL) fire resistance and 3-hour Wisconsin Administrative Code fire resistance, provided the heat transmission requirements of ASTM E-1 19 may be reduced to /2 the hourly rating. Because this barrier was constructed in accordance with the state building code, it appears that this conditional statement was satisfied.
However, further evaluation of this assembly will be conducted to ensure that the above stated conditions were adequately met.
NRC 2002-0083 Enclosure Page 3 of 4 Immediate Actions Taken In accordance with FPER 8.1.3.C.1.b and OM 3.27, Section 5.1.3, an hourly fire watch inspection will continue to be preformed on each side of the fire barrier until the integrity of this barrier is restored or the barrier is determined to be adequate.
Plans and Schedule A condition evaluation of this issue has been conducted, which identified the need for further detailed evaluation. This evaluation will involve review of the original design to ascertain compliance during the installation of this barrier. Additionally, the existing configuration will be evaluated to determine the level of protection provided. Based on these evaluations the spancrete ceiling assembly will be determined acceptable as-is or restored to the appropriate fire resistance. This detailed engineering evaluation and the appropriate corrective actions should be completed by the end of January 2003.
Degradation of Fire Doors 148 & 156 Description During performance of Nuclear Oversight (NOS) Assessment 2002-003-3, NMC engineers identified that Class A (3-hr fire rated) doors 148 & 156 are equipped with window (lites) with a 1-hr fire rating. The presence of these lites in 3-hr fire rated doors degrades the integrity of the barrier within which they are installed.
Immediate Actions Taken In accordance with FPER 8.1.3.C.l.b and OM 3.27, Section 5.1.3, an hourly fire watch inspection will continue to be preformed on each side of the fire barrier until the integrity of this barrier is restored or the barrier is determined to be adequate.
Plans and Schedule A condition evaluation of this issue has been conducted resulting in the need to replace the doors containing 1-hr fire rated lites with new doors containing 3-hr fire rated lites.
Action to replace doors 148 and 156 is being conducted via work orders. This work should be completed by the end of February 2003.
Penetration Seals Identified with Documentation Deficiencies Description During performance of Nuclear Oversight (NOS) Assessment 2002-003-3 on Fire Protection (FP), supporting documentation for the qualification of six penetration seals selected during a plant walkdown could not be provided. The physical condition of the seals was good. There were no defects or damage observed on the seals selected.
The designation and location of the questioned seals are as follows:
M-5-4-21-S10 (through transom above Door 261 at PAB el 26', east entrance)
NRC 2002-0083 Enclosure Page 4 of 4 M-0-41-F45 (Area/Zone AO1-B/1 87, near column lines G/11, el 26ft)
M-3-5-14-N7 (Area/Zone AO1-B1/237, near column lines G/13, el 44ft)
M-7-4-45-C1 (Area/Zone A03/152, el 8ft, through ceiling of Charging Pump cubicle)
M-7-3-5-W3 (A23/304, thru west wall of AFP Room, in SW corner)
M-7-3-5-W2 (A23/304, thru west wall of AFP Room, in SW corner)
As mentioned above, documentation concerning the fire penetration seals is less than adequate. An engineering analysis of each of these seals is planned to be conducted to identify the typical detail that was used for their installation and ascertain compliance with the detail parameters. Additional engineering analysis will be conducted and/or fire test documentation acquired as necessary to properly qualify these seals.
Immediate Actions Taken In accordance with FPER 8.1.3.C.l.b and OM 3.27, Section 5.1.3, an hourly fire watch inspection will continue to be preformed on each side of the fire barrier until reasonable assurance can be provided that the fire rated capability of these penetration seals can be established or the penetrations be otherwise demonstrated as operable.
Plans and Schedule An engineering evaluation of these fire penetration seals is being conducted.
Completion of this activity should be accomplished by the end of February 2003.