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| {{#Wiki_filter:(DUJKE it c AL LM""W- &V wvt" j MOM : V, M"=F: so3W 131 Serial: RNP-RW1I3-(079 10 CFR 50.36 AUG`2- 12013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washikngton, ' 20565 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEW.ED LICENSE NO. DPR-23 TECHNICAL SPECIFICATIONS (TS) SECTION 5.8.6, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION REPORT, 14-DAY REPORT FOR THE INOPERABILITY OF THE WIDE RANGE CONAINMEN Pe8 SURE TRNSMITR Ladles and Gentlemen: | | {{#Wiki_filter:it AL c LM |
| Duke Energy Progress, Inc., kfomy known as Carolina Power and Light Company, Inc., hereby submb a report in accordance with H. B. Robinson Steam Electric Plant, Unit No. 2, Technical Specifications (TS) Section 3..33, P Aident Monitoring i mentn, and TS 5.4.6, Past Accddent Moitloring Instrumentation Report.The repg O*h~k-s provided as i t ftacinetofthiete, Is basedon theinoperability of the Wide Range Containment Pressure Tlansmitter. | | ""W- &V wvt" (DUJKE j MOM : V, M"= |
| The Wide Range Cont&ment Pressure Transmitter (PT)-5 will be post maintenance tested and retured to OPERABLE status prior to restart from the next refuelin outage, which is currently scheduled to begi on Septembor14, 2013, or during the first outage of sufficient duration.If you soul have any questions concerning fts matter, please contac Ricard Hightower, Supervso -Regulatory Affalre at (843) 857-1329.Sincerely, Sharon A. Wheeler-Peavyhouse Manager -Support Services -Nuclr Attachaent SWP/sc Mr. S. P. Ungavm, NRC rtlect Manager, NRR'3/4, NRC ResiderKt1tnspector | | F: so3W 131 Serial: RNP-RW1I3-(079 10 CFR 50.36 AUG`2- 12013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washikngton, ' 20565 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEW.ED LICENSE NO. DPR-23 TECHNICAL SPECIFICATIONS (TS) SECTION 5.8.6, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION REPORT, 14-DAY REPORT FOR THE INOPERABILITY OF THE WIDE RANGE CONAINMEN Pe8 SURE TRNSMITR Ladles and Gentlemen: |
| ~.......6/4-o/
| | Duke Energy Progress, Inc., kfomy known as Carolina Power and Light Company, Inc., |
| Unied Sta. Nucer Reatory CommISSon Attsachmet to Serial: RNP-RA1I3-0079 Page I of 2..RO1SO , STEA ELECTRIC PLANT, UNIT NO. 2 TECHNICAL SPECIFICAMIONS SECTION 6*1 POST ACCIDENT MONITORING INS UMENTATION 144DAY'EMR TM M, Bo M 99 MU COTEM RU MI TRAsNrIT-TE Event Description On July 17, 2013, Pressure Tranwsmtter (Pt)-968 was found out of tolerance during the performance of a Preventive Maintenance (PM) Procedure. | | hereby submb a report in accordance with H. B. Robinson Steam Electric Plant, Unit No. 2, Technical Specifications (TS) Section 3..33, P Aident Monitoring i mentn, and TS 5.4.6, Past Accddent Moitloring Instrumentation Report. |
| The as found voltage reading should have been 42 VDC +/- 1 Volt and the AC Ripple Voltage should have been less than 20mVAC. During the perfrance of the PM the as found readings were 56.84 VDC and the AC Ripple Voltage was 61.18mVAC. | | The repg O*h~k-s provided asi t ftacinetofthiete, Isbasedon theinoperability of the Wide Range Containment Pressure Tlansmitter. |
| It was determined that PT-956 was out of tolerance due to a faulty power supply which has been replaced. | | The Wide Range Cont&ment Pressure Transmitter (PT)-5 will be post maintenance tested and retured to OPERABLE status prior to restart from the next refuelin outage, which is currently scheduled to begi on Septembor14, 2013, or during the first outage of sufficient duration. |
| However, because of the complexity of the post maintenance test to determine OPERABILITY of PT-956 it is preferred that the test be scheduled to be completed during the Refuellng Out4iiagecrrety scheduled to star on Septembe 14, 2013.The actions for Technical Specifications (TS) Section 3.3.3, Post Accident Mnftrn (PAM)Instrumentation, Table 3.3.3-1, Function 8, requires an Inoperable containment prosur monitoring channel to be restored to OPERABLE status within 30 days. If this indication Is not restoredwIthin 30 days, a report in accordance with TS 5.6.6 Is required within the following 14 days. TS 5.6.6 states that the report shall quftine the preplanned alternate method of mitoring, the camu of the lnoperabiltyk ,and th plansand schedule for restoring the channel to operable status. The Plant Nuclear Safety Committee (PNSC) will review the Corrective Action Program investigation for this event in aocordance with the Updated Flnal Safety Analysis Repot requirements for PNSC review of reportab events.Pleplanned Alternate Mthod of Monitorin Standing Instruction 13-012, effective 08/05/2013 for PT-956, Containment Vessel (CV) Wide Range Pressure Transmitter, outlines the alternate meh of monitoring oontainment pressure until PT-956 Is returned to service: Hourly Monfto Capabt:* Average Containment Pressure hourly via ERFIS Point CVP0001 Event Based Monitoring Capability" Pressure Indicator (PQ)-957, CV Wide Range Pressure (Post Accident Monitoring Panel)" PI-950, 951,952, 953, 954, and 955 Safeguards Containment Pressure (Reactor and Turbine Generator Board (RTGB)) | | If you soul have any questions concerning fts matter, please contac Ricard Hightower, Supervso - Regulatory Affalre at (843) 857-1329. |
| United States Nuclear Regulatory Commission Attachment to Serial: RNP-RN13-0079 Page 2 of 2 These indications are Vernded hourly or periodically on the RTGB, and as triggered by an event by the control room operators. | | Sincerely, Sharon A. Wheeler-Peavyhouse Manager - Support Services - Nuclr Attachaent SWP/sc Mr. S. P. Ungavm, NRC rtlect Manager, NRR |
| Annunciators are also available to alert the Control Room to adverse CV pressure conditions. | | '3/4, NRC ResiderKt1tnspector ~ |
| Should any of these indications fagl, a work order will be Initiated and worked on an emergent basis to ensure that the back-up methods for monitoring remain In place.The TS Bases for TS 3.3.3, as it pertains to the wide range containment pressure monitoring channels, states: "Contalnment Pressure (Wide Range) Is provided for verification of RCS and containment OPERABILITY. | | ....... 6 |
| Containment pressure is used to provide indication of whether the overall containment cooling function provided by containment spray and fan coolers is being achieved. | | /4-o/ |
| Containment pressure Is also used to verify the Containment Pressure-High SI signal and the Containment Pressure-High High Spray and Steam Line Isolation Signals." As stated in the TS Bases for TS 3.3.3, the wide range containment pressure monitoring channels provide a verification Indication. | | |
| This monitoring capability does not directly Impact safety systems or the ability to mitigate the consequences of an accident.Cause of the n r y This event has been entered into the H. 8. Robinson Steam Electric Plant, Unit No. 2, Corrective Action Program. The cause of the PT-956 inoperability was an out of tolerance power supply voltage. The power supply has been replaced, but the wide range containment pressure monitoring channel associated with this pressure transmitter cannot be confirmed OPERABLE until a Local Leak Rate Test (LLRT) can be performed. | | Unied Sta. Nucer Reatory CommISSon Attsachmet to Serial: RNP-RA1I3-0079 Page I of 2 |
| Plan and Schedule for Reetorn the Channe The PT-956 wide range containment pressure monitoring channel cannot be calibrated without removing two (2) channels of containment pressure from service to perform the LLRT, hence, it is preferable that this calibration be done while the unit is offline for refueling. | | . . RO1SO STEA, ELECTRIC PLANT, UNIT NO. 2 TECHNICAL SPECIFICAMIONS SECTION 6*1 POST ACCIDENT MONITORING INS UMENTATION 144DAY' |
| Therefore, PT-956 wide range containment pressure monitoring transmitter will be Local Leak Rate Tested and calibrated prior to restart from the next refueling outage, which is currently scheduled to begin on September 14, 2013, or during the first outage of sufficient duration.}} | | -Rm* EMR TM M, Bo M COTEM 99 MU RU MI TRAsNrIT-TE Event Description On July 17, 2013, Pressure Tranwsmtter (Pt)-968 was found out of tolerance during the performance of a Preventive Maintenance (PM) Procedure. The as found voltage reading should have been 42 VDC +/- 1 Volt and the AC Ripple Voltage should have been less than 20mVAC. During the perfrance of the PM the as found readings were 56.84 VDC and the AC Ripple Voltage was 61.18mVAC. |
| | It was determined that PT-956 was out of tolerance due to a faulty power supply which has been replaced. However, because of the complexity of the post maintenance test to determine OPERABILITY of PT-956 it is preferred that the test be scheduled to be completed during the Refuellng Out4iiagecrrety scheduled to star on Septembe 14, 2013. |
| | The actions for Technical Specifications (TS) Section 3.3.3, Post Accident Mnftrn (PAM) |
| | Instrumentation, Table 3.3.3-1, Function 8, requires an Inoperable containment prosur monitoring channel to be restored to OPERABLE status within 30 days. If this indication Is not restoredwIthin 30 days, a report in accordance with TS 5.6.6 Is required within the following 14 days. TS 5.6.6 states that the report shall quftine the preplanned alternate method of mitoring, the camu of the lnoperabiltyk,and th plansand schedule for restoring the channel to operable status. The Plant Nuclear Safety Committee (PNSC) will review the Corrective Action Program investigation for this event in aocordance with the Updated Flnal Safety Analysis Repot requirements for PNSC review of reportab events. |
| | Pleplanned Alternate Mthod of Monitorin Standing Instruction 13-012, effective 08/05/2013 for PT-956, Containment Vessel (CV) Wide Range Pressure Transmitter, outlines the alternate meh of monitoring oontainment pressure until PT-956 Is returned to service: |
| | Hourly Monfto Capabt: |
| | * Average Containment Pressure hourly via ERFIS Point CVP0001 Event Based Monitoring Capability |
| | " Pressure Indicator (PQ)-957, CV Wide Range Pressure (Post Accident Monitoring Panel) |
| | " PI-950, 951,952, 953, 954, and 955 Safeguards Containment Pressure (Reactor and Turbine Generator Board (RTGB)) |
| | |
| | United States Nuclear Regulatory Commission Attachment to Serial: RNP-RN13-0079 Page 2 of 2 These indications are Vernded hourly or periodically on the RTGB, and as triggered by an event by the control room operators. Annunciators are also available to alert the Control Room to adverse CV pressure conditions. Should any of these indications fagl, a work order will be Initiated and worked on an emergent basis to ensure that the back-up methods for monitoring remain In place. |
| | The TS Bases for TS 3.3.3, as it pertains to the wide range containment pressure monitoring channels, states: |
| | "Contalnment Pressure (Wide Range) Is provided for verification of RCS and containment OPERABILITY. |
| | Containment pressure is used to provide indication of whether the overall containment cooling function provided by containment spray and fan coolers is being achieved. Containment pressure Is also used to verify the Containment Pressure-High SI signal and the Containment Pressure-High High Spray and Steam Line Isolation Signals." |
| | As stated in the TS Bases for TS 3.3.3, the wide range containment pressure monitoring channels provide a verification Indication. This monitoring capability does not directly Impact safety systems or the ability to mitigate the consequences of an accident. |
| | Cause of the n r y This event has been entered into the H. 8. Robinson Steam Electric Plant, Unit No. 2, Corrective Action Program. The cause of the PT-956 inoperability was an out of tolerance power supply voltage. The power supply has been replaced, but the wide range containment pressure monitoring channel associated with this pressure transmitter cannot be confirmed OPERABLE until a Local Leak Rate Test (LLRT) can be performed. |
| | Plan and Schedule for Reetorn the Channe The PT-956 wide range containment pressure monitoring channel cannot be calibrated without removing two (2) channels of containment pressure from service to perform the LLRT, hence, it is preferable that this calibration be done while the unit is offline for refueling. Therefore, PT-956 wide range containment pressure monitoring transmitter will be Local Leak Rate Tested and calibrated prior to restart from the next refueling outage, which is currently scheduled to begin on September 14, 2013, or during the first outage of sufficient duration.}} |
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Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. 2021-02-18
[Table view] Category:Report
MONTHYEARRA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022 Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2021-11-22022 November 2021 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) IR 05000261/20210052021-08-25025 August 2021 Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005) RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)2017-08-15015 August 2017 Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) ML16281A5102016-12-15015 December 2016 Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors ML16280A2002016-10-0505 October 2016 Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P2016-05-0404 May 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.462015-11-17017 November 2015 Annual Report of Changes Pursuant to 10 CFR 50.46 ML15280A1992015-10-19019 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)2015-08-19019 August 2015 Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04) RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel2015-02-26026 February 2015 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System2014-04-0808 April 2014 Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System RNP-RA/14-0012, Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3....2014-03-12012 March 2014 Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3.... RNP-RA/14-0011, Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2014-02-27027 February 2014 Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident ML13365A2912014-02-19019 February 2014 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14027A0632014-01-24024 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for H. B. Robinson Steam Electric Plant, Unit 2, TAC No.: MF0720 ML13267A2122013-09-30030 September 2013 Enclosure 1, Transition Report - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML13270A1762013-09-24024 September 2013 Redacted - Office of Nuclear Reactor Regulation (NRR) Reactor Systems Branch (Srxb) Support of Region II Inspection of H. B. Robinson Treatment of Voids in Systems That Are Important to Safety RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter2013-08-21021 August 2013 Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication2013-06-24024 June 2013 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 20122013-04-25025 April 2013 Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012 ML12331A1752012-11-26026 November 2012 Draft Bypass Fiber Quantity Test Plan ML12278A3992012-08-31031 August 2012 WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant ML1210707162012-05-17017 May 2012 Letter Report on the Evaluation of Cables from the HEAF Fire Event at the H.B. Robinson Steam Electric Plant ML12068A1332012-02-23023 February 2012 Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System2011-11-23023 November 2011 Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System ML1124113592011-09-23023 September 2011 Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling ML1124113582011-09-23023 September 2011 Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance ML1128005282010-12-29029 December 2010 NRC 2011 Hb Robinson ML1019304172010-05-0606 May 2010 Tritium Database Report RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.2009-07-31031 July 2009 WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation2009-06-19019 June 2009 Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 2024-06-28
[Table view] Category:Miscellaneous
MONTHYEARRA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2021-11-22022 November 2021 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) IR 05000261/20210052021-08-25025 August 2021 Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005) RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) ML16281A5102016-12-15015 December 2016 Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.462015-11-17017 November 2015 Annual Report of Changes Pursuant to 10 CFR 50.46 ML15280A1992015-10-19019 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)2015-08-19019 August 2015 Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04) RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel2015-02-26026 February 2015 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System2014-04-0808 April 2014 Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System RNP-RA/14-0012, Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3....2014-03-12012 March 2014 Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3.... RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter2013-08-21021 August 2013 Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication2013-06-24024 June 2013 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 20122013-04-25025 April 2013 Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012 RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System2011-11-23023 November 2011 Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System ML1124113582011-09-23023 September 2011 Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance ML1124113592011-09-23023 September 2011 Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling ML1128005282010-12-29029 December 2010 NRC 2011 Hb Robinson ML1019304172010-05-0606 May 2010 Tritium Database Report RNP-RA/08-0026, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-03-0707 March 2008 Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors RNP-RA/06-0062, Groundwater Protection - Data Collection Questionnaire2006-07-24024 July 2006 Groundwater Protection - Data Collection Questionnaire RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure2006-07-17017 July 2006 Request for Technical Specifications, Change Related to Containment Peak Pressure RA-05-0104, Transmittal of Core Operating Limits Report2005-10-10010 October 2005 Transmittal of Core Operating Limits Report ML0414602462004-05-19019 May 2004 Q Report for Period Ending 03/31/2004 ML0324716322003-08-22022 August 2003 Submittal of 10-Q Report ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys ML0317000272003-06-0606 June 2003 Submittal of 10-O Report RNP-RA/02-0028, Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval2002-03-26026 March 2002 Request for Technical Specifications Change Re One-Time Extension of Containment Type a Test Interval 2021-08-25
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F: so3W 131 Serial: RNP-RW1I3-(079 10 CFR 50.36 AUG`2- 12013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washikngton, ' 20565 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEW.ED LICENSE NO. DPR-23 TECHNICAL SPECIFICATIONS (TS) SECTION 5.8.6, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION REPORT, 14-DAY REPORT FOR THE INOPERABILITY OF THE WIDE RANGE CONAINMEN Pe8 SURE TRNSMITR Ladles and Gentlemen:
Duke Energy Progress, Inc., kfomy known as Carolina Power and Light Company, Inc.,
hereby submb a report in accordance with H. B. Robinson Steam Electric Plant, Unit No. 2, Technical Specifications (TS) Section 3..33, P Aident Monitoring i mentn, and TS 5.4.6, Past Accddent Moitloring Instrumentation Report.
The repg O*h~k-s provided asi t ftacinetofthiete, Isbasedon theinoperability of the Wide Range Containment Pressure Tlansmitter.
The Wide Range Cont&ment Pressure Transmitter (PT)-5 will be post maintenance tested and retured to OPERABLE status prior to restart from the next refuelin outage, which is currently scheduled to begi on Septembor14, 2013, or during the first outage of sufficient duration.
If you soul have any questions concerning fts matter, please contac Ricard Hightower, Supervso - Regulatory Affalre at (843) 857-1329.
Sincerely, Sharon A. Wheeler-Peavyhouse Manager - Support Services - Nuclr Attachaent SWP/sc Mr. S. P. Ungavm, NRC rtlect Manager, NRR
'3/4, NRC ResiderKt1tnspector ~
....... 6
/4-o/
Unied Sta. Nucer Reatory CommISSon Attsachmet to Serial: RNP-RA1I3-0079 Page I of 2
. . RO1SO STEA, ELECTRIC PLANT, UNIT NO. 2 TECHNICAL SPECIFICAMIONS SECTION 6*1 POST ACCIDENT MONITORING INS UMENTATION 144DAY'
-Rm* EMR TM M, Bo M COTEM 99 MU RU MI TRAsNrIT-TE Event Description On July 17, 2013, Pressure Tranwsmtter (Pt)-968 was found out of tolerance during the performance of a Preventive Maintenance (PM) Procedure. The as found voltage reading should have been 42 VDC +/- 1 Volt and the AC Ripple Voltage should have been less than 20mVAC. During the perfrance of the PM the as found readings were 56.84 VDC and the AC Ripple Voltage was 61.18mVAC.
It was determined that PT-956 was out of tolerance due to a faulty power supply which has been replaced. However, because of the complexity of the post maintenance test to determine OPERABILITY of PT-956 it is preferred that the test be scheduled to be completed during the Refuellng Out4iiagecrrety scheduled to star on Septembe 14, 2013.
The actions for Technical Specifications (TS) Section 3.3.3, Post Accident Mnftrn (PAM)
Instrumentation, Table 3.3.3-1, Function 8, requires an Inoperable containment prosur monitoring channel to be restored to OPERABLE status within 30 days. If this indication Is not restoredwIthin 30 days, a report in accordance with TS 5.6.6 Is required within the following 14 days. TS 5.6.6 states that the report shall quftine the preplanned alternate method of mitoring, the camu of the lnoperabiltyk,and th plansand schedule for restoring the channel to operable status. The Plant Nuclear Safety Committee (PNSC) will review the Corrective Action Program investigation for this event in aocordance with the Updated Flnal Safety Analysis Repot requirements for PNSC review of reportab events.
Pleplanned Alternate Mthod of Monitorin Standing Instruction 13-012, effective 08/05/2013 for PT-956, Containment Vessel (CV) Wide Range Pressure Transmitter, outlines the alternate meh of monitoring oontainment pressure until PT-956 Is returned to service:
Hourly Monfto Capabt:
- Average Containment Pressure hourly via ERFIS Point CVP0001 Event Based Monitoring Capability
" Pressure Indicator (PQ)-957, CV Wide Range Pressure (Post Accident Monitoring Panel)
" PI-950, 951,952, 953, 954, and 955 Safeguards Containment Pressure (Reactor and Turbine Generator Board (RTGB))
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RN13-0079 Page 2 of 2 These indications are Vernded hourly or periodically on the RTGB, and as triggered by an event by the control room operators. Annunciators are also available to alert the Control Room to adverse CV pressure conditions. Should any of these indications fagl, a work order will be Initiated and worked on an emergent basis to ensure that the back-up methods for monitoring remain In place.
The TS Bases for TS 3.3.3, as it pertains to the wide range containment pressure monitoring channels, states:
"Contalnment Pressure (Wide Range) Is provided for verification of RCS and containment OPERABILITY.
Containment pressure is used to provide indication of whether the overall containment cooling function provided by containment spray and fan coolers is being achieved. Containment pressure Is also used to verify the Containment Pressure-High SI signal and the Containment Pressure-High High Spray and Steam Line Isolation Signals."
As stated in the TS Bases for TS 3.3.3, the wide range containment pressure monitoring channels provide a verification Indication. This monitoring capability does not directly Impact safety systems or the ability to mitigate the consequences of an accident.
Cause of the n r y This event has been entered into the H. 8. Robinson Steam Electric Plant, Unit No. 2, Corrective Action Program. The cause of the PT-956 inoperability was an out of tolerance power supply voltage. The power supply has been replaced, but the wide range containment pressure monitoring channel associated with this pressure transmitter cannot be confirmed OPERABLE until a Local Leak Rate Test (LLRT) can be performed.
Plan and Schedule for Reetorn the Channe The PT-956 wide range containment pressure monitoring channel cannot be calibrated without removing two (2) channels of containment pressure from service to perform the LLRT, hence, it is preferable that this calibration be done while the unit is offline for refueling. Therefore, PT-956 wide range containment pressure monitoring transmitter will be Local Leak Rate Tested and calibrated prior to restart from the next refueling outage, which is currently scheduled to begin on September 14, 2013, or during the first outage of sufficient duration.