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Category:Inspection Report
MONTHYEARIR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 IR 07200028/20220012022-12-15015 December 2022 Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report No. 07200028/2022001 IR 05000387/20224032022-11-29029 November 2022 Security Baseline Inspection Report 05000387/2022403 and 05000388/2022403 IR 05000387/20225012022-11-28028 November 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2022501 and 05000388/2022501 IR 05000387/20224042022-11-0909 November 2022 Cyber Security Inspection Report 05000387/2022404 and 05000388/2022404 (Cover Letter Only) IR 05000387/20220032022-11-0808 November 2022 Integrated Inspection Report 05000387/2022003 and 05000388/2022003 IR 05000387/20220132022-09-28028 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000387/2022013 and 05000388/2022013 IR 05000387/20220052022-08-31031 August 2022 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2022005 and 05000388/2022005) IR 05000387/20224012022-08-11011 August 2022 Material Control and Accounting Program Inspection Report 05000387/2022401 and 05000388/2022401 (Cover Letter Only) IR 05000387/20220102022-08-11011 August 2022 Biennial Problem Identification and Resolution Inspection Report 05000387/2022010 and 05000388/2022010 IR 05000387/20220022022-08-0404 August 2022 Integrated Inspection Report 05000387/2022002 and 05000388/2022002 IR 05000387/20220012022-05-0909 May 2022 Integrated Inspection Report 05000387/2022001 and 05000388/2022001 IR 05000387/20220112022-03-0707 March 2022 Post-Approval Site Inspection for License Renewal - Phase 2 Inspection Report 05000387/2022011 IR 05000387/20210062022-03-0202 March 2022 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2021006 and 05000388/2021006) IR 05000387/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000387/2022402 and 05000388/2022402 IR 05000387/20214032022-02-11011 February 2022 Cyber Security Problem Identification and Resolution Inspection Report 05000387/2021403 and 05000388/2021403 (Cover Letter Only) IR 05000387/20210042022-02-11011 February 2022 Integrated Inspection Report 05000387/2021004 and 05000388/2021004 IR 05000387/20210102021-12-13013 December 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000387/2021010 and 05000388/2021010 IR 05000387/20210112021-11-0404 November 2021 Temporary Instruction 2515/194 Inspection Report 05000387/2021011 and 05000388/2021011 IR 05000387/20210032021-11-0303 November 2021 Integrated Inspection Report 05000387/2021003 and 05000388/2021003 IR 05000387/20214012021-10-25025 October 2021 Security Baseline Inspection Report 05000387/2021401 and 05000388/2021401 IR 05000387/20214022021-09-23023 September 2021 Security Baseline Inspection Report 05000387/2021402 and 05000388/2021402 IR 05000387/20213012021-09-17017 September 2021 Initial Operator Licensing Examination Report 05000387/2021301 and 05000388/2021301 IR 05000387/20210052021-09-0101 September 2021 Updated Inspection Plan for the Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2021005 and 05000388/2021005) ML21224A2402021-08-24024 August 2021 Security Baseline Inspection Report Cover Letter 2021 FOF IR 05000387/20210022021-08-0404 August 2021 Integrated Inspection Report 05000387/2021002 and 05000388/2021002 IR 05000387/20210012021-05-0505 May 2021 Integrated Inspection Report 05000387/2021001 and 05000388/2021001 IR 05000388/20210122021-03-0404 March 2021 EA-20-131: Susquehanna Steam Electric Station, Unit 2 - NRC Investigation Report No. 1-2020-001 and NRC Inspection Report No. 05000388/2021012 IR 05000387/20200062021-03-0303 March 2021 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2020006 and 05000388/2020006) IR 05000387/20204032021-02-10010 February 2021 Cyber Security Problem Identification and Resolution Inspection Report 05000387/2020403 and 05000388/2020403 (Cover Letter Only) IR 05000387/20200042021-02-0808 February 2021 Integrated Inspection Report 05000387/2020004 and 05000388/2020004 IR 05000387/20205012020-11-18018 November 2020 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2020501 and 05000388/2020501 IR 05000387/20200032020-11-0505 November 2020 Integrated Inspection Report 05000387/2020003 and 05000388/2020003 IR 05000387/20200122020-10-27027 October 2020 Triennial Fire Protection Inspection Report 05000387/2020012 and 05000388/2020012 IR 05000387/20200052020-08-31031 August 2020 Updated Inspection Plan (Inspection Reports 05000387/2020005 and 05000388/2020005) IR 05000387/20200112020-08-18018 August 2020 Biennial Problem Identification and Resolution Inspection Report 05000387/2020011 and 05000388/2020011 IR 05000387/20200022020-08-11011 August 2020 Integrated Inspection Report 05000387/2020002 and 05000388/2020002 IR 05000387/20204012020-07-0202 July 2020 Security Baseline Inspection Report 05000387/2020401 and 05000388/2020401 2024-08-12
[Table view] Category:Letter
MONTHYEARIR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) 2024-08-12
[Table view] |
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{{#Wiki_filter:ber 14, 2014
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION - NRC INTEGRATED INSPECTION REPORT 05000387/2014004 AND 05000388/2014004 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Rausch:
On September 30, 2014, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Susquehanna Steam Electric Station (SSES) Units 1 and 2. The enclosed integrated inspection report documents the inspection results, which were discussed on October 9, 2014, with Mr. Jeffrey Helsel and other members of your staff.
This 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.
This report documents one self-revealing finding of very low safety significance (Green). If you contest the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at SSES. In addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC Senior Resident Inspector at SSES.
Additionally, the inspectors reviewed Unresolved Item 05000387/2012007-01, 05000388/2012007-01, which raised a concern as to whether PPLs method for testing the secondary containment boundary and the standby gas treatment system (SGTS) complied with the existing design and licensing bases. Following additional review of this concern, NRC staff concluded that this issue constituted a violation of NRC requirements, in that your implementation of the surveillance requirements of the plant technical specifications for Unit 1 and Unit 2 did not adequately demonstrate: (1) the quality of the secondary containment; and (2) that the limiting conditions for operation were met as required by Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c)(3). However, the NRC concluded that the cause of the issue of concern was not reasonably within PPLs ability to foresee and correct. Therefore, no performance deficiency associated with the violation was identified. The NRC performed a risk evaluation of the issue and determined it to be of very low safety significance (Green). Based on these facts, I have been authorized, after consultation with the Director, Office of Enforcement, and the Regional Administrator, to exercise enforcement discretion in accordance with Section 3.5 of the Enforcement Policy, and refrain from issuing enforcement for this violation.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records component of the NRCs Agencywide Documents Access Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Ho K. Nieh Division Director Division of Reactor Projects Docket Nos. 50-387; 50-388 License Nos. NPF-14, NPF-22
Enclosures:
Inspection Report 05000387/2014004 and 05000388/2014004 w/Attachment: Supplemental Information
REGION I==
Docket Nos: 50-387, 50-388 License Nos: NPF-14, NPF-22 Report Nos: 05000387/2014004 and 05000388/2014004 Licensee: PPL Susquehanna, LLC (PPL)
Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, Pennsylvania Dates: July 1, 2014 through September 30, 2014 Inspectors: J. Greives, Senior Resident Inspector T. Daun, Resident Inspector E. Burket, Emergency Preparedness Inspector J. Cherubini, Senior Physical Security Inspector C. Graves, Health Physicist B. Lin, Project Engineer A. Turilin, Project Engineer Approved By: Fred L. Bower, III, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure
SUMMARY
IR 05000387/2014004, 05000388/2014004; 07/01/2014 - 09/30/2014; Susquehanna Steam
Electric Station (SSES), Units 1 and 2; Followup of Events and Notices of Enforcement Discretion.
The report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. One self-revealing finding of very low safety significance (Green) was identified. The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP), dated June 2, 2011.
Cross-cutting aspects are determined using IMC 0310, Aspects Within Cross-Cutting Areas, dated December 19, 2013. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy, dated July 9, 2013. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.
Cornerstone: Initiating Events
- Green.
A finding of very low safety significance (Green) for inadequately implementing work instructions for the installation and calibration of the reactor recirculation pump (RRP)motor-generator (MG) set motor winding cooling air outlet temperature switch was self-revealed when the Unit 1 B RRP tripped on August 27, 2014, requiring a rapid unplanned downpower and transition to single loop operation. The cause of the RRP trip was a calibration error made on May 7, 2014, in which the alarm and trip setpoints were reversed such that the pump trip occurred at expected temperatures for the plant conditions. PPLs immediate corrective actions included entering the issue into their corrective action program (CAP) as CR-2014-27243 and correcting the calibration error.
The inspectors determined that PPLs failure to implement a work order (WO) as written or make changes as required by station procedures was a performance deficiency (PD) that was within PPLs ability to foresee and correct and should have been prevented. The PD was more than minor because it was associated with the Equipment Performance attribute of the Initiating Events cornerstone and affected its objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during power operations.
Specifically, inadequate implementation of work instructions as directed resulted in the incorrect calibration of the B RRP MG set high temperature trip setpoint so that it was reached during normal operations, resulted in a trip of the B RRP, that required an unplanned rapid downpower to approximately 30 percent, and establishment of single loop operating conditions. The inspectors evaluated the finding in accordance with IMC 0609,
Appendix A, "SDP for Findings At-Power," Exhibit 1 for the Initiating Events cornerstone.
The inspectors determined the finding was of very low safety significance (Green) because it did not cause a reactor trip and the loss of mitigation equipment. This finding was determined to have a cross-cutting aspect in the area of Human Performance, Field Presence, because PPL did not ensure supervisory and management oversight of work activities, including contractors and supplemental personnel. Specifically, supervisory oversight of the calibration activity, including work package development, review of work performed and work package closeout, was insufficient to ensure that the changes made to the work package were processed in accordance with station procedures and did not result in a new deficiency being introduced [H.2]. (Section 4OA3)
REPORT DETAILS
Summary of Plant Status
Unit 1 began the inspection period at or near 100 percent rated thermal power. On August 27, 2014, the 1 B RRP tripped unexpectedly, resulting in an unplanned power reduction to approximately 30 percent power. The pump was restarted on August 29, 2014, and power was returned to 100 percent on September 1, 2014. Unit 1 ended the inspection period at or near 100 percent power.
Unit 2 began the inspection period in Mode 4. Following the completion of the turbine outage maintenance activities, operators commenced a reactor startup on July 7, 2014. On July 24, 2014, operators lowered power on Unit 2 to 85 percent for planned condensate demineralizer maintenance. Power was returned to 100 percent on July 27, 2014. On August 8, 2014, operators lowered power on Unit 2 to 85 percent for a planned rod pattern adjustment and additional condensate demineralizer maintenance. Power was returned to 100 percent on August 11, 2014. On September 5, 2014, operators commenced a reactor shutdown on Unit 2 for a planned maintenance outage. Following the completion of the maintenance activities, operators commenced a reactor startup on September 13, 2014. Power was restored to 100 percent on September 20, 2014, and remained at or near 100 percent power for the remainder of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
==1R04 Equipment Alignment
.1 Partial System Walkdowns
Main article: IP 71111.04Q ==
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems:
Unit 2, A train residual heat removal (RHR) during B train RHR system outage window on August 5, 2014 Unit 1, high pressure coolant injection (HPCI) while reactor core isolation cooling (RCIC) inoperable on August 19, 2014 Unit 2, control rod drive system during startup on September 17, 2014 The inspectors selected these systems based on their risk-significance relative to the Reactor Safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the Updated Final Safety Analysis Report (UFSAR), Technical Specifications (TSs), WOs, condition reports (CRs), and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies.
The inspectors also reviewed whether PPL staff had properly identified equipment issues and entered them into the CAP for resolution with the appropriate significance characterization.
b. Findings
No findings were identified.
.2 Full System Walkdown
Main article: IP 71111.04S
a. Inspection Scope
On August 15, 2014, the inspectors performed a complete system walkdown of accessible portions of the Unit 2 RCIC to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, surveillance tests, drawings, equipment line-up check-off lists, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hanger and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related CRs and WOs to ensure PPL appropriately evaluated and resolved any deficiencies.
b. Findings
No findings were identified.
==1R05 Fire Protection
.1 Resident Inspector Quarterly Walkdowns
Main article: IP 71111.05Q