IR 05000440/2008005
Download: ML090270129
Text
January 26, 2009
Mr. Mark Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-290 Perry, OH 44081-0097
SUBJECT: PERRY NUCLEAR POWER PLANT NRC INTEGRATED INSPECTION REPORT 05000440/2008005
Dear Mr. Bezilla:
On December 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Perry Nuclear Power Plant. The enclosed report documents the inspection findings which were discussed on January 15, 2009, with you and members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, two NRC-identified and one self-revealed findings of very low safety significance were identified. Two of the findings identified also involved violations of NRC requirements. In addition, one NRC-identified violation of NRC requirements, without an associated finding, was identified. Two licensee-identified violations are listed in Section 4OA7 of this report. However, because of the very low safety significance and because the issues were entered into your corrective action program, the NRC is treating these issues as non-cited violations in accordance with Section VI.A.1 of the NRC's Enforcement Policy. If you contest the subject or severity of any non-cited violation 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 U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors' Office at the Perry Nuclear Power Plant. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Jamnes L. Cameron, Chief Reactor Projects Branch 6 Docket No. 50-440 License No. NPF-58
Enclosure:
Inspection Report 05000440/2008005
w/Attachment:
Supplemental Information cc w/encl: J. Hagan, President and Chief Nuclear Officer - FENOC J. Lash, Senior Vice President of Operations and Chief Operating Officer - FENOC D. Pace, Senior Vice President, Fleet Engineering - FENOC J. Rinckel, Vice President, Fleet Oversight - FENOC P. Harden, Vice President, Nuclear Support Director, Fleet Regulatory Affairs - FENOC Manager, Fleet Licensing - FENOC Manager, Site Regulatory Compliance - FENOC D. Jenkins, Attorney, FirstEnergy Corp. Public Utilities Commission of Ohio C. O'Claire, State Liaison Officer, Ohio Emergency Management Agency R. Owen, Ohio Department of Health
SUMMARY OF FINDINGS
......................................................................................................... 1
REPORT DETAILS
..................................................................................................................... 4 Summary of Plant Status.........................................................................................................
REACTOR SAFETY
..................................................................................................... 4
1R01 Adverse Weather Protection
............................................................ 4
1R04 Equipment Alignment
....................................................................... 5
1R05 Fire Protection (Annual/Quarterly)
.............................................. 6
1R12 Maintenance Effectiveness
............................................................ 11
1R13 Maintenance Risk Assessments and Emergent Work Control
........ 12
1R15 Operability Evaluations
.................................................................. 13
1R18 Plant Modifications
......................................................................... 13
1R19 Post-Maintenance Testing
............................................................. 14
1R20 Refueling and Other Outage Activities
........................................... 15
1R22 Surveillance Testing
....................................................................... 20
1EP4 Emergency Action Level and Emergency Plan Changes
RADIATION SAFETY
................................................................................................. 22 2OS1 Access Control to Radiologically Significant Areas 71121.01 ........................... 22 2OS2 ALARA Planning and Controls
OTHER ACTIVITIES
.................................................................................................. 27
4OA1 Performance Indicator Verification
...................................................... 27
4OA2 Identification and Resolution of Problems
........................................... 30
4OA3 Followup of Events and Notices of Enforcement Discretion
................ 31 4OA6 Meetings .......................................................................................................... 36 4OA7 Licensee-Identified Violations .......................................................................... 36
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- M. Bezilla, Vice President Nuclear
- K. Krueger, Plant General Manager
- M. Bay, Senior Nuclear Specialist, Mechanical Maintenance
- A. Cayia, Director, Performance Improvement
- K. Cimorelli, Director, Maintenance
- E. Condo, Operations Superintendant
- C. Elberfeld, Compliance Supervisor
- D. Evans, Manager, Operations
- E. Gordon, Radiation Protection Operational Superintendent
- J. Grabner, Director, Site Engineering
- R. Gemberling, Training
- H. Hanson, Jr., Director, Work and Outage Management
- J. Lucas, General Electric, Perry Site Support Engineer
- P. McNulty, Radiation Protection Manager
- A. Mueller, Manager - Training
- D. Richmond, Simulator Programs Lead
- P. Roney, Supervisor, Nuclear Mechanical/Structural Engineer
- S. Rouhani, Mechanical/Structural Engineer
- K. Russell, Staff Nuclear, Specialist Compliance
- T. Stec, Engineer - Nuclear Compliance
- R. Strohl, Training NRC
- D. Passehl, Senior Reactor Analyst
LIST OF ITEMS
OPENED, CLOSED, DISCUSSED
Opened and Closed
- 05000440/2008005-01 NCV Inspection Procedure for RPV Head Strongback Omitted Non-Destructive Testing of Structural Welds (Section 1R20.1.b.(1))
- 05000440/2008005-02 NCV Containment Polar Crane Trolley Seismic Restraints Did Not Meet Seismic Category I Requirements (Section 1R20.1.b.(2))
- 05000440/2008005-03 FIN Loss of the V-1F and V-2F Non-Vital Buses Resulting in the Loss of Technical Support Center Computers (Section 4OA3.1)
Attachment
- 05000440/2008-04 NCV Failure To Report All 10 CFR 50.73 Reportable Events Associated With The Discovery Of Loose Containment Grating (Section 4OA3.2)
Closed
- 05000440/LER-2007-003-01 LER Improper Containment Floor Grating Installation Results in an Unanalyzed Condition, Supplement (Section 4OA3.3) 2515/174 TI Hydrogen Igniter Backup Power Verification (Section 4OA5.3) 2515/176 TI Emergency Diesel Generator Technical Specification Surveillance Requirements Regarding Endurance and Margin Testing (Section 4OA5.4)
Opened
- 05000440/2008005-05 URI Unplanned Unavailability of the Motor Feedwater Pump After it was Placed in 10 CFR 50.65(a)(1) status (Section 711111.12)
Attachment
LIST OF DOCUMENTS REVIEWED
The following is a partial list of documents reviewed during the inspection.
- Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.
- Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. 1R01
- Adverse Weather
- NOP-WM-2001; Work Management Scheduling/Assessment/Seasonal Readiness Processes; Revision 7
- WO 200291786; Circulating Water Pumps Seal Water Heat Tracing; dated October 23, 2008
- CR 08-47570; Winter Prep Order Rescheduled Due to Parts Restraint; dated October 7, 2008
- WO 200286109; Auxiliary Boiler Fuel Oil; dated October 23, 2008
- WO 200285708; Heat Tracing and Freezing Protection Calibration; dated October 23, 2008
- WO 200286739; Heater Bay Ventilation; dated September 9, 2008
- WO 200283511; Centralized Heat Tracing Panel; dated September 2, 2008
- WO 200280005; Service Water B Intake Traveling Screen; dated August 27, 2008
- WO 2003133014; Turbine Building Ventilation; dated October 23, 2008
- 1R04
- Equipment Alignment
- VLI-R44; Division 1 and 2 Diesel Generator Starting Air System; Revision 4
- VLI-R47; Division 1 and 2 Diesel Generator Lube Oil; Revision 6
- VLI-R48; Division 1 and 2 Diesel Generator Exhaust, Intake, and Crankcase Systems; Revision 6
- VLI-R46; Division 1 and 2 Diesel Generator Jacket Water Systems; Revision 4
- VLI-R45; Division 1 and 2 Diesel Generator Fuel Oil System; Revision 5
- VLI-P42; Emergency Closed Cooling System; Revision 14
- CR 08-48992; Lube Oil Leak on Division 1 Diesel Generator; dated November 5, 2008 1R05
- Fire Protection (Annual/Quarterly)
- FPI-A-A02, "Periodic Fire Inspections," Revision 5
- PAP-1910, "Fire Protection Program," Revision 16
- PAP-0204, "Housekeeping/Cleanliness Control Program," Revision 21 1R11
- Licensed Operator Requalification Program
- CR 08-49100: Failure to Notify NRC to Revoke an Individual's NRC License; dated November 6, 2008 2008 Biennial Written Exam Sample Plan Methodology; no date 2007-2008 Master License Operator Requalification Schedule; no date Twenty eight JPMs; In-Plant, Administrative and Simulator JPMs; Various Dates Nine
- Scenario Guides; Various Dates Five Written Exams; Various RO and SRO Written Exams; Various Dates Perry Nuclear Power Plant (PNPP) Licensed Operator Requalification Examination Questions
- Used - 2008; no date PNPP Licensed Operator Requalification Examination Sample Plan - 2008, Weeks 1-7; no date Snapshot Self-Assessment Report; no date Engineering Design Guide 97-003; Review of Operating Instructions for USAR/Design Basis
- Impact, Attachment 6; Revision 2 Trainee Tracking; FENOC Integrated Training System Successful Completion Report; dated
- December 2, 2008
- Attachment Trainee Tracking Control #
- 2007024377; FENOC Integrated Training System Completion
- Verification with Grade; dated October 3, 2007
- PYBP-POS-1-5; Operations Training Guidelines; dated January 12, 2006
- TMA-4206; Licensed Operator Requalification Programs (Administration); dated July 28, 2008
- NOBP-TR-1109-02; Non-Facilitated Plus/Delta, Cycle 2007-01 through Cycle 2008-10
- NOBP-TR-1109-06; Trainee Feedback Summary (Multiple); various dates from January 8, 2007 - October 10, 2008 ANSI/ANS-3.4-1983; Medical Certification and Monitoring of Personnel Requiring Operator
- Licenses for Nuclear Power Plants; dated April 29, 1983
- ANSI/ANS-3.5-1998; Nuclear Power Plant Simulators for Use in Operator Training; dated
- April 15, 1998 Regulatory Guide 1.149; Nuclear Power Plant Simulation Facilities for Use in Operator License
- Examinations; Revision 3; dated October 2001
- PYBP-PTS-0033; Simulator Configuration Control; Revision 5
- PYBP-PTS-0031; Simulator Review Board; Revision 3
- PYSA-08-073; Snapshot Self-Assessment Report; November 4, 2008
- NOP-TR-1008; FENOC Simulator Configuration Management; Revision 0 Simulator Work Order Summary - Open Items; dated December 1, 2008
- Simulator Minor Work Item Summary - Open Items; dated December 1, 2008 Simulator Work Request Summary - Open Items; dated December 1, 2008 Twenty five Scenario Based Test Packages for 2008 Simulator Scenarios Ten Scenario Based Test Packages for 2007 Simulator Scenarios
- CR 08-35163; Unplanned Technical Specification Entry Which Declared ECC B and
- Associated Systems Inoperable; dated February 10, 2008
- CR 08-37799; Plant to Simulator Differences During Plant Scram; dated April 4, 2008 SWO Number 08-0044; DR464 from
- CR 08-37799 - Plant to Simulator Differences During Plant
- Scram; dated July 23, 2008
- SWO Number 08-0028; Unable to Determine if Malfunction IA02C Worked as Designed; dated
- July 23, 2008 Completed Simulator Physical Fidelity Testing;
- PYBP-PTS-0033 Revision 5; dated
- November 18, 2008 Completed Simulator Physical Fidelity Testing;
- PYBP-PTS-0033 Revision 3; dated
- December 17, 2007 Simulator Review Board Minutes; dated May 4, 2007, September 20, 2007, and
- August 18, 2008 Completed Simulator Testing; 2007 and 2008 Normal Operations; Various Dates Completed Simulator Testing; Cycle 12 BOL Core Tests; dated October 3, 2007 Completed Simulator Testing; Cycle 12 MOL Core Tests; dated June 5, 2008
- Completed Simulator Testing; 2007 and 2008 Simulator Annual Testing (Transient Tests, Heat
- Balance and Real Time Tests); Various Dates Medical Files for 12 Licensed Operators
- LER 440 2007 001; Automatic Reactor Protection System Actuation
- Due to Reactor Coolant System Level Decrease; dated May 15, 2007
- LER 440 2007 002; Shutdown Cooling Pump Trip Results in Operation Prohibited by TS; dated July 11, 2007
- LER 440 2007 003; Improper Containment Floor Grating Installation Results in Unanalyzed
- Condition; dated August 27, 2007
- LER 440 2007 004; Automatic Reactor Protection System Actuation Due to Feedwater Control
- System Power Supply Failure; dated November 28, 2007
- LER 440 2007 005; Plant Startup with Inoperable RCIC System; dated December 12, 2007
- Attachment
- LER 440 2007 006; Loss of Safety Function and Condition Prohibited by TSs due to Annulus Exhaust Gas Treatment System Inoperability; dated
- December 21, 2007
- LER 440 2008 001; Inoperable Emergency Closed Cooling System Results in Condition
- Prohibited by Technical Specifications; dated February 10, 2008
- LER 440 2008 002; Inoperable Emergency Closed Cooling System Results in Condition
- Prohibited by Technical Specifications; dated February 10, 2008 Scenario Guide
- OTLC-30582008006-PY-SGD2
- CR 07-30703; Unplanned Reactor Scram Report for Automatic Reactor Scram Due to Digital
- Feed Water Control System Malfunction; dated May 15, 2007 Lesson Plan
- OT-Combined-E51; RCIC System; Revision 0
- Lesson Plan
- OTLC-3058200806-PY-08; Revision 0 Lesson Plan
- OT-Combined-P42; Emergency Closed Cooling Water System; Revision 2
- 1R12
- Maintenance Effectiveness
- CR 08-47241; ESW Loop A Rad Monitor Failure; dated October 2, 2008
- CR 08-47287; Radwaste to ESW Radiation Monitor Inoperable Based on Spiking; dated October 6, 2008
- CR 08-48403; Pri-300; ESW A Rad Monitor Has Exceeded its 21-day Completion Date Requirement; dated October 24, 2008
- CR 08-46312; Evaluate M&TE and Vicotreen D17 Monitor Test Methodology; dated September 15, 2008 Performance Criteria data for Plant Radiation Monitoring; dated June 30, 2008
- CR 08-48507; Turbine Building/Heater Bay D-19 Had Multiple Equipment Failure Alarms; dated October 24, 2008
- CR 08-48650; 1D19N0440 Failed Testing; dated October 28, 2008 Maintenance Rule Functions, Performance Criteria and Classifications; Expert Panel Meeting Minutes, January 11, 2006
- NOP-ER-3004; FENOC Maintenance Rule Program; Revision 0
- PAP-1125; Monitoring the Effectiveness of Maintenance Program Plan; Revision 8
- PYBP-PES-1; Maintenance Rule Reference Guide; Revision 14
- CR 08-47924; Failed Goal Within a Maintenance Rule A(1) Goal Monitoring Criteria
- CR 08-47992; Less than Adequate Support for Maintenance Rule Expert Panel
- CR 06-463; ICS Unavailable
- CR 06-3974; ICS Computer Shutdown
- CR 07-29301; Full Data Disk Causes Plant Computer Shutdown
- CR 07-24527; TSC/UPS Battery Room Temperature is at 95 Degrees Maintenance Rule System Basis Document for System C91/C95; Supervisor Approval Dated September 11, 2006 Failure Summary Report for Perry Computer System from October 2005 to November 2008; Generated November 6, 2008 PWR and BWR Failure Summary Report for Plant Computer Systems from October 2005 to November 2008; Generated November 7, 2008
- CR 08-37457; Motor Feed Pump Oil Milky Appearance; dated March 29, 2008
- CR 08-44480; Water in Motor Feed Pump Lube Oil System; dated August 7, 2008
- CR 08-47924; Failed Goal Within a Maintenance Rule a(1) Monitoring Criteria; dated
- October 14, 2008
- CR 08-41632; Electrical Components Have Exceeded Maintenance Rule Performance Criteria; dated June 11, 2008
- Attachment 1R13
- Maintenance Risk Assessments and Emergent Work Control
- PYBP-POS-2-2; Protected Equipment Postings; Revision 6 PNPP No. 10241; Division 2 Outage (Yellow); dated September 8, 2008 PNPP No. 10252; Division 2 Diesel Generator Outage (Yellow); dated September 8, 2008
- CR 08-48921; Protected Train Walkdown by Shift Manager Revealed Issues with Postings; dated November 4, 2008 Outage Control Shift Turnover Report; dated November 7, 2008 1R15
- Operability Evaluations
- CR 08-48686; Performance Testing of RHR 'B' Loop; dated October 29, 2008
- PTI-E12-P0003; RHR Q-Trend Graph; dated June 2, 2008 Prompt Operability Determination;
- Acceptance Criteria; dated October 8, 2008
- 1R18
- ECP 08-0323-001
- NOP-OP-1001; Clearance/Tagging Program; Revision 9
- RWI-G61 (EDS); Equipment Drain Sump; Revision 4
- PAP-1404; Miscellaneous Tagging; Revision 5
- CR 08-48997; Platinum Pump Trip During On-line Noble Chemistry Injection; dated November 5, 2008
- PTI-N27-P0015; On-Line Noble Metals Re-Application; Revision 0
- CR 08-49594; CNRB CM/ER Subcommittee Identified a Concern with a 50.59 Screen; dated November 13, 2008 1R19
- Post-Maintenance Testing
- WO 200169007; Emergency Closed Cooling A Hydramotor; dated October 2, 2008
- WO 200328073; LPCS & RHR A Water Leg Pump; dated October 4, 2008
- CR 08-49080; Linear Indication Noted On Right Bank Cylinders 1 And 8 Rocker Arm Pedestals; dated November 6, 2008
- PMI-0019; Division 1&2 Diesel Generator Rocker Arm And Valve Lifter Maintenance; Revision 7
- CR 08-48950; Unable To Conduct Functional Test Of Bkr EH1205 As It Was Scheduled; dated November 4, 2008
- WO 200328952; ESW Pump B EH1205 Relay Replacement; dated November 5, 2008 OCC Narrative Logs; dated November 6-7, 2008
- CR 08-49289; Unacceptable Management of AOT; dated November 11, 2008
- CR 08-49279; Inadequate Tag Out for Removing Fuel Oil Piping on Division 2 Diesel; dated November 10, 2008
- CR 08-49090; Division 2 DG Cylinder Head Nuts as-found Torque Values Outside Specified Range; dated November 7, 2008
- CR 08-49109; Order Directed Cylinder Head Torque Check on the Incorrect Cylinder Head; dated November 7, 2008
- WO 200170718; ECC B HX Output Temperature Controller; dated November 26, 2008
- WO 200303033; Div 2 Weekly 125V Battery Voltage and Category A Limits Check; dated October 27, 2008
- WO 200273106; 125V Battery Category B Limits, Terminal Corrosion, and Electrolyte Temperature Check (Unit 1, Division 2); dated October 27, 2008
- CR 08-48989; Battery Rack Spacer Tubes Found Missing; dated November 5, 2008
- CR 08-48537; Battery Rack Cell Spacer Missing; dated October 24, 2008
- CR 08-48458; Shim Plate Flashing Material Found Floating in Battery Electrolyte; dated October 25, 2008
- Attachment Certificate of Conformance by EnerSys; dated August 13, 2008
- WO 200321038; Diesel Generator Start and Load Division 2; dated November 12, 2008 1R20
- Outage Activities (71111.20) Crane and Heavy Lift Inspection (OpESS FY2007-03) ANSI N14.6-1978; American National Standard for Special Lifting Devices for Shipping
- Containers Weighing 10000 Pounds (4500 kg) or more for Nuclear Materials; 1978
- ANSI B30.2.0-1976; Overhead and Gantry Cranes; 1976 Appendix K of Supplement No. 5 to
- NUREG-0887, Safety Evaluation Report Related to the Operation of Perry Nuclear Power Plant, Units 1 and 2; February 1985 Calculation No. 0280-0039-1; Reactor Vessel Head Drop Analysis; Revision 0 Calculation No. DV767E572; General Electric Structural Analysis of Perry Reactor Pressure Vessel Head and Dryer/Separator Strongbacks; 1974 Calculation No. 3:36.12; Justification and Requirements for Handling Load Over Spent Fuel w/Polar Crane Auxiliary Hoist; Revision 1 Calculation No. 4549-32-133; Reactor Building Cranes for Perry Nuclear Power Plant- Units 1 and 2 Bridge Structural Calculations; dated May 10, 1982 Calculation No. 4549-32-134; Reactor Building Cranes for Perry Nuclear Power Plant-Units 1 and 2 Trolley Structural Calculations; dated May 10, 1982 Calculation No.
- NEDE-25525; Structural Analysis of Reactor Pressure Vessel and Internals for Vessel Head Drop, Shroud Head Assembly Drop, and Steam Dryer Assembly Drop Conditions; dated January 1982 Cleveland Electric Letter to NRC, Subject: Control of Heavy Loads; dated June 19, 1981 Drawing No. 23-0119-00000; Head Strongback Carousel; Revision A
- Drawing No. 100A7595; Bottom Block Ass'y 125 Ton PH Crane; Revision A Drawing No. 3521-193; Vessel Outline; Revision 8 Drawing No. 4549-31-559; Trolley Seismic Restraint Design Drawing; Revision A Drawing No. D-511-221; Reactor Building-Steel Framing RPV Pedestal Wall Liner Details Stretch-Out - EL. 576'-9" to EL. 604'-2"; Revision L Drawing No. D-511-222; Reactor Building -Steel Framing R.P.V. Pedestal Wall Liner Details Sections and Details; Revision J Drawing No. D-511-223; Reactor Building-Steel Framing R.P.V. Pedestal Wall Liner Details Sections and Details; Revision J Drawing No. E-015-044; Final Plant Layout Reactor Refueling Floor Layout Study; Revision C
- File No. 0180; P & H Crane Manual; Revision 6 GAI Report 2329; Control of Heavy Loads Study for Perry Nuclear Power Plant, Unit 1 and 2; Revision 2 General Electric Letter to Cleveland Electric, Subject: ANSI 14.6-1978 RPV Head Strongback Carousel and Dryer/Separator; dated December 7, 1982
- GMI-0003; Mobile Cranes, Aerial Platforms (Boom Type) and Line (Bucket) Truck Guidelines; Revision 9
- GMI-0004; General Guidelines for Rigging; Revision 8
- GMI-0185; Reactor Vessel Disassembly and Assembly; Revision 10
- MAP-0201; Qualifications of Crane Operators; Revision 2
- MAP-1301; Control of Heavy Loads; Revision 2
- MM 2042; Special Crane Operations; Revision 5
- NOP-WM-5003; Rigging, Lifting and Load Handling; Revision 2 NUREG 0612 Control of Heavy Loads Fleet Oversight Performance Assessment Report; dated April 9, 2008 NUREG 0933; Resolution of Generic Safety Issues; August 2008
- Attachment
- OJT 5135; Crane, Standard; Revision 3
- OJT 5281; Special Crane, Polar; Revision 1
- OJT 5282; Special Crane, Emergency Service Water/Fuel Handling Building; Revision 1
- PAP-1313; Control of Lifting Operations; Revision 8
- PMI-0015; Reactor Polar Crane Preventative Maintenance; Revision 7
- PMI-0085; Head Strongback Carousel Preventative Maintenance; Revision 13
- PMI-0089; Examination of Lifting Devices; Revision 3 Report No. F13-E009; Dynamic Qualification of Head Strongback Carousel for Perry Nuclear Power Plant Units 1 and 2; dated February 11, 1983 Safety Evaluation 97-0056; Modifying Sections 9.1.2.3.5, 9.1.4.2.2.1 and 9.1.5 of USAR, Rev. 8 and ORM 6.5.5 and
- MAP-1301, Rev. 2 and Section 6.4 of
- PAP-1313, Revision 0; dated July 28, 1997 Work Order No.
- 200168033; Polar Crane, Reactor Building 125/10;
- PY-1L51 Cranes Hoists and Elevators; dated May 7, 2007 Work Order No.
- 200191335; Polar Crane, Reactor Building 125/10;
- PY-1L51 Cranes Hoists and Elevators; dated January 7, 2007 Work Order No.
- 200238349; Polar Crane, Reactor Building 125/10;
- PY-1L51 Cranes Hoists and Elevators; dated April 11, 2008 Work Order No.
- 200254834; Polar Crane, Reactor Building 125/10;
- PY-1L51 Cranes Hoists and Elevators; dated April 2, 2007 Condition Reports Reviewed During NRC Inspection (OpESS FY2007-03)
- CR 07-17334; Engineering Review of
- RIS 2005-025 (NRC Guidelines for Control of Heavy Loads); dated April 1, 2007
- CR 08-44711;
- NEI 08-05 Rev. 0 Control of Heavy Loads; dated August 13, 2008
- CR 08-39059; Unrecognized OPDRV Results in LER; dated April 24, 2008
Condition Reports
- Initiated as a Result of NRC Inspection (OpESS FY2007-03)
- CR 08-50714; Polar Crane Trolley Seismic Restraints are Not Fully Consistent with Calculation; dated December 11, 2008
- CR 08-50414; NRC Questions Adequacy of Testing of Special Lifting Devices; dated December 3, 2008
- CR 08-50408; NRC Identified Issues with the Containment Polar Crane Calculation; dated December 3, 2008
- CR 08-50810; NRC Identified Math Error in GE Analysis; dated December 4, 2008
- CR 08-50542; NRC Identified Issues with the Containment Polar Crane Calculation; dated December 8, 2008 1R22
- Surveillance Testing
- SVI-R10-T5226; Containment Penetration Molded Case Circuit Breaker Inspection and Preventative Maintenance; Revision 1
- CR 08-48504;
- SVI-R10-T5226 Change Identified; dated October 24, 2008
- CR 08-48545; R10-T5226 Not Completed as Scheduled; dated October 24, 2008
- WO 200055802 1EP4
- Emergency Action Level and Emergency Plan Changes
- NOP-LP-5002; Evaluation of Changes to Emergency Plans and Supporting Documents,
- 10
- CFR 50.54(q); Revision 2 Emergency Plan for Perry Nuclear Power Plant, Docket
- NOS 50-440; Revision 28
- Emergency Plan for Perry Nuclear Power Plant, Docket
- NOS 50-440; Revision 29 10
- CFR 50.54(q) Screening Packet for Emergency Plan for Perry Nuclear Power Plant; Revision 28.
- Scope of Revision for Emergency Plan for Perry Nuclear Power Plant; Revision 29.
- Attachment 2OS2
- ALARA Planning and Controls
- CR 07-27957; High Radiation Area Entry Without Proper RP Brief; dated October 2007
- CR 08-33510; Radioactive Material Generating a Radiation Area was Not Posted Appropriately; dated January 2008
- CR 08-43839; B12 Box Moved Too Close to RCA Boundary; dated July 2008
- CR 08-46891; Maintenance Mechanics Working in the Div 2 Diesel Room During Liner Movement; dated September 2008
- HPI-C0010; Radiation Protection Support of Plant Startup; Revision 5
- HPI-C0014; Radlock Key Issue; Revision 0
- HPI-L0009; Discrete Particle Control; Revision 4
- NOP-OP-4204; Special External Exposure Monitoring; Revision 00
- NOP-WM-7025; High Radiation Area Program; Revision 02
- NOP-WM-7003; Radiation Work Permit (RWP); Revision 04
- 4OA1
- Performance Indicator Verification
- MSPI Data Sheets for Emergency AC Power Systems from October 2007 to September 2008 MSPI Data Sheets for High Pressure Injection System from October 2007 to September 2008 MSPI Data Sheets for Emergency Service Water from October 2007 to September 2008
- MSPI Data Sheets for Heat Removal System; from October 2007 to September 2008. MSPI Data Sheets for Residual Heat Removal System; from October 2007 to September 2008. Control Room Operator Logs from October 2007 to September 2008 Reactor Coolant System leakage data sheets from October 2007 to September 2008
- 4OA2
- Identification and Resolution of Problems Perry Self Assessment Database through December 2008
- CR 08-49855; Adverse Trend of 4 PCEs Over 4 Consecutive Days; dated November 20, 2008
- CR 08-49233; Emergent Trend In Radiation Worker Performance; dated November 10, 2008
- CR 08-48064; Negative Trend In Engineering Quality In September; dated October 17, 2008
- CR 08-50521; Declining Trend In Pre -Job Briefs For Design Engineering; dated
- December 7, 2008 Plant Health Report 2008-02 4OA3
- Followup of Events and Notices of Enforcement Discretion
- CR 08-48075; Minor Vehicle Accident; dated October 17, 2008
- CR 08-48677; Loss of V-1-F and V-2-F; Human Performance Perspective; dated October 30, 2008
- CR 08-48676; Loss of V-1-F and V-2-F Causes Maintenance Rule Functional Failure on ICS; dated October 30, 2008
- CR 08-48471; UPS Air Handling Unit Stopped Working; dated October 25, 2008
- LER 05000440/2007-003-01; Improper Containment Floor Grating Installation Results in an Unanalyzed Condition, Supplement
- CR 08-46139; Inoperable Equipment Details not Included in
- LER 2007-003 Submittal - NRC-identified; dated September 11, 2008
- 4OA5
- Other Activities
- PYBP-ERS-0014; Emergency Management Overview; Revision 4
- EPLC-200803_PY-01; Trainee Tracking; dated October 10, 2008 Perry Nuclear Power Plant Control Room Emergency Coordinator Training; Trainee Tracking; dated October 13, 2008
- Attachment Preventative Maintenance Nuclear
- 200322813; Functional Test of Generators Maintenance Plan; Single Cycle Plan 000000107871 Maintenance Plan; Single Cycle Plan 000000237361
- OTLC-3058200807_PY-OTS; Lesson Plan; dated June 20, 2008 Course Attendance Sheet;
- ONI-SPI-D10; dated April 14, 2008 SVI- R43-T1347; Div 1 Standby Diesel Generator 24 Hour Run; Revision 2
- SVI- R43-T1348; Div 2 Standby Diesel Generator 24 Hour Run; Revision 2 SVI- E22-T1349; Div 3 Standby Diesel Generator 24 Hour Run; Revision 2 Calculation
- PSTG-0014; Diesel Loading; Revision 7
- 4OA7
- Licensee-Identified Violations
- CR 08-49069; Failed Licensed Requalification Exam; dated November 6, 2008
- Attachment
LIST OF ACRONYMS
- USED [[]]
- ER [[]]
- LO [[]]
UFSAR Updated Final Safety Analysis Report URI Unresolved Item
Attachment