IR 05000219/2010004

FZ -11 B, "Turbine Building Basement/Mezzanine North End" on September 1; *

FZ -5, "Control Room" on September 3; *

FZ -9, "Office Building" on September 3; *

RB -

FZ -1D, "Reactor Building 51' Elevation" on September 17 and *

EMS ) filter cartridge on July 16 (

FZ-11D, "Turbine Building Basement South End" on September 17. b. Findings No findings of significance were identified. 1 R06 Flood Protection Measures (71111.06) a. Inspection Scope (2 samples) The inspectors performed one internal flood protection inspection activity and one internal flood protection inspection activity associated with bunkers and manholes. The inspectors performed an internal flood protection inspection activity in the northeast corner room of the reactor building which contains the containment spray system 1 pumps and heat exchangers. The inspectors performed a walkdown of the flood Enclosure

barriers, floor drains, and floor sumps. The inspectors evaluated these items to determine if internal flood vulnerabilities existed and to assess the physical condition of the equipment and components in the northeast corner room. The inspectors reviewed preventative maintenance activities associated with flood protection equipment. The inspectors also reviewed Exelon's procedures related to flooding of the northeast corner room. The inspectors performed an internal flood protection inspection associated with bunkers and manholes. Inspections of the startup transformer cable vault and four station blackout cable vaults were performed as they are subject to flooding and contained significant cables. The inspectors performed walkdowns of these vaults to verify found water levels in the vaults and reviewed Exelon's photographs and documentation to verify the physical condition of the cables and cable supports. The inspectors also reviewed Exelon's actions to monitor cable degradation and actions to minimize water accumulation and submergence of medium voltage cables contained in these areas. Documents associated with these reviews are listed in the Supplemental Information attachment to this report. b. Findings No findings of significance were identified. 1 R11 Licensed Operator Requalification Program (71111.11) a. Inspection Scope (1 sample) The inspectors observed one simulator training scenario to assess operator performance and training effectiveness on September 1. The inspectors observed training scenario "2612.CREW.1 0-5.01 ". The inspectors assessed whether the simulator adequately reflected the expected plant response, operator performance met Exelon's procedural requirements, and the simulator instructor's critique identified crew performance problems. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. b. Findings No findings of significance were identified. 1R12 Maintenance Effectiveness (71111.12) a. Inspection Scope (2 samples) The inspectors performed two maintenance effectiveness inspection activities. The inspectors reviewed the following degraded equipment issues in order to assess the effectiveness of maintenance by Exelon: * Control Room/Cable spreading room

HVAC (

IR 759293) on August 6: and * Drywell equipment drain tank (IR 1110290) on September 9. Enclosure

The inspectors also verified that the systems or components were being monitored in accordance with Exelon's maintenance rule program requirements. The inspectors compared documented functional failure determinations and unavailable hours to those being tracked by Exelon. The inspectors reviewed completed maintenance work orders and procedures to determine if inadequate maintenance contributed to equipment performance issues. The inspectors also reviewed applicable work orders, corrective action program condition reports, operator narrative logs, and vendor manuals. Documents reviewed for this inspection activity are listed in the Supplemental I nformation attachment to this report. b. Findings No findings of significance were identified. 1 R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) a. Inspection Scope (5 samples) The inspectors reviewed five on-line risk management evaluations through direct observation and document reviews for the following plant configurations: * Risk evaluation on core spray system check valves due to missed surveillances on August 26; * #2 emergency diesel generator inoperable due to an overspeed trip on August 9; * Master automatic recirculation speed control unavailable due to unplanned maintenance on August 19; . * Core spray system #2 unavailable due to planned maintenance and receipt of spurious half-scrams on reactor protection system #2 on August 23; and * Declaration of tornado watch with 0-1029 offsite power line unavailable for Jersey Central Power and Light (JCPL) planned maintenance on September 28. The inspectors reviewed the applicable risk evaluations, work schedules, and control room logs for these configurations to verify the risk was assessed correctly and reassessed for emergent conditions in accordance with Exelon's procedures. Exelon's actions to manage risk from maintenance and testing were reviewed during shift turnover meetings, control room tours, and plant walkdowns. The inspectors also used Exelon's on-line risk monitor (Paragon) to gain insights into the risk associated with these plant configurations. Additionally, the inspectors reviewed corrective action program condition reports documenting problems associated with risk assessments and emergent work evaluations. Documents reviewed for this ins'pection activity are listed in the Supplemental Information attachment to this report. b. Findings No findings of significance were identified. 1 R15 Operability Evaluations (71111.15) a. Inspection Scope (4 samples) The inspectors reviewed four operability evaluations for degraded or non-conforming conditions associated with: Enclosure

Water in the turbine building radioactive gaseous environmental monitoring system (RAG

IR 1091519); * Average power range monitor (APRM) #1 did not insert half-scram during surveillance testing on August 7 (IR 1099066); * #1

EDG cooling fan shaft pillow-block bearing failure evaluation on July 27 (

IR [[1078312); and * Core spray system check valves past surveillance dates on August 13 (lR 1097964). The inspectors reviewed the technical adequacy of the operability evaluations to ensure the conclusions were technically justified: The inspectors also walked down accessible portions of equipment to corroborate the adequacy of Exelon's operability evaluations. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. b. Findings Introduction. The inspectors identified an unresolved item (URI) to review Exelon's equipment apparent cause evaluation (EACE) for the #1]]

EDG cooling fan shaft block bearing failure to determine whether a performance deficiency exists that was within Exelon's ability to foresee and prevent. The inspectors will review Exelon's

EACE when it is complete, which had not occurred by the end of this inspection period. Description. During the routine overhaul and inspection of the #1

EDG [[on June 8, maintenance personnel noticed damage to the cooling fan shaft pillow-block bearing. Exelon removed the bearing for further analysis by an offsite lab and replaced the bearing and shaft with new components on June 9. Exelon entered this issue into their corrective action program as]]

IR 1078312 and

IR 1103610 and is performing an

EACE to review the offsite lab report to determine the cause of the failure and any additional corrective actions. (URI 05000219/2010004-01:

EDG [[Pillow-Block Bearing) 1 R18 Plant Modifications (71111.18) a. Inspection Scope (1 temporary modification sample) The inspectors reviewed one temporary plant modification that was implemented by Exelon personnel at Oyster Creek. The inspectors reviewed the following modification: * Temporary configuration change package (]]

TCCP) to lift lead to lock in electromatic relief valve (EMRV) open alarm (ECR 10-00284) on August 17. The inspectors reviewed the engineering/procedure change packages, design basis, and licensing basis documents associated with each of the modifications to ensure that the systems associated with each of the modifications would not be adversely impacted by the change. The inspectors walked down portions of the systems associated with the modification when applicable and prudent. The inspectors reviewed the modifications to ensure they were performed in accordance with Exelon's modification process. The inspectors also ensured that revisions to licensing/design basis documents and operating procedures were properly revised to support implementation of the modification. The inspectors also reviewed Exelon's 10 CFR 50.59 screening for this modification. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. Enclosure

b. Findings No findings of significance were identified. 1 R19 Post-Maintenance Testing (71111.19) a. Inspection Scope (7 samples) The inspectors observed portions of and/or reviewed the results of seven maintenance tests for the following equipment: * V-21-17 stem lubrication and packing retorque on July 7 (R2126779); * Standby gas treatment system #2 filter replacement on August 2 (C2023814); * Replacement of #2

EDG overspeed trip switch on August 8 (C2024062); * V-28-23 replacement on August 19 (R2119622); * Core spray system 2 relay replacement and oil change on August 25 (R2163871); * V-14-30 stem lubrication and packing retorque on September 29 (R2142502); * 'E'

EMRV [[pressure switch replacement on September 24 (R2119341). The inspectors verified that the post-maintenance tests conducted were adequate for the scope of the maintenance performed and that they ensured component functional capability. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. b. Findings No findings of significance were identified. 1 R22 Surveillance Testing (71111.22) a. Inspection Scope (2 In-service test (1ST) samples and 2 routine surveillance samples) The inspectors observed portions of and/or reviewed the results of four surveiliance/lST tests: * Reactor building to suppression chamber self actuating vacuum breaker surveillance test and]]

1ST on July 1; * Containment spray and emergency service water system 1 pump operability, 1

ST and containment spray pump trip surveillance on July 7; * Reactor coolant system (RCS) leak detection surveillance on July 15; and * Automatic scram contactor surveillance on August 30. The inspectors verified that test data was complete and met procedural requirements to demonstrate that the systems and components were capable of performing their intended function. The inspectors also reviewed corrective action program condition reports that documented deficiencies identified during these surveillance tests. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. Enclosure

b. Findings No findings of significance were identified. Cornerstone: Emergency Preparedness [EP]

1 EP 2 Alert and Notification System (

ANS [[) Evaluation a. Inspection Scope (71114.02 -1 Sample) The inspectors conducted an onsite review to assess the maintenance and testing of the Oyster Creek alert and notification system (ANS). During the inspection, the inspectors reviewed the Federal Emergency Management Agency (FEMA) design report to ensure Exelon's compliance with design report commitments, the system maintenance and test records, and applicable]]

ANS procedures. The planning standards contained in 10

CFR 50.47(b)(5) and the related requirements of

10 CFR 50 Appendix E, were used as reference criteria . . b. Findings No findings were identified. 1

EP [[3 Emergency Response Organization (ERa) Staffing and Augmentation System a. Inspection Scope (71114.03 -1 Sample) The inspectors reviewed Oyster Creek's emergency response organization (ERa) augmentation staffing requirements, training program, and the process for notifying and augmenting the]]

ER a. This was performed to ensure the readiness of key licensee staff to respond to an emergency event and to ensure Exelon's ability to activate their emergency facilities in a timely manner. The inspectors reviewed Oyster Creek's

ER a duty roster, sampling of training records, call-in reports, applicable procedures, and condition reports (CR) related to the

ER a staffing augmentation system. The planning standards contained in 10

CFR 50.47(b)(2) and related requirements of

10 CFR 50 Appendix E, were used as reference criteria. b. Findings No findings were identified. 1

EP 4 Emergency Action Level lEAl) and Emergency Plan Changes a. Inspection Scope (71114.04 -1 Sample) Since the last

NRC inspection of this program area, Exelon implemented changes to their emergency action levels (

EAL ), emergency plan and implementing procedures. Exelon had determined that, in accordance with

10 CFR [[50.54(q), any change made to the plan, and its lower-tier implementing procedures, had not resulted in any decrease in effectiveness of the emergency plan, and that the revised emergency plan continued to meet the standards in 50.47(b) and the reqUirements of 10]]

CFR 50 Appendix E. Enclosure

The inspectors reviewed all

EAL changes and a sample of emergency plan changes to evaluate any potential decreases in effectiveness of the emergency plan. However, this review by the inspectors was not documented in an

NRC Safety Evaluation Report and does not constitute formal

NRC approval of the changes. Therefore, these changes remain subject to future

NRC inspection in their entirety. The requirements contained in

10 CFR 50.54(q) were used as reference criteria. b. Findings No findings were identified. 1

EP 5 Correction of Emergency Preparedness Weaknesses a. Inspection Scope (71114.05 -1 Sample) The inspectors reviewed Exelon's Corrective Action Program (CAP) procedure for evaluating their

EP program and performance. The inspectors reviewed a sampling of drill reports, self assessment reports, 10

CFR 50.54(t) audits, and

10 CFR 50.47(b)(14) and the related requirements of 10

CFR 50 Appendix E, were used as reference criteria. b. Findings No findings were identified. 4.

OTHER [[]]

ACTIVI [[TIES lOA] 40A1 Performance Indicator Verification (71151) a. Inspection Scope (5 Samples) The inspectors reviewed performance indicator (PI) data associated with five Pis. The inspectors used the guidance provided in Nuclear Energy Institute (NEI) 99-02, Revision 6, "Regulatory Assessment Performance Indicator Guideline" to assess the accuracy and completeness of the]]

PI [[data reported by Exelon between July 1, 2009 and June 30, 2010. Documents reviewed for this inspection activity are listed in the Supplemental Information attachment to this report. . The inspectors reviewed the following Pis: * Drill and exercise performance (]]

DEP); * Emergency Response Organization (ERO) drill participation; * Alert and notification system (ANS); * Reactor coolant system activity (RCSA); and * Reactor coolant system identified leak rate (RCSL). b. Findings No findings of significance were identified. Enclosure

40A2 Identification and Resolution of Problems (71152) .1 Review of Items Entered Into the Corrective Action Program The inspectors performed a daily screening of items entered into Exelon's corrective action program to identify repetitive equipment failures or specific human performance issues for follOW-Up. This was accomplished by reviewing hard copies of each condition report, attending daily screening meetings, or accessing Exelon's computerized database. Assessment and Observations No findings of significance were identified. 40A3 Event Followup (71153) (1 sample) The inspectors performed one event follow-up inspection activity. Documents reviewed for this inspection activity are listed in the Supplemental Information attached to this report . . 1 Drywell Unidentified Leak Rate Increase a. Inspection Scope On September 7, operators noted that drywell unidentified leak rate (UILR) rose to a peak of 2.63 gpm from its prior value, which had been trending from 0.92 to 1.02 gpm. Exelon determined that the problem was a result of a failed open valve in the drywell equipment drain tank recirculation line and installed a temporary modification (ECR 10-00530) to correct the problem. The

UILR [[subsequently returned to its previous values. The inspectors verified that operations personnel responded in accordance with procedures and equipment responded as intended by reviewing the completed procedures, control room narrative logs, corrective action program condition reports, and through interviews of operations personnel. The inspectors also reviewed technical specification requirements to ensure that Oyster Creek was operated in accordance with its operating license. The inspectors performed a walkdown of the main control room panels and indications to verify equipment status and plant parameters. The]]

UILR increase is described and evaluated in corrective action program condition report IR 1110290. b. Findings No findings of significance were identified. 40A6 Meetings, Including Exit Resident Inspector Exit Meeting. On October 19, the inspectors presented their overall findings to members of Exelon's management led by Mr. M. Massaro, (Site Vice President), and other members of his staff who acknowledged the findings. The inspectors confirmed that proprietary information was not retained at the conclusion of the inspection period. Enclosure

Commissioner Site Visit. On August 31, a site visit was conducted by Mr. William Magwood, Commissioner for the Nuclear Regulatory Commission and Mr. Martin Virgilio, Deputy Executive Director for Operations. During Mr. Magwood's visit, he toured the plant and met with Exelon managers. Mr. Marc Dapas, Acting Regional Administrator (RA) for the

NRC Region 1 office, accompanied Mr. Magwood on his visit. 40A7 Licensee-Identified Violations None.

ATTACH MENT:

SUPPLE [[]]

MENTAL [[]]

INFORM [[]]

ATION Enclosure

SUPPLE [[]]

MENTAL [[]]

INFORM [[]]

ATION Licensee Personnel

M. Massaro, Site Vice-President P. Orphanos, Plant Manager

KEY [[]]

POINTS [[]]

OF [[]]

CONTAC [[T D. Dicello, Director, Work Management J. Dostal, Director, Operations A. Farenga, Emergency Preparedness Manager R. Peak, Director, Engineering R. Reiner, Director, Training P. Colgan, Director, Maintenance J. Barstow, Manager, Regulatory Assurance T. Keenan, Manager, Security R. Wiebenga, Senior Manager, System Engineering H. Ray, Senior Manager, Design Engineering M. McKenna, Shift Operations Superintendent D. Peiffer, Manager, Nuclear Oversight J. Kerr, Manager, Corrective Action Program M. Ford, Manager, Environmental/Chemistry Manager J. Renda, Manager, Radiation Protection K. Barnes, Regulatory Assurance Specialist Others: State of New Jersey, Bureau of Nuclear Engineering]]

LIST [[]]

OF [[]]

ITEMS [[]]

OPENED ,

CLOSED ,

AND [[]]

DISCUS SED Opened 05000219/2010004-01

URI [[]]

EDG Pillow-Block Bearing (Section 1R15)

LIST [[]]

OF [[]]

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED In addition to the documents identified in the body of this report, the inspectors reviewed the following documents and records. Section 1 R01: Adverse Weather Protection Procedures

OC -1 08-1 09-1 001 , "Preparation for Severe Weather

T&RM for Oyster Creek"

OP -OC-1 08-1 09-1 004, "Hurricane Staffing

T&RM for Oyster Creek"

OP -AA-1 08-111-1001, "Severe Weather and Natural Disaster Guidelines"

WC -

AA -107, "Seasonal Readiness"

OC -1 08-1 001, "Preparation for Severe Weather

T&RM for Oyster Creek"

ABN-31, "High Winds" Attachment

Condition Reports (IR) 1118951 Section 1R04: Equipment Alignment Procedures 310, "Containment Spray System Operation" 307, "Isolation Condenser System" A-2 609.3.002, "Isolation Condenser Isolation Test and Calibration -A1/B1 Sensors First" Drawings

GE 148F740, "Flow Diagram -Containment Spray System" Section 1 R05: Fire Protection Procedures

ABN -29, "Plant Fires" 101.2, "Oyster Creek Site Fire Protection Program"

CC -

AA -211, "Fire Protection Program" 333, "Plant Fire Protection System" Other Documents

RB -

FZ -1 F4, Oyster Creek Generating Station Pre-Fire Plan, "NE Corner Room"

RB -

FZ -1O, Oyster Creek Generating Station Pre-Fire Plan, "51' Elevation"

FZ -11 B, Oyster Creek Generating Station Pre-Fire Plan, "Turbine Building Basement/Mezzanine (0'-0" Elevation) North End (27' 0" Elevation)"

FZ -11 D, Oyster Creek Generating Station Pre-Fire Plan, "Basement Floor South End (3' 6" Elevation)

FZ -5, Oyster Creek Generating Station Pre-Fire Plan, "Control Room"

FZ -9, Oyster Creek Generating Station Pre-Fire Plan, "Office Building"

FA -26, Oyster Creek Generating Station Pre-Fire Plan, '''C' Battery Room" Fire Drill Scenario, "C Battery Room Fire", dated September 29,2010 Section 1 R06: Flood Protection Measures Procedures

OC -773-001, "Testing/Condition Monitoring of Inaccessible Medium Voltage Cables not Subject to

10CFR 50.49 Environmental Qualification"

ER -AA-3003, "Cable Condition Monitoring Program"

AA -723-500, "Inspection of Non-EQ Cables and Connections for Managing Adverse Localized Environments" 117.3, "Alternate

AC System Reliability Monitoring" Drawings

GE 148F740, Containment Spray System

GU 3D-153-07, 001, General Arrangement Floor and Equipment Drains -Reactor Building Condition Reports

OR) 852474 828327 828338 890453 373114 1086111 1066334 1076306 1113908 330592 Work Orders (AR) R2095953 R2139427 R2162105 R2103165 A2193092 A2193908 A2193907 A2187171 A2073455 R2116819 R213.9427 R2146232 R2157294 R2153284 Attachment

Other Documents Oyster Creek Nuclear Generating Station

UFSAR section 9.3.3.2.2, "Reactor Building Floor and Equipment Drains"

RB -FZ-1 F4, Oyster Creek Generating Station Pre-Fire Plan, "NE Comer Room" Design and Licensing Basis for Flooding at

OCGS Intemal Flood Evaluation Summary and Notebook -Oyster Creek Nuclear Generating Station

EQIS -315403-003, "Flooding due to

HELB s Outside Containment"

TDR 779, "Evaluation of Possible Internal Flooding of Oyster Creek Nuclear Generating Station Power Plant Buildings" C-1302-822-E61 0-076, "Flooding due to

HELB s Outside Containment" Oyster Creek Generating Station License Renewal Application Section B.1.36, "Inaccessible Medium-voltage Cables not subject to 10

CFR 50.49 Environmental Qualification Requirements" Exelon letter, "Response to

NRC Generic Letter 2007-01, "Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients"", dated May 7, 2007 Exelon Letter, "Exelon Generation Company,

LLC /AmerGen Energy Company,

LLC Response to the Request for Additional Information (

RAI ) Regarding Resolution of

NRC Generic Letter 2007-01, "Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients"", dated December 7, 2007 Report # 2009-09, "Cable System Assessment Provided for Exelon Oyster Creek Nuclear Generating Station, Forked River,

NJ , February 24-March 5, 2009" System Engineer Spreadsheet of Cablewise Testing Results, updated for 2010 Oyster Creek Nuclear Generating Station

UFSAR , Section 8.3.4, "Station Blackout"

USNRC Letter, "Safety Evaluation -Station Blackout Analysis Oyster Creek Nuclear Generating Station (TAC

NO. 68577)", dated August 23, 1991

USNRC Letter, "Supplemental Safety Evaluation (SSE) -Oyster Creek Nuclear Generating Station Blackout Rule (TAC

NO. 68577)", dated February 12, 1992

USNRC Regulatory Guide 1.155, "Station Blackout" Section 1 R11: Licensed Operator Requalification Program Other Documents

EOP User's Guide (2000-

BAS -3200.02)

2612.CREW. 10-5.01 Section 1R12: Maintenance Effectiveness Procedures

ER -AA-310, "Implementation of Maintenance Rule"

AA -31 0-1 005, "Maintenance Rule -Disposition Between (a)(1) and (a)(2)"

LS [[]]

AA -125-1003, "Apparent Cause Evaluation Manual" 351.2, "High Purity Waste System"

AA -102-103, "Operator Work-Around Program"

NEI 93-01, "Industry Guideline for monitoring the Effectiveness of Maintenance at Nuclear Power Plants" Oyster Creek Generating Station Technical Specification 3.3.0, "Reactor Coolant System Leakage"

AB-331-1006, "BWR Reactor Coolant System Leakage Monitoring and Action Plan" Drawings JC 147434, "Sump and Waste Collection System" Attachment

Condition Reports (IR) 744793 749568 967366 1008461 1110762 Work Orders (AR) 754608 1055518 A-4 790158 1080887 804233 1098953 940266 1110290 A0700924 A0705758 C0528074 C2002414 C2019099 C2024198 R0800924 Other Documents

ECR 10-00530 Section 1R13: Maintenance Risk Assessments and Emergent Work Control Procedures

AA -600-1042, "On-line Risk Management"

AA -600-1 021, "Risk Management Application Methodologies"

AA -600-1 014, "Risk Management Configuration Control"

AA -600-1 011, "Risk Management Program"

WC -

OC -1 01-1 001, "On-line Risk Management and Assessment" 2400-SMI-3422.02, "Digital

FW and Recirc Speed Control System Maintenance"

WC -AA-104, "Integrated Risk Management"

AA -600-1045, "Risk Assessments of Missed or Deficient Surveillances" Condition Report

OR ) 1102779 1056730 Work Orders (

AR ) C2024102 Other Documents 1093256 Oyster Creek Generating Station Technical Specification Section 4, "Surveillance Requirement Applicability"

OC -

SURV -01, "Risk Analysis for Missed Surveillance, Failure to Open and Inspect Core Spray Main Pump Discharge Check Valves" Section 1R15: Operability Evaluations Procedures

AA -1 08-115, "Operability Determination" 620.4.002, "APRM Surveillance Test -Front Panel Check"

ABN -39, "

RPS Failures"

LS -

AA -125-1003, "Apparent Cause Evaluation Manual"

OC -861-101, "Diesel Generator Inspection (24 Month) -Mechanical"

OC -861 03-100, "Diesel Generator Fan Belt Replacement" Drawings

GU -3E-661-21-1001, "Radiation Monitor System,

RAGEMS II, Turbine Building" Attachment

Condition Reports (lR) 1093256 1056730 1097964 1091519 1099444 658467 814754 1099066 1100447 1093120 1099180 1089395 1103610 1078312 370560 1081766 1078411 Work Orders (AR) A2256877 R2165933 A2255578 C2023739 R2017655 R2085970 R2125850 A2089090 R2096800 R2113198 Other Documents

NRC Inspection Manual -Part 9900 Technical Guidance, "Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety"

NRC Letter, "Safety Evaluation of the Inservice Testing Program Relief Requests for Pumps and Valves, Oyster Creek Nuclear Generating Station", dated September 24,

1992 NRC Letter, "Safety Evaluation of the Inservice Testing (1

ST ) Program Relief Requests for Pumps and Valves, Oyster Creek Nuclear Generating Station", dated August 14,

1993 GL 89-04, "Guidance on Developing Acceptable Inservice Testing Programs" Oyster Creek Nuclear Generating Station Technical Specification 4.4, "Emergency Cooling"

ASME [[]]

OM Code-1995, "Code for Operation and Maintenance of Nuclear Power Plants"

NUREG -1482, "Guidelines for Inservice Testing at Nuclear Power Plants", Revision 1 Oyster Creek Generating Station Technical Specification Table 3.1.1, "Protective Instrumentation Requirements"

OYS -99753, Exelon PowerLabs report, "Failure Evaluation of the No.1 Emergency Diesel Generator Cooling Fan Shaft Pillow-Block Bearing,

EMD General Motors"

M. 1.1200, "Maintenance Instruction -

MP 45 Cooling Fan and Related Drive Train Assembly" Section 1R18: Plant Modifications Procedures

LS -

AA -104-1001, "50.59 Review Coversheet Form"

ABN -40, "Stuck Open

EMRV " Condition Report

OR ) 1083235 1072166 Work Order (

AR ) C2022310 Other

1064669 OC -2010-S-0080, 50.59 Screening form for

ECR 10-00284 Oyster Creek Nuclear Generating Station

UFSAR section 6.3.1.2, "Automatic Depressurization System" Oyster Creek Nuclear Generating Station

UFSAR section 6.3.2.2, "Equipment and Component Description" Oyster Creek Nuclear Generating Station

UFSAR section 7.3.1.3.5, "Automatic Depressurization System" Oyster Creek Nuclear Generating Station

UFSAR section 7.3.5.2, "Non-RPS Systems" Attachment

Section 1R19: Post-Maintenance Testing Procedures A-6

AA -716-012, "Post Maintenance Testing"

MA -1 09-1 01, "Clearance and Tagging" 607.4.014, "Containment Spray and

ESW System 1 Pump Operability, 1

ST and Containment Spray Pumps Trip"

OC [[-741-101, "Diesel Generator Inspection {24 Month} -Electrical" 636.4.013, "Diesel Generator #2 Load Test" 334, "Instrument and Service Air System" 651.3.002, "SGTS Particulate Filter In-Place Leak Test" 610.4.022, "Core Spray System 2 Pump Operability and Quarterly In-Service Test"]]

AA -321, "Administrative Requirements for Inservice Testing" 609.4.001, "Isolation Condenser Valve Operability and In-Service Test" 602.3.004, "Electromatic Relief Valve Pressure Sensor Test and Calibration" Drawings

EM 8397907 Sheet 3, "Emergency Diesel Generator #2 Electrical Elementary Wiring Diagram,

DG [[]]

DC Control Circuits"

GE 885D781, "Core Spray System Flow Diagram"

GE 729E182, "Elementary Diagram, Auto Depressurization System" Condition Report (

IR ) 794100 1099299 1105435 553984 1062804 Work Order (AR) R2126779 R2146198 C2023814 R2163871 Other 1096095 553996 C2024062 R2119622 1096375 1027679 587926 618201 C2010504 A2256817 R2142502 R2119341 531101354 660529 R2166827 R2119343

VM -

OC [[-0096, "Engine Maintenance Manual -645E4 Turbo Charge Engine (Diesel Generators )" Safety Evaluation 00212-036, "Core Spray System Operability Criteria" Safety Evaluation 00212-046, "Core Spray Main Pump Operability Criteria" Safety Evaluation 00212-061, "Core Spray System 2 Main Pump Operability Criteria"]]

ECR 02-00927

GL 88-14, "Instrument Air Supply System Problems Affecting Safety-Related Equipment"

GPU Nuclear letter, "Generic Letter 88-14", dated February 21,1989 Safety Evaluation 000212-029, "

EMRV [[Setpoint and Tolerance" Oyster Creek Generating Station Technical Specification 2.3{D}, "Limiting Safety System Settings, Reactor High Pressure, Relief Valves Initiation" Section 1 R22: Surveillance Testing Procedures]]

SA -

AA -129, "Electrical Safety"

AA -1000, "Conduct of Maintenance" 604.4.003, "Reactor Building to Suppression Chamber Self Actuating Vacuum Breaker Surveillance Test and

1ST " 607.4.014, "Containment Spray and

ESW System 1 Pump Operability, 1ST and Containment Spray Pumps Trip" Attachment

NRC Inspection Manual Part 9900 Technical Guidance, "Maintenance-Preconditioning of Structures, Systems, and Components Before Determining Operability" C-1302-243-531 0-041, "

AA [[-302-1006, "Generic Letter 96-05 Program Motor-Operated Valve Maintenance and Testing Guidelines" 619.4.025, "Automatic Scram Contactor Test" Condition Reports (lR) 1088380 1088608 794100 1088397 1104183 1107302 Work Orders (AR) R2160886 R2146198 R2168080 Other Documents]]

OCNGS 20"

RB to Suppression Chamber Vacuum Verification oft est Procedure #604.4.003" Oyster Creek Nuclear Generating Station Technical Specification 3.5.A.4, "Reactor Building to Suppression Chamber Vacuum Breaker System" Section 1

EP 2: Alert and Notification System

IANS ) Evaluation Procedures

EP -MA-121-1004, "Exelon East

ANS Corrective Maintenance"

EP -MA-121-1005, "Exelon East

ANS Preventive Maintenance Program"

EP -MA-121-1006, "Exelon East

ANS Siren Monitoring, Troubleshooting, and Testing"

EP -MA-121-1002, "Exelon East Alert Notification System (ANS) Program"

AA -125-1 001, "EP Performance Indicator Guidance" Other Documents Oyster Creek Alert Notification System, Upgraded System Design Report, April 2005 Section

1 EP 3: Emergency Response Organization

IERO ) Staffing and Augmentation System Procedures

AA -112-200, "TSC Activation and Operation"

AA -112-100-F-07, "Mid-Atlantic

ER a Notification or Augmentation"

EP -AA-121-1001, "Automated Call-out System Maintenance"

AA -122-1001, "Drill and Exercise Scheduling, Development and Conduct"

TQ -

AA -113, "ERa Training and Qualification"

AA -121, "Emergency Response Facilities and Equipment Readiness" Other Documents

ER a Call-in Augmentation Drill Results, dated June 26,2010

ER a Call-in Augmentation Drill Results, dated March 23,

2010 ER a Call-in Augmentation Drill Results, dated December 9, 2010

ER a Call-in Augmentation Drill Results, dated December 1,

2009 ER a Call-in Augmentation Drill Results, dated September 24, 2009

ER a Call-in Augmentation Drill Results, dated March 21,

2009 ER a Call-in Augmentation Drill Results, dated May 29, 2009 Section 1

EP 4: Emergency Action Level lEAL) and Emergency Plan Changes Procedures

LS -

AA -104, "Exelon 50.59 Review Process"