IR 05000277/2010003

HPSW pumps take suction from the Conowingo Pond through the

SW pump bays. The

ESW pumps are common to both units and supply cooling to the

EDG coolers. In addition,

ESW also supplies cooling to the emergency core cooling system (

ECCS ) room coolers, core spray pump motor oil coolers, and

RHR pump seal coolers. The

HPSW system for each unit provides cooling water for the

RHR heat exchangers (

HX s) under post-accident conditions. The emergency cooling tower (ECT) provides the heat sink for the related pump bays in the unlikely event that the Conowingo Dam fails or the Conowingo pond floods. The inspectors reviewed the

ESW ,

HPSW , and intake design to evaluate the adequacy of system monitoring and performance testing. The inspectors reviewed a sample of

IST s in accordance with American Society of Mechanical Engineers Code requirements. In addition, the inspectors reviewed Exelon's monitoring, maintenance, and testing of interface valves between safety-related

HPSW [[pump and valve performance tests, system health and Generic Letter (GL) 89-13 Program reports, and in-service test (1ST) vibration monitoring results for adverse trends and to verify that the systems functioned as designed. The inspectors verified that Exelon performed the pump and valve]]

SW and non-safety related or non-seismic piping systems to ensure that adequate

SW flow is available post-accident consistent with design basis assumptions. The inspectors reviewed Exelon's buried pipe inspection and monitoring program to independently assess the condition and structural integrity of the

HPSW piping. The inspectors reviewed a sample of

HPSW pipe nondestructive examination records and intake structure inspections to ensure that Exelon appropriately identified and dispositioned any

HPSW piping or intake structure degradation. The inspectors performed an above ground walkdown of accessible areas containing buried

HP [[]]

SW and Enclosure

ESW piping to look for soil subsidence or other indications of piping leakage and/or degradation. The inspectors also directly observed the condition of

HPSW and

ESW piping in the accessible portions of the

SW pump bays, valve pits, and

EDG rooms. The inspectors reviewed Exelon's procedures and processes to control macrofouling of the

HPSW systems. The inspectors also observed the condition of several zebra mussel monitoring locations. The inspectors reviewed Exelon's procedures for

ESW ,

HPSW , and intake structure operation; abnormal

SW [[operations; intake flooding; and for a loss of the Conowingo Pond. The inspectors verified that Exelon maintained these procedures consistent with their design and licensing basis, and that plant operators could reasonably implement the procedures as written. The inspectors independently verified that the]]

HPSW [[pump bay and intake level instrumentation, which operators rely upon for decision making, was available and functional. The inspectors also reviewed the most recent third party structural inspection of the Conowingo Dam to assess the integrity and availability of the Conowingo Pond heat sink. The inspectors walked down control room instrument panels, accessible portions of]]

HPSW piping in the turbine and reactor buildings (including the

RHR [[]]

HX s), the

ECT , the

HPSW pumps, and the intake area (including the trash racks, outer traveling water screen room, and

SW traveling water screens) to assess the material condition and configuration control of these structures, systems and components (SSCs). The inspectors also reviewed a sample of corrective action issue reports (IRs) related to the

HPSW and

ESW isolation valves, pumps, and piping integrity to ensure that Exelon appropriately identified, characterized, and corrected problems related to these essential

SSC [[s. Documents reviewed are listed in the Attachment. b. Findings No findings of significance were identified. 1R11 Licensed Operator Regualification Program (71111.11Q -1 Sample) .1 Resident Inspector Quarterly Review a. Inspection Scope On May 3, 2010, the inspectors observed operators in]]

PBAPS [['s simulator during licensed operator requalification training to verify that operator performance was adequate and that evaluators were identifying and documenting crew performance issues. The inspectors verified that performance issues were discussed in the crew's post-scenario critiques. The inspectors discussed the training, simulator scenarios, and critiques with the operators, shift supervision, and the training instructors. The inspectors observed the following scenario: *]]

PS [[]]

EG-1109R: Evaluation Scenario. b. Findings No findings of significance were identified. Enclosure

1R12 Maintenance Effectiveness (71111.12Q -2 Samples) a. Inspection Scope The inspectors evaluated

PBAPS 's work practices and follow-up corrective actions for safety-related

SSC s and identified issues to assess the effectiveness of

PBAPS 's maintenance activities. The inspectors reviewed the performance history of

SSC s and assessed

PBAPS 's extent-of-condition (

EOC ) determinations for those issues with potential common cause or generic implications to evaluate the adequacy of the

PBAPS 's corrective actions. The inspectors assessed

PBAPS 's problem identification and resolution (PI&R) actions for these issues to evaluate whether

PBAPS had appropriately monitored, evaluated, and dispositioned the issues in accordance with Exelon procedures, including

ER -AA-310, "Implementation of the Maintenance Rule (MR)," and the requirements of 1

0 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance." In addition, the inspectors reviewed selected

SSC classifications, performance criteria and goals, and

PBAPS 's corrective actions that were taken or planned, to evaluate whether the actions were reasonable and appropriate. Documents reviewed are listed in the Attachment. The inspectors performed the following two samples: * 2 'C'

RHR (System 10) Exceeded

MR (a)(1) Unavailability Limit (

IR "1084973); and * Maintenance Activities Associated with Failure Mode Causal Tree (FMCT) for Tritium Leakage Mitigation Efforts (IR 1046838, Activity 6). b. Findings No findings of significance were identified. 1 R13 Maintenance Risk Assessments and Emergent Work Control ([[Inspection procedure" contains a listed "[" character as part of the property label and has therefore been classified as invalid. -6 Samples) a. Inspection Scope The inspectors evaluated]]

PBAPS 's implementation of the Maintenance Risk Program with respect to the effectiveness of risk assessments performed for maintenance activities that were conducted on

SSC s. The inspectors also verified that the licensee managed the risk in accordance with

10 CFR Part 50.65(a)(4) and procedure .

WC -AA-101, "On-line Work Control Process." The inspectors evaluated whether

PBAPS had taken the necessary steps to plan and control emergent work activities and to manage overall plant risk. The inspectors selectively reviewed

PBAPS's use of the online risk monitoring software and daily work schedules. The activities selected were based on plant maintenance schedules and systems that contributed to risk. Documents reviewed are listed in the Attachment. The inspectors completed six evaluations of maintenance activities on the following: * Control of Work and Management of Plant Risk, between April 6-7, 2010, during Partial Loss of 3 'A' Main Power Transformer Cooling (IR 1053261); * Control of Work and Management of Plant Risk, between April 26-30, during Week 1 of 5 of the 11th Annual Independent Spent Fuel Storage Installation Campaign (SF-221); Enclosure

Control of Work and Management of Plant Risk, on May 20, 2010, during Troubleshooting and Repair of Backup Nitrogen Supply to the Automatic Depressurization System (ADS) valves (Action Request (AR) A1730354 and

ST [[-M-016-400-3); * Control of Work and Management of Plant Risk, between May 10-28, 2010, during Transfer of Reactor Protection System Power Supplies for Cooper Substation Tie-In to Off-Site Source 220-08 (Clearance 10000772); * Control of Work and Management of Plant Risk, between April 4-5, 2010, during on-line steam leak injection repairs to]]

CV -2-08-4018: Main Steam Supply to Recombiner System Control Valve (Operational Technical Decision Making (OTDM) associated with

IR 1045319); and * Control of Work and Management of Plant Risk during and following Identification of a Leak in the Unit 2 'C'

RHR [[]]

HX on June 16 (

RT [[-O-010-630-2). b. Findings No findings of significance were identified. 1 R15 Operability Evaluations (71111.15 -6 Samples) a. Inspection Scope The inspectors reviewed six issues to assess the technical adequacy of the operability evaluations, the use and control of compensatory measures, and compliance with the licensing and design bases. Associated adverse condition monitoring plans (ACMPs), engineering technical evaluations, and]]

OTDM documents were also reviewed. The inspectors verified these processes were performed in accordance with the applicable administrative procedures and were consistent with

NRC guidance. Specifically, the inspectors referenced procedure

AA -108-115, "Operability Determinations," and

NRC [[]]

IMC Part 9900, "Operability Determinations & Functionality Assessments for Resolutions of Degraded or Nonconforming Conditions Adverse to Quality or Safety." The inspectors also used Technical Specifications (TSs),

TRM ,

UFSAR , and associated

DBD s as references during these reviews. Documents reviewed are listed in the Attachment. The following degraded equipment issues were reviewed: * Operability Evaluation Number 10-002, Engineer Evaluation of Submerged Cable Issue (

IR 1048012); * Operability Evaluation Number 10-003, Unit

3 HPCI 30P038 Inboard and Outboard Seal Leak After Run (

IR 1048641); * Evaluate Utilization of the

2AE 018 Reactor Building Closed Cooling Water (

RBCCW )

HX with River Water Temperature Greater than 60 Degrees Fahrenheit (

AR A1552281 Evaluation 21); * Unit 2 Control Rod Drive 38-15 Double Notch (IR 1072280); *

GNF -

II Quality Update 2010-001:

GNF Bent Spacer Flow Vanes; and *

ACMP for Monitoring of 3 'B' Phase Main Power Transformer Combustible Gases (IR 1082693). b. Findings No findings of significance were identified. Enclosure

1R18 Plant Modifications (71111.18 -1 Sample) .1 Permanent Modifications a. Inspection Scope The inspectors reviewed one permanent modification to verify that modification implementation did not place the plant in an unsafe condition. The review was also conducted to verify that the design bases, licensing bases, and performance capability of risk significant

SSC s had not been degraded as a result of these modifications. The inspectors verified the modified equipment alignment through control room instrumentation observations;

UFSAR [[, drawings, procedures, and work order ryvO) reviews; staff interviews; and plant walkdowns of accessible equipment. Documents reviewed are listed in the Attachment. The following engineering change request (ECR) for a permanent modification was reviewed: *]]

ECR 07-00274, Addition of Vent Valves and Reroute of Unit 3

HPCI [[Main Pump Seal Water Line. b. Findings No findings of significance were identified. 1R19 Post-Maintenance Testing (71111.19 -5 Samples) a. Inspection Scope The inspectors observed and reviewed completed test records for selected post-maintenance testing (PMT) activities. The inspectors observed whether the tests were performed in accordance with the approved procedures or instructions and assessed the adequacy of the test methodology based on the scope of maintenance work performed. In addition, the inspectors assessed the test acceptance criteria to evaluate whether the test demonstrated that components satisfied the applicable design and licensing bases and the]]

TS requirements. The inspectors reviewed the recorded test data to verify that the acceptance criteria were satisfied. Documents reviewed are listed in the Attachment. The inspectors reviewed five

PMT s performed in conjunction with the following maintenance activities: *

RBCCW 2

AE 018

HX Replacement ryvO C0231717); * E-2

EDG Engine Inspection ryvO R1108074); * Unit 2 End-of-Cycle Recirculation Pump 'B' Trip Breaker Replacement ryvO C0299083-07); * Unit

3 HPCI Turbine Trip Level Adjustment (

IR 1060963); and * Unit 3 'B' Core Spray Pump, Valve, Flow and Cooler Functional and

1ST following Planned 'B' Loop Maintenance Outage (

ST-O-014-305-3 performed on May 19, 2010). b. Findings No findings of significance were identified. Enclosure

1R22 Surveillance Testing (71111.22-5 Samples) a. Inspection Scope (3 Routine Surveillances;

1 RCS ; and 1 1

ST [[Sample) The inspectors reviewed and observed selected portions of the following surveillance tests (STs), and compared test data with established acceptance criteria to verify the systems demonstrated the capability of performing the intended safety functions. The inspectors also verified that the systems and components maintained operational readiness, met applicable]]

TS requirements, and were capable of performing design basis functions. Documents reviewed are listed in the Attachment. The five

ST s reviewed or observed included: *

ST -O-032-301-3,

HPSW Pump, Valve and Flow Functional and

1ST [[[1 1]]

ST [[Sample]; *]]

ST [[-O-020-560-2/3, Units 2 & 3 -Reactor Coolant Leakage Test [1 Reactor Coolant System (]]

RCS [[) Leakage sample]; *]]

ST -O-010-306-3, 'B'

RHR Loop Pump, Valve, Flow, and Unit Cooler Functional and

1ST [[[1 1]]

ST [[sample]; *]]

ST -M-071-602-2, Independent Spent Fuel Storage Installation (l

SFSI ) Casks

TN -68-64 Drying, Backfilling, and Leak Tests; and *

RT -O-023-302-2,

HPCI Turbine Overspeed Trip Reset Time Check / Adjustment and

HPCI Auxiliary Oil Pump and Manual Trip Lever Tension Test, performed on May 22,2010. The inspectors noted that

IR 1068090 was entered into the corrective action system to address a question related to the acceptance criteria contained in

RT -O-023-302-2, and verified that appropriate corrective actions were taken by

PBAPS. b. Findings No findings of significance were identified.

1EP 6 Drill Evaluation (71114.06 -1 Sample) a. Inspection Scope The inspectors evaluated the conduct of a

PBAPS emergency drill on May 10, 2010, to identify any weaknesses and deficiencies in classification and notification activities. The drill was conducted, in part, to provide drill and exercise performance (DEP) opportunities for the

DEP performance indicator (

PI [[). The inspectors observed operators respond to events in the simulator control room through the declaration and notification of an alert. The inspectors observed the operations shift manager transition emergency response command and control responsibilities to the site emergency director in the technical support center (TSC). The inspectors relocated to the]]

TSC [[to observe command and control of the emergency response organization and dose assessment as the event escalated to the declaration and notification of a site area emergency, followed by further escalation to a general emergency. The inspectors verified that the event classification and notifications were done in accordance with]]

AA -1007, "Exelon Nuclear Radiological Emergency Plan Annex for

PBAPS. " The inspectors verified that the drill evaluators correctly counted the drill's contribution in the calculation of the

DEP PI. The inspectors also verified that operations personnel in the Enclosure

simulator control room identified weaknesses or deficiencies during the critique of the drill. The following simulated events were classified during this training exercise: *

FG 1 -General Emergency, Fission Product Barrier Degradation: Fuel Cladding; *

FS 1 -Site Area Emergency, Fission Product Barrier Degradation: Primary Containment; and *

FA 1 -Alert, Fission Product Barrier Degradation: Reactor Coolant System (

RCS ). b. Findings No findings of significance were identified. 4.

OTHER [[]]

ACTIVI TIES (OA) 40A1 Performance Indicator (PI) Verification (71151 -4 Samples) Cornerstone: Barrier Integrity .1 Barrier Integrity Pis (71151 -4 Samples) a. Inspection Scope The inspectors reviewed a sample of

PBAPS 's submittals for the four Barrier Integrity Pis listed below to verify the accuracy of the data reported. The

PI definitions and the guidance contained in Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Indicator Guideline," Revision 6, and Exelon procedure

LS -

AA -2001, "Collecting and Reporting of

NRC [[]]

PI Data," were used to verify that the reporting requirements were met. The inspectors reviewed

PI data collected from January 2009 to April 2010. The inspectors compared the graphical representations from the most recent

PI report available from the

NRC public website to the raw

PI data to verify the data was properly included in the report. The Pis reviewed were: * Unit 2 and Unit

3 RCS Specific Activity (

BI 01); and * Unit 2 and Unit

3 RCS Leakage (

BI 02). b. Findings No findings of significance were identified. 40A2 Identification and Resolution of Problems (PI&R) (71152 -1 Semi-annual Trend Sample;

1 OWA Sample) .1 Review of Items Entered into the

CAP [[a. Inspection Scope As required by Inspection Procedure (IP) 71152, "Identification and Resolution of Problems," and in order to help identify repetitive equipment failures or specific human performance issues for fOllOW-Up, the inspectors performed screening of all items entered into the licensee's]]

CAP. This was accomplished by reviewing the description of each new

AR / IR and attending daily management review committee meetings. Enclosure

b. Findings No findings of significance were identified . . 2 Semi-Annual Review to Identify Trends (1 Semi-annual Resident Inspector Sample) a. Inspection Scope The inspectors reviewed lists of

CAP items to identify trends (either

NRC or licensee identified) that might indicate the existence of a safety issue requiring more detailed inspection follow-up. The inspectors reviewed a list of approximately 6,700

IR s that

PBAPS initiated and entered into the

CAP action tracking system (Passport) from December 1, 2009 through June 1, 2010. The inspectors also reviewed a list of approximately 3,200

IR s for which corrective actions remained open. The lists were reviewed and screened to complete the required semi-annual

PI&R trend review. A sample of 54 Passport

IR [[s (listed in the Attachment) were selected from the list and reviewed in more detail to verify whether the issues were adequately identified and evaluated, and that corrective actions were either closed or planned appropriately. The inspectors evaluated the]]

IR s against the requirements of Exelon procedure,

LS -AA-125, and

10 CFR 50, Appendix B, Criterion

XVI ", "Corrective Action." b. Assessments and Observations No findings of significance were identified. The inspectors noted that during this trend review period, two significant unplanned transients occurred. One involved the trip of the 2 'A'reactor recirculation pump (IR 1026936) and the other involved a Unit 2 load reduction that was performed in response to a loss of isophase bus duct cooling ([[Issue report" contains a listed "[" character as part of the property label and has therefore been classified as invalid.). The inspectors observed that the]]

PBAPS appropriately performed root cause analyses for these two events. The inspectors also noted that

PBAPS [[performed a root cause analysis of an event involving multiple control rods that had slow scram times during the initial portions of their insertion (IR 1023827). A common cause analysiS was performed to review multiple equipment related reactivity events. The inspectors observed that the licensee appropriately used the]]

CAP and associated anal

YS is tools to evaluate reactivity management events. The inspectors observed that

PBAPS took appropriate action to perform common cause analyses of two additional areas. The first involved an adverse trend of problem identification and resolution cross-cutting aspects associated with

NRC "findings (IR 1060396). The second involved security department training and qualification failures that required remediation (IR 1061573). The inspectors also noted that maintenance personnel identified (IR 1059363) a list of historical deficiencies that supported their conclusion that poor operating reliability existed for the glycol chillers in the offgas system and contributed to adverse environmental impacts. The inspectors noted additional trends related to the following subject areas: [[Isotope" contains a listed "[" character as part of the property label and has therefore been classified as invalid. (IR 1044318,]]

IR 1024952,

IR 1032576,

IR 1030952), motor control center (

MCC ) voltages (IR 1002703,

IR 1081198,

IR 1081472,

IR 1081490,

IR 1081496), main turbine master trip solenoid valves (IR1042832,

IR 1070301,

IR 1076001), submerged cable issues (IR 1030481,

IR 1081636,

IR 1048012,

IR 1022206) and fire induced multiple spurious operations (

MSO s) related issues (IR 1053615,

IR 985851,

IR 106316, IR 1047196). The inspectors also observed a trend of aged issues that remained open Enclosure

during the inspection period that included engineering issues identified during or in preparation for

IR 762371). The inspectors had discussed these issues and trends with

PBAPS personnel. However, based on the overall review of the selected sample, the inspectors concluded that

PBAPS was: appropriately identifying and entering issues into the

CAP , adequately evaluating the identified issues, and acceptably identifying adverse trends before they became more safety significant problems . . 3 Review of Operator Work Arounds (1

OWA Sample) a. Inspection Scope As required by

IP 71152, "Identification and Resolution of Problems," the inspectors conducted a review of the

OWA program to verify that

PBAPS was identifying

OWA s problems at an appropriate threshold, have entered them in the

CAP , and proposed or implemented appropriate corrective actions. The inspectors reviewed the list of

OW As and Operator Challenges (

OC s) identified and managed in accordance with Exelon Procedure,

AA -1 02-103, "OWA Program." Specifically, the review was conducted to determine if any

OWA s for mitigating systems affected the mitigating system's safety functions or affected the operators' ability to implement abnormal and emergency operating procedures. The inspectors reviewed the following open

OWA s being tracked by

PBAPS * Unit 3 -

HPCI Pump Inboard and Outboard Seal Leakage (AR A1752639). The inspectors also reviewed the lists of open

OC s (deficiencies that are obstacles to normal plant operations), periodically walked down the panels in the main control room, and have reviewed control room deficiencies to identify and be cognizant of: (1)

OWA s that have not been evaluated by

PBAPS , and (2)

OWAs that increase the potential for personnel error, including OWAs that: * Require operations contrary to past training or require more detailed knowledge than routinely provided; * Require a change from longstanding operational practices; * Require operation of a system or component in a manner different from similar systems or components; * Create the potential for the compensatory action to be performed on equipment or under conditions for which it is not appropriate; * Impair access to required indications, increase dependence on oral communications, or require actions under adverse environmental conditions; and * Require the use of equipment and interfaces that have not been designed with consideration of the task being performed. The inspectors accompanied the Unit 2 turbine building equipment operator during dayshift rounds on June 3, 2010, and the Unit 3 reactor building nuclear equipment operator during day shift rounds on June 24, 2010, to observe any potential work around challenges. The inspectors also interviewed operators to determine if any compensatory actions they routinely take are (or should be) categorized as workarounds/challenges. Finally, the inspectors reviewed current operator turnover Enclosure

documentation to determine if there are documented compensatory actions that should be categorized as workarounds!challenges. b. Findings No findings of significance were identified. 40A6 Meetings, Including Exit .1 Commissioner Site Visit and Meeting On June 2, 2010, Commissioner

W. Magwood and members of his staff visited

PBAPS , toured the site and met with senior Exelon management. Commissioner Magwood was accompanied by Mr.

S. [[Collins, Regional Administrator, Region I and Mr. P. Krohn, Branch Chief, Region I, Division of Reactor Projects . . 2 Quarterly Resident Exit Meeting Summary On July 16,2010, the resident inspectors presented the inspection results to Mr. Thomas Dougherty and other]]

PBAPS staff, who acknowledged the findings. Mr.

P. Krohn, Chief,

USNRC [[, Region 1, Division of Reactor Projects, Branch 4, attended this quarterly inspection exit meeting. The inspectors asked the licensee whether any of the material examined during the inspection should be considered proprietary. No proprietary information was identified . . 3 Triennial Heat Sink Performance Exit Meeting Summary On May 21, 2010, the inspectors presented the inspection results to Mr. Thomas Dougherty, Site Vice President, and other members of the Exelon staff. The inspectors verified that no proprietary information was documented. 40A7 Licensee-Identified Violations The following violation of very low significance (Green) was identified by the licensee and is a violation of]]

NRC requirements which meets the criteria of Section

VI of the

NRC Enforcement Policy for being dispositioned as a

NCV * License Condition

2.C. (11).(b) requires, in part, that

PBAPS shall develop and maintain strategies for addressing large fires and explosions. On May 11, 2010, the licensee discovered that equipment used for a single mitigation strategy, described in

TSG -4.1, Attachment 15, had been removed from its designated location. The finding was assessed in accordance with

IMC 0609, Appendix L, Table 2, and determined to be of very low (Green) safety significance because the finding only impacted an individual mitigation strategy. The licensee restored the equipment and entered the issue into their

CAP as

IR 01068128.

ATIACH [[]]

MENT [[:]]

SUPPLE [[]]

MENTAL [[]]

INFORM [[]]

ATION Enclosure

SUPPLE [[]]

MENTAL [[]]

INFORM [[]]

ATION [[]]

KEY [[]]

POINTS [[]]

OF [[]]

CONTAC T Exelon Generation Company Personnel

T. [[Dougherty, Site Vice President G. Stathes, Plant Manager J. Armstrong, Regulatory Assurance Manager M. Weidman, Acting Engineering Director R. Franssen, Work Management Director J. Kovalchick, Security Manager L. Lucas, Chemistry Manager P. Navin, Operations Director R. Holmes, Radiation Protection Manager T. Wasong, Training Director J. Donell,]]

GL 89-13 Program Manager

C. Esham, System Engineer (Traveling Water Screens) W. Ford, System Engineer (

HPSW )

NRC [[Personnel P. Krohn, Branch Chief F. Bower, Senior Resident Inspector A. Ziedonis, Resident Inspector F. Arner, Senior Reactor Inspector S. Pindale, Senior Reactor Inspector L. Scholl, Senior Reactor Inspector J. Schoppy, Senior Reactor Inspector K. Young, Senior Reactor Inspector]]

LIST [[]]

OF [[]]

ITEMS [[]]

OPENED ,

CLOSED ,

AND [[]]

DISCUS SED Opened None Opened/Closed None Closed None Discussed None Attachment

LIST [[]]

OF [[]]

DOCUME [[]]

NTS [[]]

REVIEW [[]]

ED Section 1 R01: Adverse Weather Protection

SE -16, Revision 5, Grid Emergency

SE -16, Attachment A, Revision 2, Power Team Generation Dispatcher/Power System Director (PTGD/PSD) Communications to Peach Bottom

SE -16, Revision 2, Grid Emergency -Bases

OP -AA-1 08-1 07, Revision 2, Switchyard Control

AA -1 08-107-1 001 , Revision 3, Station Response to Grid Capacity Conditions

AA -1 08-107-1 002, Revision 4, Interface Agreement between Exelon Energy Delivery and Exelon Generation for Switchyard Operations

AA -107, Revision 8, Seasonal Readiness

AA -8003, Revision 1, Interface Procedure between Energy D'elivery (COMED/PECO) and Exelon Generation (Nuclear/Power) for Design Engineering and Transmission Planning Activities McDonald, John

E. ;

PECO Nuclear Station Switchyard Readiness Certification for Summer 2009, Memo to Michael Pacillio; May 15, 2009 Single Line Diagram E1, Revision 45, Station System Health Report,

DC [[Systems (Unit 2 and Unit 3), 10/1/2009 -12/31/2009 System Health Report, 4 kV (Unit 2 and Unit 3), 10/1/2009 -12/31/2009 System Health Report, Emergency Diesels, 10/1/2009 -12/31/2009 System Health Report, Station Blackout, 10/1/2009 -12/31/2009 System Health Report, Substations/Startup Sources, 10/1/2009 -12/31/2009]]

IR 891537, 2009 Summer Readiness Action Item Tracking

IR 918739, Large Transformer Summer Readiness Assessment

AIR A 1714466,

RT -O-031-91 0-3 Chemical Maintenance Treatment for

SW Systems (Spring)

CC -

PB -201, Revision 0, Hazard Barrier Control Program Drawing A-490, Revision 4, Barrier Plans: Circulating Water Pump Structure,

ECT and Diesel Generator Building P-T-07, Revision 2, External Hazards

SE -4, Revision 24, Flood Procedure

SE -4 Bases, Revision 14, Flood Procedure Bases

WO R1134802,

RT -O-031-91 0-3 Chemical Maintenance Treatment for

SW Systems (Spring) Memorandum from Thomas Dougherty to Joseph Grimes, Jr., dated May 14, 2010: Certification for 2010 Summer Readiness

RT -O-040-61 0-2, Revision 16, Outbuilding

HVAC and Equipment Inspection for Summer Operation

AA -107, Revision 8, Seasonal Readiness

IR 1048641, Unit 2

HPCI 30P038 Inboard and Outboard Seal Leak after Run

IR 1053261, 3 'A' Main Transformer Cooling Control Power Breaker Tripped

IR 1054217, Conflict between

PBAPS and Energy Delivery

HVAC Tagging

IR 1057671, Summer Readiness Contingent

EDG [[]]

IR 1065139, Maintenance Plan Closed Summer Readiness Assignments with No Action

IR 1072242, 2B

EOC/RPT Breaker Inspection Results IR 1076476, 'B' Cooling Tower Lift Pump Failed to Start Attachment

Section 1R04: Equipment Alignment

TS Surveillance Requirement Section 3.6.4.3,

SGTS Peach Bottom Protected Equipment Tracking Sheet for

2AE 018 2 'A'

RBCCW [[]]

HX and 'B'

SBGT Fan, 04/14/2010

AA -101-1004, Revision 4, Project Critique U2 'B'

RHR Loop

TSA Section 1 R05: Fire Protection

PF -60, Revision 2, Prefire Strategy Plan, Unit 2 Reactor Building,

RCIC Room -Elevation 88'-0" Fire Zone

60 PF -88, Revision 3, Prefire Strategy Plan, Unit 2 Turbine Building, Lube Oil Tank Room, Elevation 116'-0" Fire Zone 88

PF -12C, Revision 5, Prefire Strategy Plan, Unit 3 Recirculation Pump

MG Set Room, 135' Elevation, Fire Area 12C

PF -78C, Revision 5, Prefire Strategy Plan, Turbine Building Common, Radiation Chemical Area, 116' Elevation, Fire Area 78C

PF -117, Revision 6, Prefire Strategy Plan, Unit 3 Turbine Building, Emergency Battery Switchgear Rooms, 135' Elevation, Fire Area 117

PF -127, Revision 6, Prefire Strategy Plan, Unit 2 Turbine Building, Emergency Battery Switchgear Rooms, 135' Elevation, Fire Area 127 *

IR 1065158, The Legend on Drawing A-484 is Incorrect *

IR 1054609,

PF -78C and

PF -12C Need Door Identification Updated * Indicates

NRC -Identified Section 1R06: Flood Protection Measures

AO [[]]

20A. 1, Temporary Removal and Installation of Flood Barriers in the Reactor Building Drainage System, Revision 13

CR 01048641, U3

HPCI 30P038 Inboard and Outboard Seal Leak After Run

ECP 10-00151, U3

HPCI 30P038 Inboard and Outboard Seal Leak After Run

ECP 09-00160, U3

HPCI Vent Valve Installation T-103, Secondary Containment Control, Revision 16 Section 1R07: Heat Sink Performance Memo from Joseph G. Schoppy to Paul G. Krohn Thru Richard J. Conte dated June 1, 2010, regarding

PBAPS Triennial Heat Sink Performance Inspection Feeder Audits and Self-Assessments 565955,

GL 89-13 Program Functional Area Self Assessment, dated 2/28/07 703604-03,89-13 Program Check-in Assessment, dated 6/28/09 989394, Pre-

NRC Heat Sink Inspection Check-in Assessment, dated 2/24/10 Completed Surveillances

ST -O-032-301-2,

HPSW Pump, Valve and Flow FunctionaliST, performed 1/7/10

ST -O-032-301-3,

HPSW Pump, Valve and Flow FunctionaliST, performed 3/30/10

ST -O-032-635-2,

HPSW System Pressure Test Examination, performed 7/6/08, 8/11/08 & 8/13/08

ST -O-032-635-3,

HPSW System Pressure Test Examination, performed 3/4/08 & 6/7/08 Attachment

ST -0-033-300-2,

ESW , Valve, Unit Cooler, and

ECT Fans Functionali

ST , Performed 1/18/10

ST -0-033-400-2,

ESW Valve

CHK -2-33-514 1

ST , performed 9/26/08

ST -0-033-400-3,

ESW Valve

CHK -3-33-514 1

ST , performed 9/25/09 Design Basis

DBD P-S-02, Revision 12,

ESW System Design Baseline Document

DBD P-S-04, Revision 10,

HPSW System Design Baseline Document

DBD P-S-35, Revision 7, Intake Water System Design Baseline Document

DBD P-T-07, Revision 2, External Hazards Design Baseline Document Drawings 6280-M-315 Shts. 1, 2, 4, & 5, Revisions 68, 55, 53, & 57,

HPSW Systems 6280-M-330 Sh. 1, Revision 35, Emergency Cooling System A-490 Sh. 1, Revision 4, Barrier Plan

CW. Pump Structure

IRs 304543 532363 536910 543926 574158 685077 660310 678567 708222 708248 708255 708261 708284 712457 712465 758678 758690 766675 791321 793791 793803 Miscellaneous 89-13 Program Improvement Plan, dated 6/28/09 794363 798807 805940 822594 823612 824075 824082 846746 849833 896894

899886 920405 933013

2904 1026915

26919 1026921 1058866 1071180 1071347 Equipment Operator Rounds (Unit 2 & 3 Intake Areas), dated 3/29/10 -4/4/10 G3 Wavemaker (G366) Certificate of Conformance, dated 8/8/08 & 11125/08 Inspection Report Susquehanna Electric Company Conowingo Hydroelectric Station, January

2007 PD 145404, Zebra Mussel Recommendations, dated 12/16/09 Risk-Informed Inspection Notebook for

PBAPS Unit 2 and 3, Revision 2.1a Pump Room (Room 802)

MR Walkdown Datasheet, performed 9/22/97, 3/14/01, and 11/22/06

SW (Room 806) MR Walkdown Datasheet, performed 12/16/97, 11/15/99, and Attachment

6/12/04 Unit 2 Circulating Pump Room

MR Walkdown Datasheet, performed 9/22/97, 1/25/02, and 6/28/06 Unit 2 Circulating Water 8creens

MR Walkdown Datasheet, performed 12/16/97, 11/15/99, and 6/12/04 Unit 2 8ervice Water Pump Room

MR Walkdown Datasheet, performed 9/22/97, 1/25/02, and 6/28/06 Unit 3 Circulating Pump Room

MR Walkdown Datasheet, performed 9/22/97, 1/25/02, and 6/28/06 Unit 3 Circulating Water 8creens

MR Walkdown Datasheet, performed 11/15/99 and 6/12/04 Unit 3 8ervice Water Pump Room

MR Walkdown Datasheet, performed 9/22/97, 1125/02, and 6/28/06

PB -430-1 001, 8T-0-033-400-2 Test Results Evaluation (TRE), dated 9/29/08

WO R0931744, Unit 2 & Unit 3 Intake Canal 8i1t Level Readings, performed 4/8/08 *

IR 1071837, E8W Bay Level Measurement Potentially Non-Conservative * Indicates

NRC -Identified

NDE Reports 180-2-32-4 E04 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 8/8/08 180-2-32-4 E05 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/15/09 180-2-32-4 E05 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/15/09 180-2-32-4 R03 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 8/8/08 180-2-32-4 T01 BR, Raw Water Corrosion Ultrasonic Examination Report, dated 8/8/08 180-2-32-5 E03, Raw Water Corrosion Ultrasonic Examination Report, dated 7/9/08 180-2-32-5 E03 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 1/2/09 180-2-32-5 P01, Raw Water Corrosion Ultrasonic Examination Report, dated 7/9/08 180-2-32-10 V01, Raw Water Corrosion Ultrasonic Examination Report, dated 12/8/08 180-2-32-10 V02, Raw Water Corrosion Ultrasonic Examination Report, dated 12/14/08 180-2-32-10 V04, Raw Water Corrosion Ultrasonic Examination Report, dated 12/14/08 180-2-32-10 V05, Raw Water Corrosion Ultrasonic Examination Report, dated 12/9/08 180-2-32-10 V06, Raw Water Corrosion Ultrasonic Examination Report, dated 12/14/08 180-2-32-10 V07, Raw Water Corrosion Ultrasonic Examination Report, dated 12/10/08 180-2-32-10 V08, Raw Water Corrosion Ultrasonic Examination Report, dated 12/10/08 180-3-32-6 F02 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/27/09 180-3-32-6 F02 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/27/09 180-3-32-6 F04 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/27/09 180-3-32-6 V03 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/28/09 180-3-32-6 V03 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 3/4/09 180-3-32-7 E02 U/8, Raw Water Corrosion Ultrasonic Examination Report, dated 3/4/09 180-3-32-7 F01 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 11/24/08 180-3-32-7 V03 0/8, Raw Water Corrosion Ultrasonic Examination Report, dated 4/28/09 180-3-32-10 V01, Raw Water Corrosion Ultrasonic Examination Report, dated 12/14/08 180-3-32-10 V02, Raw Water Corrosion Ultrasonic Examination Report, dated 11/18/08 180-3-32-10 V04, Raw Water Corrosion Ultrasonic Examination Report, dated 11/19/08 180-3-32-10 V05, Raw Water Corrosion Ultrasonic Examination Report, dated 11/25/08 180-3-32-10 V06, Raw Water Corrosion Ultrasonic Examination Report, dated 11/18/08 180-3-32-10 V07, Raw Water Corrosion Ultrasonic Examination Report, dated 12/16/08 180-3-32-10 V09, Raw Water Corrosion Ultrasonic Examination Report, dated 11/18/08 180-3-32-10 V10, Raw Water Corrosion Ultrasonic Examination Report, dated 12/16/08 Attachment

Report No. 0800534.401.RO, G-Scan Assessment of Various Piping Lines, dated 12/31/08 Report No. 0901287.401.R1, G-Scan Assessment of Various Safety Related Piping, December 2009 Operating Experience Generic

SW System Risk-Based Inspection Guide,

NUREG /CR-5865

EGG -2674

NRC Information Notice 2007-06: Potential Common Cause Vulnerabilities in Essential

SW Systems, dated 2/9/07

PBAPS Response to

NRC Information Notice 2007-06, dated 5/15/07 Procedures

AO 32.2-2, Revision 2,

HPSW Injection into the Reactor Vessel

AO 33.1-3, Revision 0,

ESW Bypass Valve Lineup during Shutdown of Chemical Injection System and Return to Normal

AO 33.2, Revision 6,

ESW System Manual Startup and Operations

AO 33.4-2, Revision 2,

ESW System Effluent High Radiation

AO 33.5.A, Revision 1,

RHR lCore Spray Room Cooler Flush

AO 33.6-0, Revision 1,

ESW Pump Discharge Cross-Tie Operation

COL 33.1.A-2, Revision 22,

ESW System (Unit 2 and Common)

EP -AA-1007, Revision 19, Radiological Emergency Plan Annex for

PBAPS [[]]

ER -AA-340, Revision 6,

GL 89-13 Program Implementing Procedure

ER -AA-340-1001, Revision 7,

GL 89-13 Program Implementation Instructional Guide

ER -AA-5400, Revision 2, Buried Piping and Raw Water Corrosion Program Guide

ER -

AA -5400-1 001, Revision 2, Raw Water Corrosion Program Guide

ER -

AA -5400-1002, Revision 1, Buried Piping Examination Guide

RT -0-010-660-2, Revision 10,

RHR [[]]

HX Performance Test

RT -0-031-91 0-2, Revision 17, Chemical Maintenance Treatment for Unit

2 SW Systems

RT -0-033-600-2, Revision 18, Flow Test of

ESW to

ECCS Coolers and Diesel Generator Coolers

SE -3, Revision 19, Loss of Conowingo Pond Procedure

SE -4, Revision 24, Flood Procedure

SO 32.1.A-2, Revision 14,

HPSW System Startup and Normal Operations

SO 32.2.A-2, Revision 7,

HPSW System Shutdown

SO 32.3.A-2, Revision 4,

HPSW Filling and Venting the

HPSW Side of the

RHR [[]]

HX s

SO 32.7.A-2, Revision 11, Placing Unit

2 HPSW Loops in Service Using Unit 3

HPSW Pumps

SO 32.8.A-2, Revision 6,

HPSW System Routine Inspection

SO 33.1.A, Revision 2,

ESW System Setup for Normal Standby Operation

SO 33.8.A, Revision 2,

ESW System Routine Inspection While in Standby Condition

SO 33.8.B, Revision 1,

ESW System Routine Inspection While System is in Operation System Health Reports. Maintenance History & Trending

ESW System Health Report, 4th Quarter 2009

HPSW System Health Report (Unit 2 & Unit 3), 4th Quarter 2009 Intake Silt Level Readings (In Front of Outer Screen Structure), performed 7/31/07

PBAPS [[]]

GL 89-13 Program Health Report, 4th Quarter 2009 & 1 st Quarter

2010 PBAPS Intake Canal Silt Measurements, performed 4/29/93 and 9/4190

RT -M-033-675-2, Unit 2 Pump Intake Structure Inspection and Cleaning, performed 9/28/08

RT -M-033-675-3, Unit 2 Pump Intake Structure Inspection and Cleaning, performed 9/28/09

RT -0-28B-800-2, River Temperature and Flow Monitoring, performed 4/4/10 Waterbox Debris Collected Unit 2 (Trend Data), dated 9/13/02 -1/30/10 Waterbox Debris Collected Unit 3 (Trend Data), dated 5/18/02 -3/15/09 Attachment

WO s C0223901 C0225314 C0225515 C0225614 C0229231 C0229556 C0230346 R0880510 R0916150 A-7 Section 1 R11: Licensed Operator Regualification Program

PSEG -1109R: Evaluation Scenario, Revision 2, performed 05/03/10 Section 1R12: Maintenance Effectiveness

IR 1046838, Tritium High Impact Team Action Tracking

IR 1046838, Activity 6,

FMCT [[]]

IR 1068999, Inspect / Repair / Coat Torus Drain Tank Line and Valve Pit as Required

IR 1085524, 2 'C'

RHR Floating Head Leaking

IR 1080382,

RHR [[]]

DPI -2-10-130" Indication Lowering with 2"

HPSW in Service

IR 882934, 2 'C'

RHR [[]]

HX Post-Maintenance Leakage Observed

IR 882467, Mis-measurement of 2C

RHR [[]]

HX Flange Pit Depth

IR 881590, 2

CE 024

RHR [[]]

HX Tube Side Drain Plate Cover Washed Out

IR 882367, 2 'C'

RHR Lower Outer Shell Gasket Change Learnings

WO C0233586, 2 'C'

RHR [[]]

HX Investigate/Repair/Replace

AR A 1764159,

RHR [[]]

HX A Tube to Shell Differential Pressure

WO C0220077, 2

CE 024 (2 'C'

RHR [[]]

HX ) Replace Lower (Floating) Head

AR A1546765, Testing for 2 'C'

RHR [[]]

HX Leak Section 1 R13: Maintenance Risk Assessments and Emergent Work Control

AO [[]]

50F. 3-3, Revision 5, Main Transformer High Temperature Operation

ARC -320 30C209R A-3, Revision 6, Unit 3 Generator Transformer Trouble

AR A1753947, Intermittent Main Transformer Alarm

AR A 1754304, 3 'A' Main Power Transformer Cooling Control Power Breaker Tripped

WO C0233005, Install Temporary Powerl

TCCP and Replace Breakers E-1-42-A, Sheet 3, Revision 0, Hyundai Transformer Power Control Circuit Diagram E-1-42-A, Sheet 4, Revision 0, Hyundai Transformer Power Control Circuit Diagram

IR 988387, Indicated Winding Temperature Lower Than Actual

IR 1052265, Intermittent Main Transformer Alarm

IR 1053352, 3

AX 001 Lost All Cooling for Approximately 5 Minutes

IR 1053261, 3 'A' Main Transformer Cooling Control Power Breaker Tripped Narrative Logs: April 6, 2010, Night Shift

SO [[]]

50F. 7.A-3, Revision 0, Response to 3 'A' Main Power Transformer General Trouble Alarm

IR 1044591, Procurement of

TN -68 Dry Casks

IR 1060406, Enhancement for Future

ISFSI Evaluation Risk Analysis

IR 1059078, Remove Unirradiated Fuel Channels from Peach Bottom Unit 3 Spent Fuel Pool IR 1064201, High Silica in Refuel Water Storage Tank Attachment

Narrative Logs: April 26, 2010, Night Shift; April 27, 2010, Night Shift; and April 28, 2010, Night Shift

NUREG -0612, Control of Heavy Loads at Nuclear Power Plants

SF -221, Revision 0, Spent Fuel Casks

TN -68-64 Loading and Transport Operations

UFSAR Section 10.3, Spent Fuel Storage

AR A 1730354, Back-up N2 Supply to Automatic Depressurization System Valves

IR 1067597, Backup

ADS Nitrogen Regulators High

OOS [[]]

ST -M-016-400-3, Revision 13, Instrument Nitrogen Check Valve In-Service Test

UFSAR Section 4.4, Nuclear System Pressure Relief

UFSAR Section 10.17, Instrument Air, Service Air, and Instrument Nitrogen Systems Clearance 10000772, Tie-in of Cooper Substation to 220-08 Line

SO 60F.6.A-2, Revision 13, Transferring Reactor Protection System Power Supplies Narrative Logs: May 27,2010, Night Shift P-S-06, Revision 14, Reactor Protection System

TS and Bases Section 3.3.1.1, Reactor Protection System Instrumentation

TS and Bases Section 3.3.8.2, Reactor Protection System Electric Power Monitoring

UFSAR Section 7.2, Reactor Protection System

OTDM associated with

IR 10453119, Repair Decision for Steam Leak on

CV -2-08-4018

IR 1058291, Steam Leak on

CV -2-08-4018 has Returned

IR 1053162, U2

CV -4018 Leak Repair Exceeds Dose Estimate

TRM 3.19, Hydrogen Concentration

UFSAR Section 9.4, Gaseous Radwaste / Off-Gas System Addendum 2 to Specification 6280-M-87, Revision 1, Off-Gas Recombiners for the

PBAPS Units 2 and

3 RT -0-010-630-2, 2C

RHR [[]]

HX Leak Test, performed 06/16/10 M-010-002, Revision 12,

RHR [[]]

HX Maintenance, Section 5.8 (Bubble Test)

ACMP associated with the 2 'C'

RHR [[]]

HX Leak, dated 06/16/10

ACMP associated with the 3 'A'

RHR [[]]

HX Leak, dated 11/07/07

AO 10.9-2, Revision 4, Depressurization of the

RHR System Discharge Piping

AR A1638094,

RHR [[]]

HX 3 'A' Leak

ARC -223 20C203A, E-4, Revision 3, A

RHR [[]]

HX Tube to Shell Lo Pressure

ARC -219 20C209L, D-2, Revision 3,

HPSW Discharge Hi Radiation

CH -426, Revision 13,

HPSW System Sampling and Isotopic Analysis

IR 1080382,

DPI -2-10-130A Indication Lowering with 2 'A'

HPSW in Service

IR 1080296,

ECCS Leakage Tracking -Suggested Improvement Based on

DIER [[]]

IR 1080798,

RHR [[]]

HX Leakage for

10 CFR 100 Compliance Based on Pre-

AST [[]]

IR 1081522,

NDO Page on System Status was Inaccurate

IR 1081844, Overview Sheet Contained Incomplete

OLR Data

IR 1085385, Unexpected Alarm during 2 'C'

RHR Clearance Activities M-315, Sheet 1, Revision 68,

P&ID M-361, Sheet 1, Revision 81,

HPSW [[]]

RHR [[]]

P&ID Narrative Control Room Logs, 06/14/10 Nightshift, 06/15/10 Dayshift, and 06/17/10 Night Shift

OTDM associated with

IR 1080382, 2 'C'

HX Leak Inspection and Repair, dated 06/16/10 Regulatory Guide 1.183, Alternate Radiological Source Terms for Evaluating DeSign Basis Accidents at Nuclear Power Reactors

SI 2D-10-91-A2Cs, Calibration Check of

RHR [[]]

HX Differential Pressure Instruments

DPT 2-10-91A and C,

DPI 2-10-130A and C, and

DPS 2-10-92A and C, performed 08/18/09

SO 32.1.A-2, Revision 14,

HPSW System Startup and Normal Operations

SO 32.3.A-2, Revision 4,

HPSW Filling and Venting the

HPSW Side of the

RHR HXs Attachment

ST -0-032-301-2,

HPSW Pump, Valve and Flow Functional and

1ST [[]]

UFSAR Section 10.7,

HPSW System

UFSAR Section 14.9.2, Current Licensing Basis Dose Evaluation Using Alternate Source Term Section 1R15: Operability Evaluations Operability Evaluation Number 10-002, Revision 0, Engineering Evaluation of Submerged Cable Issue Nuclear Event Report

NC -10-008-Y, Peach Bottom

IR 01048012, Engineering Evaluation of Submerged Cable Issue

IR 01030481,

NRC [[]]

NCV 2009005-01 -Submerged Cables Design Deficiency

IR 01054751,

NOS [[]]

ID Operations Demand for Formal Evaluations for Operability Determinations

IR 01039017,

WANO [[]]

AFI [[:]]

CM Long Term Reliability Management for Wetted Cables

OP -AA-1 08-115, Revision 9, Operability Determinations (CM-1)

ACMP for Unit 3

HPCI Seal Leakage, dated 03/27/10

IR 827889, Air Voids Identified in Various Unit 2

HPCI Lines -P2R17

IR 977203, Air Identified in Unit 3

HPCI Gland Seal Condenser Cooling Water Pipe

IR 1048641, Unit 3

HPCI 30P038 Inboard and Outboard Seal Leak After Run Operability Evaluation Number 10-003, Revision 0, Unit

3 HPCI Seal Leakage M-023-0002,

HPCI [[]]

DVMX Pump Maintenance

WO C0217821, 30P038: Replace

HPCI Pump Mechanical Seals

WO C0232672, 30P038: Perform Seal Replacement

WO C2033235, Install New Vent Valves A1611271, Unit 2 2

AE 018

RBCCW [[]]

HX Suspected Tube Leaks A1552281, Utilization of

2AE 018 with River Temperature Greater than 60 Degrees F

GNF -II Quality Update 2010-001:

GNF Bent Spacer Flow Vanes, dated 04/27/10 Part 21,

GE Hitachi Nuclear Energy: Bent Fuel Spacer Flow Wing

GE Nuclear Energy Corrective Action Request 51275, Bent Flow Tab

GE Nuclear Energy Corrective Action Request 51317, Water Rod Tab to Tab Spacing

GE Nuclear Energy Corrective Action Request 51392, Bent Flow Tab

IR 1074153, Unit 2 Control Rod Drive 38-15

HCU Directional Control Valve Requires Measurement of Adjustment Screw

AR 1761150, Unit 2 Control Rod Drive 38-15 Double Notch

AR A1762149, Unit 2 Control Rod Drive 38-15

HCU Directional Control Valve Requires Measurement of Adjustment Screw

WO M1762149, Obtain 38-15

DCV Measurement for Engineering

IR 1086595, 3 'B' Main Power Transformer Serveron O2 Gas Levels Rising

IR 1082693, 3 'B' Main Power Transformer Serveron Indicated Gas Levels Rising

AR A 1765051, 3 'B' Main Power Transformer Serveron Indicated Gas Levels Rising Section 1 R18: Plant Modifications

ECR 07-00274, Revision 0, Addition of Vent Valves and Reroute of Unit

3 HPCI Main Pump Seal Water Line 50.59 Screening Number

PB-2007-042-S, Revision 0, 50.59 Screening Associated with ECR 07-00274 Attachment

Section 1R19: Post-Maintenance Testing A1552281, Evaluate Max Re-Torque Value for

RBCCW Inlet Flange A1754274, 2 'B'

RBCCW [[]]

HX Internal Tube Leak C0231717-99, Re-Torque 2

AE 018

HX Piping/Flanges C0232897, Investigate Repair as Required C0233136, Correct Deficiencies in

OBG 013 Lower Panel

IR 1057147, Accelerated 2

BE 018

HX Degradation

IR 1060270, Visual Exam of

SW Piping Reveals Suspected Wall Thinning

IR 1062815, Piping Class

JB Gasket Selection Guidance Re: Blue-Gard Sht

IR 1064826, Lube Oil Strainer Spool Pulled Apart During Reassembly

IR 1065180, Bent Drive Pin on Tachometer Drive

IR 1066002, Corroded Connection Discovered

IR 1066427, Followup to E-2 Diesel Exciter Cabinet Cable Corroded

IR 1066888, E23 Breaker

UT Fuse Clip Female End Is Damaged

IR 1067037, Incorporate Permanent Revision

TCS to

SO 52A Procedures M-052-002, Diesel Engine Maintenance, Revision

33 RT -M-052-902-2, E2 Diesel Generator and Fuel Oil Storage Tank Inspection, Revision 6

RT -0-052-252-2, E2 Diesel Generator Inspection Post-Maintenance Functional Test, Revision

26 SO 35.6.B-2, Placing Standby

RBCCW [[]]

HX In-Service and Removing One from Service, Revision 3

ST -I-052-252-2, E-2 Diesel Generator Inspection Post-Maintenance Instrumentation and Logic Test, Revision

9 ST -I-052-262-2, E-2 Diesel Generator Inspection Post-Maintenance Handswitch Logic Test, Revision 4

ST -0-052-412-2, E2 Diesel Generator Fast Start and Full Load Test, Revision

20 ST -I-02A-406-2, Determination of 2 'B' System I End of Cycle-Recirculation Pump Trip Breaker Arc Suppression Response Time, performed

OS /23/10

ST -R-02A-400-2, End of Cycle-Recirculation Pump Trip Response Time Summation Test, Performed

OS /23/10

ACMP , Revision 1, Unit 2 'B' Recirculation Pump Trip Breaker Temperatures

OTDM Issue:

2BA 034 (3401) and (3402) Recirculation Pump Trip Breaker Heating (

IR 867732), Dated May 3,2010

IR 1072366,

PS 02 End of Shift Critique, May 21 st to 23rd D Shift

IR 1072242, 2 'B'

EOC [[]]

RPT Breaker Inspection Results

IR 1072266, New

EOC -

RPT Needs

CRL [[]]

ID and Inspection Prior to Use

RT -0-023-302-3,

HPCI Turbine Overspeed Trip Reset Time Check/Adjustment and

HPCI Auxiliary Oil Pump and Manual Trip Lever Tension Test, performed

OS /22/10 and 06/15/10

IR 1060963, Unit 3

HPCI Turbine Trip Lever Tension in Alert Range

ST -0-014-306-3, Core Spray Loop 'B' Pump, Valve, Flow, and Cooler Functional and Inservice Test, performed 05/19/2010

ST -0-014-355-3, Core Spray Loop 'B' Valve Alignment and Filled and Vented Verification, Performed 05/19/2010

IR 1069554,

MO -3-14-026B-OP Boroscopic Inspection Removed from

WW 1021

IR 1070414,

CV -3-14-034B Needs Travel Stops in Actuator

IR 1070483, Motor Connection Box Hardware Deficiencies

IR 1070880,

PCV -3-14-034B Check Valve Seated

IR 1071092, Air Voids Found During

NDE Exams of Unit 3 Core Spray Piping Attachment

Section 1 R22: Surveillance Testing M-315, Revision 52,

P&ID -

ST -O-032-301-3, Revision 24,

HPSW Systems

HPSW Pump, Valve and Flow Functional and 1

ST , Performed 03/30/10

ST -O-020-560-2/3, Units 2 & 3 -Reactor Coolant Leakage Test

ST -O-010-306-3, Revision 30, 'B'

RHR Loop Pump, Valve, Flow, and Unit Cooler Functional and 1

ST Exelon Submittal of Registration for

IDFSI Casks #48 and #49, dated May 13, 2010 Exelon Submittal of Registration for

IDFSI Casks #50, #51 and #52, dated June 3,

2010 IR 1063429,

ISFSI Cask Vacuum Drying Duration Unexpectedly Exceeded

IR 1065100,

PS 01 End of Shift Critique for Nightshift April 30th,

2010 IR 1065390,

ISFSI Helium Leak Detector Instrument Failed

IR 1066320,

ISFSI Calibration Data Sheet Discrepancy

IR 1067335,

ISFI Vacuum Pump Float Stuck

IR 1067512, Editorial Corrections for

ISFSI [[]]

TN -68

IFSSAR and 212 Report

IR 1068443, Unusual Sheave Rotation Observed on Main Hoist Load Block

IR 1069313,

ISFSI Cask Vacuum Drying Duration Unexpectedly Exceeded

IR 1069468, Maintenance Planning Process Bypassed for Repairs of the Reactor Building Crane

IR 1069549, Historical

FME Found in the Base of the Unit 3 Fuel Prep Machine

SF -900, Revision 7,

ISFSI Abnormal Condition Response

SF -910, Revision 0, Spent Fuel Cask Leakage Location Determination

SI 2P-71-0748-XXC3, Revision 0, Channel Operational Test of

ISFSI Low Pressure Test Switches

PS -70748A and

PS -70748B, Performed 05/03/10

ST -H-071-804-2, Revision 0,

ISFSI Casks

TN -68-52 Surface Dose Rate and Contamination, Performed 04/30/10

ST -M-071-602-2, Revision 0,

ISFSI Casks

TN -68-64 Drying, Backfilling, and Leak Tests, Performed 04/30/10

TN -68 Generic

TS , Amendment Number 1

RT -O-023-302-2,

HPCI Turbine Overspeed Trip Reset Time Check 1 Adjustment and

HPCI Auxiliary Oil Pump and Manual Trip Lever Tension Test, performed 04/24/10, 04/30/10, and 05/22/2010 *IR 1068090,

HPCI Procedures

RT -O-023-302-2(3) should be Revised

IR 1067843,

RT -O-023-302-3 System Manager Data for past 3 years for

RT -O-023-302-2(3)

GE [[]]

SIL 392, Part 1, Revision 1, Improved

HPCI Turbine Mechanical Hydraulic Trip Design

GE [[]]

SIL 392, Part 2, Revision 1, Improved

HPCI Turbine Mechanical Hydraulic Trip Design

GE [[]]

RICSIL 37,

HPCI and

RCIS Turbine Overspeed Trip Tappet Assembly Binding * Indicates

NRC -Identified Section

1 EP 6: Drill Evaluation

EP -M-1007, Revision 19, Exelon Nuclear Radiological Emergency Plan Annex for

PBAPS [[]]

IR 1063970,

EP 01 Performance Issues Identified in 4/12

EP Drill

IR 1063984, Drill Performance S/L Notification of Site Evacuation

FMT Briefing Attachment

PBAPS 2010 Team 5

DEP Drill Evaluation Report

PBAPS May 10, 2010 Training Drill Controller Manual Section 40A1: Performance Indicator (

PI ) Verification

LS -

AA -2001, Revision 13, Collecting and Reporting of

NRC Performance Indicators Data

LS -AA-2090, Revision 4, Monthly Data Elements for

NRC [[]]

RCS Specific Activity

LS -

AA -21 00, Revision 5, Monthly Data Elements for

NRC [[]]

RCS Leakage

ST -O-020-560-2, Revision 12, Reactor Coolant Leakage Test (sample of completed test records)

ST -O-020-560-3, Revision 14, Reactor Coolant Leakage Test (sample of completed test records)

ST -C-095-864-2, Off Gas Monitor Response and Release Rate Verification by a Grab Sample

ST -C-095-864-3, Off Gas Monitor Response and Release Rate Verification by a Grab Sample

ST -C-095-820-2, Determination of Dose Equivalent f

JC i/g 1-131 in Primary Coolant

ST -C-095-820-3, Determination of Dose Equivalent f

JC i/g 1-131 in Primary Coolant

CH -407, Sampling of Reactor Water

CH -C-601, Determination of Dose Equivalent 1-131 Section 40A2: Identification and Resolution of Problems *

IR 1 062071 ,

FSAR Change not Implemented per License Amendment

IR 1080647, 1Q10 Station Trend Review

IR 1023827, Unit 2 Control Rod (CR) Scram Times -CR Slowlinoperable

IR 1008530, Iso phase Bus Loss of Cooling Load Reduction

IR 1026936, Operations Lessons Learned frorn 2 'A' Recirc Pump Trip

IR 1020648, Common Cause Analysis for Equipment Related Reactivity Events

IR 1060396, Exelon

R. 1 Performance Indicator -Adverse Trend in

PIR -Evaluation Area

IR 707459,

EDG [[]]

GL 89-13 Testing Issues

IR 479833, No Calculation for

RCIC Oil Cooler Performance during

SBO [[]]

IR 453385, Low Margin in

HPCI [[]]

NPSH Calculation 182470-M-001

IR 452577, Lack of Allowance for Frequency Variation in

EDG Load Calc.

IR 451634,

NPSH Margin for

FSSD in Re-Rate Report

IR 705464,

EQ Temperature Affects not Considered in

MCC Control Circuit Voltage Drop

IR 1059363, Glycol Chiller Deficiencies Irnpacting Equipment Reliability

IR 1061573, Security Department Training/Qualification Failures -

CCA [[]]

IR 1044318, Corrective Actions from

IR 808183 Determined to be Ineffective

IR 1024952, Increased Trend in Tritium Levels in

MW -PB-26

IR 1032576, Elevated Tritium in Pre-Developed New Well #27 Water

IR 1030952, Unit

3 CST Heating Coil Leak, Tritium Source in Aux Steam

IR 808191, Evaluation of Unit 1 Tritium -ACE

IR 808183, Evaluation for Well #4 Tritium Increase -

ACE [[]]

IR 1086963, Torus Dewatering Tank (

TDT ) Drain valve Found Degraded

IR 1086966, Concrete Drain Valve Pit is Uncoated

IR 1087143, Coat/Seal the Unit 3 Band D

RHR Sumps

IR 1087145, Pressure Test the 3D

RHR Sump Discharge Line

IR 1087148, Perform Remote Inspection of the Recombiner Pipe Tunnel

IR 762371,

URI for Load Tap Changer Licensing Basis

IR 1002703, Insufficient Post-Loss-of-Coolant Accident

MCC Voltage for E234-T-B (6023) Attachment

IR 1081198, Low Voltage at

IR 1081472, Low Voltage at

IR 1081490, Low Voltage at

IR 1081496, Low Voltage at

IR 1081503, Low Voltage at

IR 1081505, Low Voltage at

IR 1081512, Low Voltage at

IR 1081546, Low Voltage at

IR 1081554, Low Voltage at

IR 1081563, Low Voltage at

IR 1081572, Low Voltage at

IR 1081589, Low Voltage at

IR 1081597, Low Voltage at

IR 1081601, Low Voltage at

IR 1081605, Low Voltage at

IR 1081611, Low Voltage at

NCV 2009005-01 -Submerged Cables Design Deficiency

IR 1030481,

NRC [[]]

IR 1081636,

CM [[]]

ECR Needed for Modifications for Electrical Manholes

IR 1048012, Engineering Evaluation of Submerged Cable Issue

IR 1022206, 480V Safety Related Cable Identified Submerged in Manhole

35 IR 1053615,

MSOPS 2 '0' -Failure to Trip Rx Recirc Pump on Loss of

RBC [[]]

IR 985851, Parent

IR -Coordinate Fleet Actions for

RG 1.189/NEI 00-01

IR 1063169,

MSOPS -MSO Scenarios Not Applicable to Peach Bottom

IR 1047196, Fire Protection -Multiple Spurious Operations

IR 1042832, 'B' Master Trip Solenoid Light Took 90 Seconds to Light

IR 1070301,

SV -2-01D-4896A Main Turbine

MTSV A Slow to Trip

IR 1076001, Unit

2 MTSV Harder to Reset than Normal

IR 1086613,

SV -2-01D-4896B Master Trip Solenoid Valve Not Energized

IR 1086985,

OCC Open Action Items

OP -AA-102-103, Revision 3,

OWA Program

OP -AA-102-103,

OWA and Challenges -Official List, dated 06/03/10

OP -AA-102-103,

OWA and Challenges -Closed List, dated 06/03/10

OP -AA-102-103-1001, Revision 2, Operator Burden and Operationally Significant Decisions Impact Assessment Program

PB -112-1 01-1 007, Reactor Building Equipment Operator Shift Turnover Checklist, Unit 3, 06/25/10 Night Shift