IR 05000334/2011004

IR 05000334/2011004; 05000412/2011004; 07/01/2011-09/30/2011; Beaver Valley Power Station, Units 1 and 2; Routine Integrated Report

ML11306A204
Person / Time
Site:	Beaver Valley
Issue date:	11/02/2011
From:	Eugene Dipaolo NRC/RGN-I/DRP/PB6
To:	Harden P FirstEnergy Nuclear Operating Co
DiPaolo E
References
IR-11-004
Download: ML11306A204 (25)

Text

September 30, 2011

SUBJECT:

BEAVER VALLEY POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000334/201 1004 AND 05000412t201 1001

Dear Mr. Harden:

On September 30, 2011, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Beaver Valley Power Station Units 1 and 2. The enclosed integrated inspection report documents the inspection results, which were discussed on October 12,2011, with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, no findings were identified.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, and its enclosures, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http:i/www.nrc.qov/readinq-rmiadams.html (the Public Electronic Reading Room). We appreciate your cooperation. Please contact me at 610-337-5200 if you have any questions regarding this letter.

Sincerely,

/RA/

Eugene M. DiPaolo, Acting Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-334, 50-412 License Nos: DPR-66, NPF-73

Enclosures:

Inspection Report 05000334/2011004; 0500041212011004 M Attachment: Supplemental lnformation

REGION I==

50-334, 50-412 DPR-66, NPF-73 05000334/201 1 004 and 05000 41 21 2U I OA4 FirstEnergy Nuclear Operating Company (FENOC)

Beaver Valley Power Station, Units 1 and 2 Shippingport, PA 15077 July 1,2011through September 30,2011 D. Spindler, Senior Resident Inspector E. Bonney, Resident InsPector T. Moslak, Sr. Health Physicist (DRS)

J. Brand, Reactor lnsPector (DRS)

T. Burns, Sr. Reactor lnspector (DRS)

Eugene M. DiPaolo, Acting Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure

TABLE of

SUMMARY OF FINDINGS

tR 0500033 4t2011004, tR 0500041 2l2o11OO4; A710112011 - 0913012011; Beaver Valley Power

Station, Units 1 & 2; Routine Integrated Report The report covered a 3-month period of inspection by resident inspectors, regional reactor inspeciors, and a regional health physics inspector. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 4, dated December 2006.

No findings were identified.

REPORT DETAILS

Summarv of Plant Status:

Unit 1 began the inspection period at 100 percent power. On July 21, the unit was down-powered to 94 percent due to condenser hotwell temperature limitations during hot weather conditions and returned to full power on July 22. The unit remained at 100 percent power for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent power and remained at full power throughout the inspection period.

1R01 Adverse Weather Protection

.1 Seasonal Susceptibilitv

a. Inspection Scope

The inspectors reviewed hurricane readiness of Unit 1 and Unit 2 river water/service water systems for extreme weather conditions; specifically, hurricanes, high winds, high water level, and other relevant severe weather events. The inspection verified that the indicated equipment, its instrumentation, and supporting structures were configured in accordance with FENOC's procedures and that adequate controls were in place to ensure functionality of the system. The inspectors reviewed licensee procedures and walked down the system. Documents reviewed for each section of this inspection report are listed in the Attachment.

b.

Findinqs No findings were identified.

==1R04 Equipment Aliqnment

==

.1 Partial Svstem Walkdowns

a. Inspection Scope

The inspectors performed three partial equipment alignment inspections during conditions of increased safety significance, including when redundant equipment was unavailable during maintenance or adverse conditions. The partial alignment inspections were also completed after equipment was recently returned to service after significant maintenance. The inspectors performed partial walkdowns of the following syltems, including associated electrical distribution components and control room panels, to verify the equipment was aligned to perform its intended safety functions:

.

Unit 1, 'A' Motor driven Auxiliary Feed Water (AFW) pump and turbine driven AFW pump during testing of the 'B' motor driven AFW pump on August 10 o Unit 2,'A'Train Service Water System (SWS) lineup during'B'train SWS Limiting Condition for Operation (LCO) entry on August 15

.

Unit 2, 125 Volt batteries (2-1,2-2, and 2-3) during 2-4battery individual cell voltage degradation on August 11 b.

Findinqs No findings were identified.

==1R05 Fire Protection

==

.1 Quarterlv Sample Review

a. Inspection Scope

The inspectors reviewed the conditions of the fire areas listed below, to verify compliance with criteria delineated in Administrative Procedure 112-ADM-1900, "Fire Protection," Rev. 23. This review included FENOC's control of transient combustibles and ignition sources, material condition of fire protection equipment including fire detection systems, water-based fire suppression systems, gaseous fire suppression systems, manual firefighting equipment and capability, passive fire protection features, and the adequacy of compensatory measures for any fire protection impairments.

.

Unit 1, Relay Room (Fire Area CR-3)

.

Unit 1, Process Rack Room (Fire Area CR-4)

.

Unit 1, Battery Rooms 1&3 (Fire Area ES-1)

.

Unit 1, Control Room HVAC Equipment Room (Fire Area CR-2)

.

Unit 2, Fuel Building (Fire Area FB-1)b.

Findinqs No findings were identified.

1R06 Flood Protection Measures

a.

lnspection Scope The inspectors reviewed a sample of internal flood protection measures for equipment in Unit 2, 2-2 and 2-4 Battery Rooms.

This review was conducted to evaluate FENOC's protection of the enclosed safety-retated systems from internalflooding condition. The inspectors performed a walkdown of the area, reviewed the UFSAR, related internal flooding evaluations, and other related documents. The inspectors examined the as-found equipment and conditions to ensure that they remained consistent with those indicated in the design basis documentation, flooding mitigation documents, and risk analysis assumptions.

b.

Findinqs No findings were identified.

1R1 1 Licensed Operator Requalification Proqram (71111.11)

.1 Resident Inspector Quarterlv Review

a. Inspection Scope

The inspectors observed a sample of Unit 1 licensed operator simulator training on August 18. The inspectors evaluated licensed operator performance regarding command and control, implementation of normal, annunciator response, abnormal, and emergency operating procedures, communications, technical specification review and compliance, and emergency plan implementation. The inspectors evaluated the licensee staff training personnel to verify that deficiencies in operator performance were identified, and that conditions adverse to quality were entered into the licensee's corrective action program for resolution. The inspectors reviewed simulator physical fidelity to assure the simulator appropriately modeled the plant control room. The inspectors verified that the training evaluators adequately addressed that the applicable training objectives had been achieved.

b.

Findinqs No findings were identified.

1R12 Maintenance Effectiveness

a. Inspection Scope

The inspectors evaluated Maintenance Rule (MR) implementation for the issues listed below. The inspectors evaluated specific attributes, such as MR scoping, characterization of failed structures, systems, and components (SSCs), MR risk characterization of SSCs, SSC performance criteria and goals, and appropriateness of corrective actions. The inspectors verified that the issues were addressed as required by 10 CFR 50.65 and the licensee's program for MR implementation. For the selected S-SCs, the inspectors evaluated whether performance was properly dispositioned for MR category (aX1) and (a)(2) performance monitoring. MR System Basis Documents were also reviewed, as apProPriate.

.

2ASystem Station Service Transformer (SSST) availability monitoring during tap changer rePair.

b.

Findinqs No findings were identified.

1R13 Maintenance RiskAssessmentand EmerqentWork Control

a. Inspection Scope

The inspectors reviewed the scheduling and control of maintenance activities, and evaluated their effect on overall plant risk. This review was conducted to ensure compliance with applicable criteria contained in 10 CFR 50.65(a)(4).

r Unit 1, CR 11-98009, "Probabilistic Risk Assessment (PRA) not performed prior to clearance posting on PRA component" on July 21

.

Unit 1, PRA late update to control room on August 1

.

Unit 1 and Unit 2, Maintenance risk assessment during a hot weather alert the week of July 18

.

Unit 2, 'A' Component cooling water (CCP) pump maintenance activities window extended and associated PRA review on September 20 b.

Findinos No findings were identified.

1R15 Operabilitv Evaluations

a. Inspection Scope

The inspectors evaluated the technical adequacy of selected immediate operability determinations (lOD), prompt operability determinations (POD), or functionality assessments (FA), to verify that determinations of operability were justified. In addition, the inspectors verified that technical specification (TS) limiting conditions for operation (LCO) requirements and UFSAR design basis requirements were properly addressed.

ln addition, the inspectors reviewed compensatory measures implemented to ensure the measures worked and were adequately controlled.

o Unit 1, Urgent rod control alarm during Rod Insertion testing, CR 2011-00582 r Unit 1, Turbine driven auxiliary feedwater pump [1FW-P-2] high oil level in outboard bearing as documented in CR '11-97241

.

Unit 1, Part 21 evaluation of installed Velan globe valve, CR 1 1 -97892 o Unit 2, Primary component cooling water pumps oil bubbler design and level settling as documented in wos 20011932000, 20011933000, 20011933000, and

===200028524 o Unit 2, 'B' SWS line pinhole leak prompt operating determination, as documented in cR 2011-00581 o Unit 2, 2A SSST Manual tap changer relay function restoration to exit TS LCO 3.8.1 b.

Findinqs No findings were identified.

I

1R18 Plant Modifications

a.

Inspection Scooe The inspectors reviewed the following permanent and temporary modifications based on risk significance. The permanent modifications and associated 10 CFR 50.59 screenings were reviewed against the system design basis documentation, including the UFSAR and the TS. The inspectors verified that attributes and parameters within the design documentation were consistent with required licensing and design bases, as well as credited codes and standards, and walked down the systems to verify that changes described in the package were appropriately implemented. The inspectors verified the temporary modifications were implemented in accordance with Administrative (ADM)

Procedure, 112-ADM-2028, "Temporary Modifications," Rev. 6. The inspectors also verified the post-modification testing was satisfactorily accomplished to ensure the system and components operated consistent with their intended safety function.

o Engineering Change Package 11-0426-00,1-2 Emergency diesel generator (EDG)

Start on Loss of Voltage relay replacement b.

Findinqs No findings were identified.

1R19 Post-Maintenance Testino

a. Inspection Scope

The inspectors reviewed the activities listed below to determine whether the post-maintenance tests (PMT) adequately demonstrated that the safety-related function of the equipment was satisfied given the scope of the work, and that operability of the system was restored. In addition, the inspectors evaluated the applicable acceptance criteria to verify consistency with the design and licensing bases, as well as TS requirements. The inspectors witnessed the test or reviewed test data to verify results adequately demonstrated restoration of affected safety functions. The inspectors also verified that conditions adverse to quality were entered into the corrective action program for resolution.

. Unit 1, 1-2 EDG Undervoltage start relay replacement o Unit 2,2A SSST Tap charger rePair o Unit 2, Turbine driven auxiliary feedwater pump I2FWE-P221 trip throttle valve stem coupling repair o Unit 2, 2-4125 Volt battery jumper installation, 2MSP-E-39-300, Vital Bus Weekly Battery Inspection b.

Findinqs No findings were identified.

I

1R22 Surveillance Testinq

a. Inspection Scope

The inspectors witnessed the performance of or reviewed test data for the seven Operation Surveillance Test (OST) and Maintenance Surveillance (MSP) packages listed below. The reviews verified that the equipment or systems were being tested as required by TS, the UFSAR, and procedural requirements. The inspectors also verified that the licensee established proper test conditions, that no equipment pre-conditioning activities occurred, and that acceptance criteria were met.

. Unit 1, l 05T-36.2, Diesel Generator No. 2 Monthly Test on August 3 (in-service test)o Unit 1, l OST-13.2, Quench Spray Pump [1OS-P-1 B] Test on August 4

. Unit 1, lOSf -24.3, Motor Driven Auxiliary Feed Pump Test [1FW-P-3B] on August 10 o Unit 2, 2OST-30.2, Service Water Pump [25SWS.P21A] Test on August 25

. Unit 2,2OST-15.2, Primary Component Cooling Water Pump I2CCP*P21BI Test on July 17

. Unit 2,2OST-1.128, Safeguards Protection System Train 'B' SIS Test on August 3 o Unit 2,2OST-13.1, Quench Spray Pump [2QSS*P21A] Test on September 22 b.

Findinqs No findings were identified.

Gornerstone: Emergency Preparedness [EP]

1EP6 Drill Evaluation

a. Inspection Scope

The inspectors observed an emergency preparedness mini-drill and Unit 1 licensed-operator simulator evaluation on August 18. Senior licensed-operator performance regarding event classifications and notifications were specifically evaluated. The inspectors evaluated the simulator-based scenario that involved multiple, safety-related component failures and plant conditions that would have warranted emergency plan activation, emergency facility activation, and escalation to the event classification of Alert. The licensee planned to credit this evolution toward Emergency Preparedness Drill/Exercise Performance (DEP) Indicators, therefore, the inspectors reviewed the applicable event notifications and classifications to determine whether they were appropriately credited, and properly evaluated consistent with Nuclear Energy Institute (NEl) gg-02, Rev. 6, "Regulatory Assessment Performance Indicator Guideline." The inspectors reviewed licensee evaluator worksheets regarding the performance indicator acceptability, and reviewed other crew and operator evaluations to ensure adverse conditions were appropriately entered into the Corrective Action Program. Other documents utilized in this inspection include the following:

.

112-ADM-1 1 1 1, Rev. 4, "NRC EPP Performance Indicator lnstructions"

.

112-ADM-1111.F01, Rev. 3, "Emergency Preparedness Performance Indicators Classifications/Notifications/PARS" o EpP-l-1a/b, Rev. l4, "Recognition and Classification of Emergency Conditions;"

.

112-EPP-l-2, Rev. 35, "Unusual Event"

.

112-EPP-l-3, Rev. 33, "Alert"

.

112-EPP-l-4, Rev. 33, "Site Area Emergency" and

.

112-EPP-I-5, Rev. 34, "General Emergency" b.

Findinqs No findings were identified.

RADIATION SAFETY

Gornerstone: Public Radiation Safety [RS]

2RS0 7 Radioloqical Environmental Monitorinq Proqram (REMP)

a.

Inspection ScoPe During the period July 1 8 - 21,2011, the inspector conducted the following activities to verifylhat the licensee implemented the radiological environmental monitoring program (REMP) consistent with the Site Technical Specifications and the Off-Site Dose Calculation Manual (ODCM) to validate that radioactive effluent releases met the design objectives of Appendix I to 10 CFR Part 50.

This inspection activity represents completion of one

(1) sample relative to this inspection area.

REMP Inspections:

The inspector reviewed the 2009 and 2010 Annual Radiological Environmental Operating Reports and the 2010 REMP Land Use Census Report to verify that the environmental monitoring programs were implemented as required by the ODCM.

The inspector walked down nine (of ten) air sampling stations (Nos. 13, 27, 28, 29B, 30, 32, 46.1, 47, S1), two (of three) milk sampling stations (Nos. 25, 96), three (of three)surface water sampling stations (Nos. 2.1, 5, 49A), two (of two) drinking water stations (Nos. 4, 5), and seventeen (of fifty) thermoluminescent (TLD) monltoryg stations (ttos. t0, i3, i4, 15, 27, 28',298; 30, 32, 45, 45.1, 46, 46.1, 47,51, 60, 72) to determine if sampling was conducted as described in the ODCM and associated procedures, and to evaluate the sampling equipment material condition' As part of the walkdown, the inspector observed the technician collect and prepare for analysis air particulate/iodine filter samples, milk samples, and water samples; and verified that environmental sampling was representative of the release pathways as specified in the ODCM, and that sampling techniques were in accordance with approved procedures.

Based on direct observation and review of records, the inspector verified that the primary and redundant meteorological instrumentation was operable, calibrated, and maintained in accordance with the gu'rdance contained in the UFSAR, NRC Regulatory Guide 1'23,

,

and the licensee procedures. The inspector verified that the meteorological data readout and recording insiruments in the control room and at the tower were operable for wind direction, win-d speed, and delta temperature. The inspector confirmed that redundant instrumentation was oPerable.

The inspector reviewed the calibration and maintenance records for ten

(10) air samplers and observed the technician verifying the calibration of three water compositors.

The inspector reviewed Condition Reports, a Nuclear Oversight audit report (MS-C-10-08-02), and Nuclear Oversight field observation reports, addressing implementation of REMP requirements, to evaluate the threshold for which issues are entered into the corrective action program, the adequacy of subsequent evaluations, and the effectiveness of the resolution. The inspector also reviewed monthly RETS/ODCM effluent occurrence reports to evaluate the adequacy and timeliness of performance indicator information.

The inspector reviewed the results of the licensee's quarterly laboratory cross-check program to verify the accuracy of the licensee's environmental air filter, charcoal cartridge, water, and milk sample analyses.

The inspector reviewed changes made by the licensee to the ODCM as a result of changes to the land use census or sampler station modifications since the last inspection. The inspector also reviewed technicaljustifications for any change in sampling location (or frequency) and verified the licensee performed the reviews required to ensure that the changes did not affect its ability to monitor the radiological condition of the environment.

The inspector walked down the on-site groundwater monitoring wells and discussed programmatic enhancements that are being made in identifying and controlling spills/leaks to groundwater with the Chemistry Department Manager.

b.

Findinqs No findings were identified.

OTHER ACTIVITIES

IOAI

4OA1 Performance lndicator Verification (7 1 151)

.1 Mitiqatinq Svstem Performance lndex (6 samples)

a.

lnspection Scope The inspectors reviewed FENOC's submittal of the Mitigating Systems Performance Index for the following systems for the period of September 1, 2010 through August 31, 2011:

. Unit 1 Auxiliary Feedwater System

. Unit 1 Residual Heat Removal System

. Unit 1 Support Cooling Water System o Unit 2 Auxiliary Feedwater System

. Unit 2 Residual Heat Removal System

. Unit 2 Support Cooling Water System a.

To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6. The inspectors also reviewed FENOC's operator narrative logs, condition reports, mitigating systems performance index derivation reports, event reports and NRC integrated inspection reports to validate the accuracy of the submittals.

Occupational Exposure Control Effectiveness===

lnspection Scope The inspector reviewed implementation of the licensee's Occupational Exposure Control Effectiveness Performance Indicator (Pl) Program. Specifically, the inspector reviewed condition reports, and associated documents, for occurrences involving locked high radiation areas, very high radiation areas, and unplanned exposures against the criteria specified in Nuclear Energy lnstitute (NEl) 99-02, Regulatory Assessment Performance lndicator Guideline, to verify that all occurrences that met the NEI criteria were identified and reported as performance indicators. This inspection activity represents the completion of one

(1) sample relative to this inspection area; completing the annual inspection requirement.

Findinqs No findings were identified.

RETS/ODCM Radioloqical Effluent Occurrences (1 sample)

lnspection Scope The inspector reviewed relevant effluent release reports for the period April 1,2010 through June 1,2011, for issues related to the public radiation safety performance indicator, which measures radiological effluent release occurrences that exceed 1.5 mrem/quarter whole body or 5.0 mrem/quarter organ dose for liquid effluents; 5 mrads/quarter gamma air dose, 10 mrad/quarter beta air dose, and 7.5 mrads/quarter for organ dose for gaseous effluents. This inspection activity represents the completion of one

(1) sample relative to this inspection area; completing the annual inspection requirement.

Findinqs No findings were identified.

Problem ldentification and Resolution (71152 - 2 samples)

Routine Review of Problem ldentification and Resolution Activities lnspection Scope As required by Inspection Procedure71152, "Problem ldentification and Resolution," the inspectors routinely reviewed issues during baseline inspection activities and plant status reviews to verify that FENOC entered issues into the corrective action program at an appropriate threshold, gave adequate attention to timely corrective actions, and

.3 a.

b.

4c.42

.1 a

identified and addressed adverse trends. In order to assist with the identification of repetitive equipment failures and specific human performance issues for followup, the inspectors performed a daily screening of items entered into the corrective action program and periodically attended condition report screen meetings.

Findinqs No findings were identified.

Semi-Annual Trend Review Inspection Scope The inspectors reviewed site trending results for the time period January through June 2011, to determine if trending was appropriately performed and evaluated by FENOC.

This review covered the site trending program under FENOC's Integrated Performance Assessment process, and included a sample of self-assessments from the several organizations at Beaver Valley. This review verifies that existing trends were (1)appropriately captured and scoped by applicable departments,

(2) consistent with the inspectors' assessment from the daily CR and inspection module reviews and

(3) not indicative of a more significant safety concern. Additionally, the inspectors verified the performance of site trending against NOP-LP-2001, Rev. 23, "Condition Report Process," and NOBP-LP-2018, Rev. 05, "lntegrated Performance Assessment

/Trending." The inspectors also reviewed quarterly Quality Assurance reports and issues captured in the Activity Tracking database to identify issues and trends to evaluate during the inspection.

Findinqs and Observations No findings were identified. However, an adverse trend was identified regarding procedure usage by operations and maintenance personnel. Three specific instances of inadequate procedural adherence were noted. One instance resulted in an inadvertent auxiliary feedwater injection at power (CR 1 1-97132). A second instance resulted in lost data gathered during surveillance testing because procedural steps were marked "N/A" (CR 11-97062). Athird instance resulted in an inadvertent actuation of Unit 2 auxiliary feedwater while shutdown (CR 11-90528). The licensee has identified a trend in inadequate procedure usage and has entered the issue into the corrective action process (CR 11-97126).

Annual Sample: Review of On-Line Risk Assessment and Manaqement Inspection Scooe The inspectors reviewed FENOC CRs related to PRA components and, combinations of components removed from service and thereby unavailable during the scheduled work week. The CRs were evaluated for accuracy and comprehensiveness of problem identification, thoroughness of cause determination and effectiveness and timeliness of corrective actions Twelve CRs were evaluated for compliance with NOP-OP-1007, Revision 10, "Risk Management",ll2ADM-2003, Revision 4, "Risk Management Program", and %-ADM-0804, Revision 9, "On-line Risk Assessment and Management". ln addition to the b.

documentation review, the inspectors interviewed the On Line Work Week Manager and PRA Analyst to assess overall coordination and management of scheduled activities involving PRA components to effectively manage plant risk.

Findinqs and Observations No findings were identified. The inspectors determined that the implementation of the "Risk Management Program" was being managed to effectively apply the PRA modelto risk management decision making to ensure that planned work activities on PRA components have been evaluated for PRA impact.

Followup of Events and Notices of Enforcement Discretion (71153 - 3 samples)

Plant Event Review Inspection Scope For the plant events below, the inspectors reviewed and/or observed plant parameters, reviewed personnel performance, and evaluated performance of mitigating systems.

The inspectors communicated the plant events to regional personnel and compared the event details with criteria contained in IMC 0309, "Reactive Inspection Decision Basis for Reactors," for consideration of additional reactive inspection activities. As applicable, the inspectors verified that FENOC made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR Parts 50.72 and 50.73. The inspectors reviewed FENOC's follow-up actions related to the events to assure that FENOC implemented appropriate corrective actions commensurate with their safety significance.

.

Abnormal Operating Procedure 1/2OM-53C.4A.75.3, Acts of Nature-Earthquake, entry and followup on August 23 due to seismic activity Findinqs No findings were identified.

(Closed) Licensee Event Report 05000412/2011-002-00: Auxiliary Feedwater System Vent Line Weld Crack Results in Technical Specification Required Plant Shutdown and Valid Reactor Protection System/Engineered Safety Feature Actuation System Actuations On April g,2011, FENOC discovered an active leak during power ascension on the 'A' steam generator (SG) feedwater injection header, which involved entry into TS 3.7.5.

During-the TS required shutdown, 'A' SG water level reached a low level requiring a reactor trip. The inspectors determined that no new findings of significance were identified isee 1R0500041212011009 NCV 05000334, 41212011009-01)' This LER is closed.

(Closed) Licensee Event Report 05000412/2011-003-09: Automatic Actuation of Standby Sen tce Water Pumps Following Unexpected Service Water Pump Trip On June 10,2011, the in-service 'A' service water pump motor failed, resulting in the automatic start of the 'A' and 'B' standby service water pumps due to low service water 40A3

.1 a.

b.

.2.3

40A6 header pressure. The inspectors determined that no new findings of signiflcance were identified (see 1R0500041212011009 NCV 0500041212011009-02). This LER is closed.

Manaqement Meetinqs Radioloqical Environmental Monitorinq Proqram (REMP)

The inspector presented the inspection results of 2RS07 to Dan Murray, Director of performance lmprovement, and other members of FENOC staff, at the conclusion of the inspection on July 21. No proprietary information is presented in this report' Quarterlv Inspection RePort Exit On October 12, the inspectors presented the normal baseline inspection results to Paul Harden. Site Vice President, and other members of the licensee staff. The inspectors confirmed that proprietary information was not retained at the conclusion of the inspection period.

.1 ATTACHMENT: SUPPLEMENTAL I NFORMATION

Licensee personnel S. Baker M. Banko G. Cacciani S. Checketts R. Dinello R. Ferrie B. Furdak R. Groggett P. Harden G. Henzler L. Huyler D. Jones M. Kienzle M. Librich R. Lieb R. Lubert C. Makawka M. Manolarus J. Mauck D. McBride C. McFeaters T. McGourty J. Miller M. Mitchell D. Murray D. Neidlinger A. Reardon J. Redmond L. Renz D. Salera D. Schwer B. Sepelak B. Tuite Other Personnel L. Ryan

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Radiation Protection Manager

Environmental & Chemistry Supervisor

Design Engineer

Operations Manager

Environmental Field Specialist

Supervisor, Nuclear Relay Maintenance

Fleet Oversight Assessor

Advanced Nuclear SPecialist

Site Vice President

lnstrumentation & Control Technician

Advanced Nuclear Specialist

Staff Nuclear Engineer

AFW System Engineer

Reactor Operator

Director, Site Operations

Supervisor, Electrical Design

Staff Nuclear Specialist

Director of Engineering

Regulatory Compliance

Fleet Oversight Manager

Manager, Operations

Flood Program Engineer

Fire Marshall

Supervisor, Work Planning

Director, Performance lmprovement

Senior Quality Technician

Staff Nuclear Engineer

Staff Nuclear Engineer

Advanced Nuclear SPecialist

Chemistry Supervisor

Superintendent, Operations Services

Supervisor, Regulatory ComPliance

Manager, RegulatorY ComPliance

Inspector, Pennsylvania Department of Radiation Protection

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Closed

05000334/2010002-01 0500041 212011002-00

050004121201 1003-00 LER LER LER 270 Degree Circumferential Flaw Found on Residual Heat Removal System Drain Valve Socket Weld (lR

05000334/2011002 Section 4OA3)

Auxiliary Feedwater System Vent Line Weld Crack Results in Technical Specification Required Plant Shutdown and Valid Reactor Protection System/Engineered Safety Feature Actuation System Actuations (Section 4OA3)

Automatic Actuation of Standby Service Water Pumps Following Unexpected Service Water Pump Trip (Section 4OA3)