IR 05000334/2009004

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IR 05000334-09-004 and 05000412-09-004, on 07/01/09 - 09/30/09, for Beaver Valley Power Station - NRC Routine Integrated Inspection Report
ML093090281
Person / Time
Site: Beaver Valley  FirstEnergy icon.png
Issue date: 11/05/2009
From: Bellamy R
NRC/RGN-I/DRP/PB6
To: Harden P
FirstEnergy Nuclear Operating Co
BELLAMY, RR
References
IR-09-004
Download: ML093090281 (31)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 5, 2009

SUBJECT:

BEAVER VALLEY POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000334/2009004 AN D 05000412/2009004

Dear Mr. Harden:

On September 30, 2009, 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 30, 2009, 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 of Significance 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 dOGument system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.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, IRN Ronald R. Bellamy, Ph.D., Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-334,50-412 License Nos: DPR-66, NPF-73

Enclosures:

Inspection Report 05000334/2009004; 05000412/2009004 w/Attachment: Supplemental Information

REGION I==

Docket Nos. 50-334, 50-412 License Nos. DPR-66, NPF-73 Report Nos. 05000334/2009004 and 05000412/2009004 Licensee: FirstEnergy Nuclear Operating Company (FENOC)

Facility: Beaver Valley Power Station, Units 1 and 2 Location: Post Office Box 4 Shippingport, PA 15077 Dates: July 1,2009 through September 30,2009 Inspectors: D. Werkheiser, Senior Resident Inspector D. Spindler, Resident Inspector S. Barr, Senior Emergency Preparedness Specialist P. McKenna, Reactor Inspector T. Moslak, Health Physicist Approved by: R. Bellamy, Ph.D., Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure

TABLE of REPORT DETAILS Summary' of Plant Status:

Unit 1 began the inspection period at 100 percent power. On August 7, the unit was down powered to 82 percent for planned condenser waterbox repair and cleaning and returned to full power on August 8. The unit remained at 100 percent power for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent power. On July 7, the unit was down powered to 96.5 percent for planned main turbine valve testing and returned to full power the same day. The unit was down-powered to 97.5 percent on August 10 for unplanned leading edge flow meter instrumentation repairs and returned to full power on August 14. The unit remained at 100 percent power for the remainder of the inspection period.

1. REACTOR SAFETY Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity [R]

1R01 Adverse Weather Protection (71111.01)

Seasonal Susceptibility a. Inspection Scope (1 sample)

In preparation for high winds associated with summer storm conditions and hurricane season, the inspectors reviewed the Beaver Valley Power Station (BVPS) design features and FENOC's implementation of procedures to protect risk significant mitigating systems from adverse weather. The inspectors reviewed the corrective action program database, operating experience, the Updated Final Safety Analysis Report (UFSAR),

and technical specifications to determine the types of adverse weather conditions to which the site is susceptible, and to verify that the licensee was appropriately identifying and resolving weather-related equipment problems. The inspectors also reviewed and walked down the emergency diesel generators and vital 4160 VAC systems to verify seasonal readiness.

b Findings No findings of significance were identified.

1R04 Equipment Alignment (71111.04)

Partial System Walkdowns (71111.04Q)

a. Inspection Scope (3 samples)

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 Enclosure

systems, including associated electrical distribution components and control room panels, to verify the equipment was aligned to perform its intended safety functions:

  • Unit 2, on Aug 26, '8' Train of Recirculation Spray System during pipe and valve 2 SWS-1217 [RSS Radiation Mons Sample Cooler SWS Isolation] replacement; and
  • Unit 2, on September 19, Train 'B' component cooling system lineup during the restoration of 'C' component cooling water pump after planned maintenance.

b. Findings No findings of significance were identified.

1R05 Fire Protection (71111.05)

Quarterly Sample Review (71111.05Q)

a. Inspection Scope (3 samples)

The inspectors reviewed the conditions of the fire areas listed below, to verify compliance with criteria delineated in Administrative Procedure (ADM) 1/2-ADM-1900,

"Fire Protection," Rev. 19. 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. Documents reviewed are listed in the Attachment: .

  • Unit 1, Intake Structure, Pump Cubicle CW-S-1 C (Fire Area IS-3);
  • Unit 1, Communication Equipment and Relay Panel Room (Fire Area CR-3); and
  • Unit 2, Service Building (East) (Fire Area SB-2).

b. Findings No findings of significance were identified.

1R06 Flood Protection Measures (71111.06)

a. Inspection Scope (1 sample)

On July 24, the inspectors reviewed a sample of flood protection measures for equipment in the Unit 1/2 intake structure. This review was conducted to evaluate FENOC's protection of the enclosed safety-related systems from internal flooding 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. Documents reviewed during the inspection are listed in the Attachment.

Enclosure

b. Findings No findings of significance were identified.

1R07 Heat Sink Performance (71111.07)

Annual Sample Review (7111.07 A)

a. Inspection Scope (1 sample)

During the week of July 30 through August 6, the inspectors reviewed periodic maintenance associated with Unit 2, 2CCP-E21A Primary Component Cooling Heat Exchanger. The review included an assessment of the maintenance and verified consistency with Electric Power Research Institute document NP-7552, "Heat Exchanger Performance Monitoring Guidelines," December 1991, and NRC Generic Letter 89-13

"Service Water System Problems Affecting Safety-Related Equipment." The inspectors reviewed inspection results, related condition reports and program health reports.

b. Findings No findings of significance were identified.

1R11 licensed Operator Regualification Program (71111.11)

Resident Inspector Quarterly Review (71111.11 Q)

a. Inspection Scope (1 sample)

The inspectors observed one sample of Unit 1 licensed operator simulator training on September 10 (Cycle 5, Day 3). 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 pilant control room. The inspectors verified that the training evaluators adequately addressed that the applicable training objectives had been achieved.

b. Findings No findings of significance were identified.

1R12 Maintenance Rule Implementation (71111.12)

a. Inspection Scope (3 samples)

The inspectors evaluated Maintenance Rule (MR) implementation for the issues listed b1310w. The inspectors evaluated specific attributes, such as MR scoping, characterization of failed structures, systems, and components (SSCs), MR risk Enclosure

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 SSCs, the inspectors evaluated whether performance was properly dis positioned for MR cltegory (a)(1) and (a)(2) performance monitoring. MR System Basis Documents were also reviewed, as appropriate.

  • CR 09-61226, "Maint. Rule Functional Failure Review Implementation Issue";
  • CR 09-62429, "Flow Transmitter for Blender Boric Acid"; and
  • CR 09-61881, "Failed Maintenance Rule Goal for Unavailability Time for 21AS-C21 n.

b. Findings No findings of significance were identified.

1R13 Maintenance Risk Assessment and Emergent Work Control (71111.13)

a. Inspection Scope (6 samples)

The inspectors reviewed the scheduling and control of six 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). Documents reviewed during the inspection are listed in the Attachment.

  • During the week of July 6, Unit 1 review of Yellow Risk during repairs on 1RC-47, Refueling Water Storage Tank Return Line;
  • On July 28, Unit 2 impact for 2CHS-FT113, Flow Transmitter for Boric Acid feed to the blender, failed as documented in CR 09-62429;
  • On August 26, Unit 2 risk associated with 2-1 EDG and 'A' train recirculation spray system maintenance activities; and
  • On September 18, Unit 1 review due to expanded maintenance scope of 'A' fuel pool purification pump [1 FC-P-4A], documented in CR 09-64612.

b. Findings No findings of significance were identified.

1R 15 Operability Evaluations (71111.15)

a. Inspection Scope (5 samples)

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

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

Documents reviewed are listed in the Attachment.

  • On July 1, Unit 2 assessment of operability regarding lube oil engine outlet temperature high as documented in CR 09-61333;
  • On July 30, Unit 2 'A' service water coupler test as documented in CR 09-62515;
  • On August 4, Unit 2 emergency diesel generator (EDG) operability and assessment regarding inleUoutlet temperatures information provided by vendor, as documented in CR 09-62702;
  • On August 5, Unit 1 100 regarding the failure to start and run motor-driven fuel oil pump [1 EE-P-98] during a monthly surveillance test of the '8' Train EDG, as documented in CR 09-62782; and
  • On August 18, Units 1 and 2, Licensee's review, assessment, and POD of Nuclear Safety Advisory Letter 09-05 from Westinghouse regarding thermal limits documented in CR 09-62810.

b. Findings No findings of Significance were identified.

1R18 Plant Modifications (71111.18)

Temporary Plant Modifications a. Inspection Scope (1 sample)

The inspectors reviewed the following temporary modifications (TMOD) based on risk significance. The TMOD and associated 10 CFR 50.59 screening were reviewed against the system design basis documentation, including the UFSAR and the TS. The inspectors verified the TMODs were implemented in accordance with 1/2-ADM-2028,

"Temporary Modifications," Rev. 6. Documents reviewed are listed in the Attachment.

  • Unit 1 TMOD 09-0549, associated with installing temporary ventilation mixing fans in containment due to the failure of the 'C' containment air recirculation fan to start on June 25. For this activity, the inspectors also reviewed the environmental and seismic qualifications of the parts and intended installation plan. Inspectors observed portions of construction of the mounting system and electrical wiring to verify that changes described in the package were actually implemented. Of three temporary fans planned, two were installed (July 17 and July 21).

b. Findings No findings of significance were identified.

1R19 f1ost-Maintenance Testing (71111.19)

a. Inspection Scope (6 samples)

The inspectors reviewed the following activities to determine whether the post maintenance tests (PMT) adequately demonstrated that the safety-related function of the Enclosure

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. Documents reviewed during the inspection are listed in the Attachment:

  • Unit 1 'C' containment recirculation fan replacement during 1R19 CWO 200074187);

activation timer 62-ACB relay replacement due to its failure to actuate upon receiving a Unit 2 high radiation monitor test signal during maintenance as documented in CR 09-61743;

  • On July 15, Unit 1 power range nuclear instrument (N44) operational mode selector switch (S303) replacement (WO 200377904) due to a degraded test signal documented in CR 09-61812;

[2EGS*EG2-1] Monthly Test" after replacing service water heat exchanger temperature control valve [2EGS-TCV216-1] internals per WO 200377159;

  • On July 30, Unit 2 wiring and relay upgrades to emergency diesel generator circuits [ECP 08-0660] related to alternate shutdown panel control transfer; and
  • On August 6, Unit 1, 1OST-36.4.AH, after replacement of contact block [STL02]

for motor-operating fuel supply pump [EE-P-98] for the 'B' train emergency diesel generator [EE-EG-2];

b. Findings No findings of significance were identified.

1R20 Refueling and Outage Activities (71111.20)

Unit 2 Refueling Outage (2R14)

a. Inspection Scope (1 partial sample)

The inspectors reviewed procedures and observed selected activities associated with the Unit 2 pre-outage activities. Inspectors verified activities were performed in accordance with procedures and verified required acceptance criteria were met. The inspectors also verified that conditions adverse to quality identified during performance of selected pre-outage activities were identified as required by the licensee's corrective action program. The inspectors also evaluated the following activities:

  • Pre-outage shutdown safety I defense-in-depth review;
  • New fuel receipt and inspection; and
  • Moderator temperature coefficient determination (2RST-2.5).

b. Findings No findings of significance were identified.

Enclosure

1R22 Surveillance Testing (71111.22)

a. Inspection Scope (4 samples: 2 in-service testing and 2 routine)

The inspectors witnessed the performance of or reviewed test data for the eight following Operation Surveillance Test (OST) and Maintenance Surveillance Packages (MSP). 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.

  • On July 7, 10ST-13.02, Rev 33, "Quench Spray Pump QS-P-'IB Test [1ST];"

Monthly Test;

  • On August 18, 10ST-13.11A, Rev. 5, Train A Quench Spray System Operability Test."

b. Findings No findings of significance were identified.

Cornerstone: Emergency Preparedness [EP]

1EP2 Alert and Notification System (ANS) Evaluation (71114.02)

a. Inspection Scope (1 sample)

An onsite review was conducted to assess the maintenance and testing of the Beaver Valley Power Station ANS. During this inspection, the inspectors interviewed EP staff responsible for implementation of ANS testing and maintenance and reviewed Condition Reports (CRs) pertaining to the ANS for causes, trends, and corrective actions. The inspectors reviewed the ANS procedures and the ANS design report to ensure FENOC's compliance with design report commitments for system maintenance and testing. The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment .02. Planning Standard, 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 of Significance were identified.

1EP3 Emergency Response Organization (ERO) Staffing and Augmentation System (71114.03)

a. Inspection Scope (1 sample)

The inspectors conducted a review of Beaver Valley's ERO augmentation staffing n:!quirements and the process for notifying and augmenting the ERO. This was performed to ensure the readiness of key licensee staff to respond to an emergency event and to ensure FENOC's ability to activate their emergency facilities in a timely Enclosure

manner. The inspectors reviewed the Beaver Valley ERO roster, training records, applicable procedures, drill reports for augmentation, quarterly EP drill reports, and CRs related to the ERO staffing augmentation system. The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment .03. Planning Standard, 10 CFR S0.47(b)(2) and related requirements of 10 CFR SO, Appendix E, were used as reference criteria.

b. Findings No findings of significance were identified.

1EP4 Emergency Action Level (EAL) and Emergency Plan Changes (71114.04)

a. Inspection Scope (1 sample)

Since the last NRC inspection of this program area, in August 2008, FENOC had implemented various revisions of the different sections of the Beaver Valley Power Station Emergency Plan. FENOC had determined that, in accordance with 10 CFR SO.54(q), any change made to the Plan, and its lower-tier implementing procedures, had not resulted in any decrease in effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR S0.47(b) and Appendix E to 10 CFR SO.

The inspectors confirmed no EAL changes had been made since August 2008, and conducted a sampling review of other Emergency Plan changes, including the changes to lower-tier emergency plan implementing procedures, to evaluate any potential decreases in effectiveness of the Emergency Plan. However, this review 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 inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment .04. The requirements in 10 CFR SO.S4(q)

were used as reference criteria.

b. Findings No findings of significance were identified.

1EPS Correction of Emergency Preparedness Weaknesses (71114.0S)

a. Inspection Scope (1 sample)

The inspectors reviewed a sampling of self-assessment procedures and reports to assess FENOC's ability to evaluate their EP performance and programs. The inspectors reviewed a sampling of CRs from July 2007 through August 2009 from drills, self assessments and audits. Additionally, the inspectors reviewed Quality Assurance audits, including 10CFRSO.S4(t) audits, and several self-assessment reports. This inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment .OS. Planning Standard, 10 CFR SO.47(b) (14) and the related requirements of 10 CFR SO Appendix E were used as reference criteria.

b. Findings No findings of significance were identified.

Enclosure

'I EP6 Drill Evaluation (71114.06)

a. Inspection Scope (1 sample)

The inspectors observed an emergency preparedness mini-drill for the 'Green' team and a Unit 2 licensed-operator simulator evaluation conducted on September 17. Senior licensed-operator performance regarding event classifications and notifications were specifically evaluated. The inspector 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 General Emergency. 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 (NEI) 99-02, Rev. 5, "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:

  • 1/2-ADM-1111, Rev. 3, "NRC EPP Performance Indicator Instructions"
  • EPP/I-1a/b, Rev. 13114, "Recognition and Classification of Emergency Conditions"
  • 1/2-EPP-I-2, Rev. 35, "Unusual Event"
  • 1/2-EPP-I-3, Rev. 33, "Alert"
  • 1/2-EPP-I-4, Rev. 33, "Site Area Emergency" and
  • 1/2-EPP-I-5, Rev. 34, "General Emergency" b. Findings No findings of significance were identified.

2. RADIATION SAFETY Cornerstone: Public Radiation Safety [PS]

2PS3 Radiological Environmental Monitoring Program (REMP) and Radioactive Material Control Program (71122.03)

a. Inspection Scope (10 samples)

During the period July 6 - 10, the inspectors conducted the following activities to verify that the licensee implemented the radiological environmental monitoring program (REMP) consistent with station TSs and the Off-Site Dose Calculation Manual (ODCM)

to validate that radioactive effluent releases met the design objectives of Appendix I of 10 CFR 50.

Additionally, the inspectors verified that radiological surveys and controls were adequate to prevent the inadvertent release of radioactive material into the public domain.

Implementation of these controls was reviewed against the criteria contained in 10 CFR Enclosure

20 & 50, relevant TSs, and the licensee's procedures. This inspection activity represents completion of 10 samples relative to this inspection area.

REMP Inspections:

  • The inspectors walked down eight (of 10) air sampling stations (Nos. 27, 29B, 30, 32,46.1, 47, 48, 51), two (of 3) milk sampling stations (Nos. 25, 27), three (of 3)

surface water sampling stations (Nos. 2.1, 5, 49), two (of 2) drinking water stations (Nos. 4,5), and nine (of 48) thermoluminescent (TLD) monitoring stations (Nos. 27, 28, 29B, 30, 32, 46.1,47,48, 51) 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 inspectors 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 procedures;
  • Based on direct observation and review of records, the inspectors verified that the primary and redundant meteorological instrumentation was operable, calibrated, and maintained in accordance with the guidance contained in the FSAR, NRC Safety Guide 23, and the licensee procedures. The inspectors verified that the meteorological data readout and recording instruments in the control room and at the tower were operable for wind direction, wind speed, and delta temperature. The inspectors confirmed that redundant instrumentation was operable;
  • The inspector reviewed the calibration and maintenance records for 11 air samplers and observed the technician verifying the calibration of three water compositors;
  • The inspector reviewed CRs and a Nuclear Oversight Assessment Report (BV-C-08-08-02), 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 inspectors 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; and
  • The inspectors 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 inspectors also reviewed technical justifications 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.

Unrestricted Release of Material from the Radiologically Controlled Area (RCA):

  • The inspectors observed several locations in Units 1 and 2, including the Health Physics Main Control Points, and the Decontamination Facility, where the licensee monitors potentially contaminated material leaving the RCA, and inspected methods used for control, survey, and release from these areas, including observing the performance of personnel surveying and releasing material for unrestricted use.

Enclosure

With the assistance of a technician, the inspector verified that the Small Article Monitors (SAM) alarmed when a check source was counted and the operating parameters met criteria; and

  • The inspector verified that the contamination monitoring instrumentation (SAM-11 f RM-14) was appropriate for the radiation types potentially present and was calibrated with appropriate radiation sources. The inspectors reviewed the licensee's criteria for the survey and release of potentially contaminated material; verified that there was guidance on how to respond to an alarm which indicates the presence of contamination; and reviewed instrument alarm setpoints to ensure that radiation detection sensitivities are consistent with the NRC guidance contained in IE Circular 81-07 and IE Information Notice 85-92 for surface contamination and Health Physics Position (HPPOS) 221 for volumetrically contaminated material. The inspectors also reviewed the licensee's procedures and records to verify that the radiation detection instrumentation was used at its typical sensitivity level based on appropriate counting parameters, and verified that the licensee has not established a release limit by altering the instruments sensitivity through such methods as raising the energy discrimination level or locating the instrument in a high radiation background area.

b. Findings No findings of significance were identified.

4. OTHER ACTIVITIES fOAl 40A1 Performance Indicator (PI) Verification (71151)

a. Inspection Scope (9 samples total)

The inspectors sampled licensee submittals for Pis listed below for both Unit 1 and Unit 2. The inspectors reviewed Licensee Event Reports, condition reports, portions of various plant operating logs and reports, and PI data developed from monthly operating reports. Methods for compiling and reporting the Pis were discussed with engineering and licensing personnel. To verify the accuracy of the PI data reported during this period, PI definitions and guidance contained in NEI 99-02, "Regulatory Assessment Indicator Guideline," Revision 5, were used for each data element.

.1 Cornerstone: Mitigating Systems (6 samples)

The inspectors sampled licensee data to verify accuracy of the data recorded from October 2008 through July 2009 for:

  • Support cooling water systems [MS1 0]: River water (Unit 1) & service water (Unit 2) .

.2 ~:ornerstone: Emergency Preparedness (3 samples)

Enclosure

The last NRC EP inspection at Beaver Valley was conducted in the second quarter of 2008, so the inspectors reviewed supporting documentation from EP drills, training records, and equipment tests from the second calendar quarter of 2008 through the second quarter of 2009, to verify the accuracy of the reported PI data. The inspectors reviewed data for the following Beaver Valley EP Pis:

  • Drill and Exercise Performance (DEP) [EP01];
  • Emergency Response Organization (ERO) Drill Participation [EP02]; and
  • Alert and Notification System (ANS) Reliability [EP03].

Additionally, the inspectors performed NRC Temporary Instruction (TI) 2515/175,

"Emergency Response Organization, Drill/Exercise Performance Indicator, Program F<teview," ensured the completeness of the licensee's completed Attachment 1 from the TI, and forwarded that data to NRC Headquarters.

b. Findings No findings of significance were identified.

40A2 Problem Identification and Resolution (71152 - 1 sample total)

.1 Daily Review of Problem Identification and Resolution a Inspection Scope As required by Inspection Procedure 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 a daily screening of items entered into FENOC's corrective action program. This review was accomplished by reviewing summary lists of each CR, attending screening meetings, and accessing FENOC's computerized CR database.

b. Findings No findings of significance were identified .

.2 Semi-Annual Trend Review (71152)

a. Inspection Scope (1 sample)

The inspectors reviewed site trending results for the time period April through September 2009, 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 (Section 40A2.1), 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. 5, "Integrated Performance Assessment !Trending." The inspectors also reviewed quarterly Quality Assurance Enclosure

reports and issues captured in the Activity Tracking database to identify issues and trE~nds to evaluate during the inspection.

b. Findings No findings of significance were identified. However, improvements in operations crew performance have been observed and were evident during response to plant malfunctions (Le. challenges during the shutdown for the Unit 1 spring refueling outage (1 R19). An emerging adverse trend was identified in the implementation of the clearance program, specifically regarding the proper use (execution) of the clearance program and planning (preparation) of the clearance points (eRs 08-38276, 09-56328, 09-65317,09-63342,09-63807, and 09-66167) .

.3 Annual Sample: Emergency Diesel Generator (EDG) Maintenance Practices a. Inspection Scope (1 sample)

This inspection was conducted to assess the adequacy of FENoe's evaluation and resolution of equipment failures associated with the emergency diesel generators (EDG).

Specifically, the inspectors reviewed the actions taken by FENOe following two Maintenance Preventable Functional Failures (MPFF) on the Unit 2 EDGs in July and October, 2008. The inspectors also reviewed the evaluation and resolution of two failures of the #10 fuel injection pump on EDG 2-1 within a 13 month period, with the latest failure in December, 2007, and three failures of the EDG 2-1 lube oil heater breaker within a month period in August 2008. Finally, the inspectors reviewed FENOe's actions to address multiple deficiencies associated with the EDG 1-2 governor over a two month period ending in June 2009.

The inspectors reviewed FENOe's condition reports and apparent cause analyses associated with the EDG issues. The inspectors also interviewed plant personnel, and reviewed EDG system health reports, maintenance rule failure review forms and maintenance rule (a)(1) evaluation forms. This review was done to evaluate the effectiveness of FENOe's actions and determine if FENOe had promptly corrected adverse conditions when identified. In addition, the inspectors walked down the EDGs in Unit 1 and Unit 2 to assess the material condition of the EDGs. Finally, the inspectors reviewed the long term actions planned by FENOe to address remaining deficiencies to dE~termine if they were adequate. Documents reviewed are listed in the Attachment.

b. Findings and Observations No findings of significance were identified.

The inspectors concluded FENOe appropriately evaluated the causes of the EDG issues discussed above. The condition report packages included cause analyses, extent-of-condition reviews, completed corrective actions and planned corrective actions.

In the case of the rocker arm lube oil tank float control valve MPFF on EDG 2-1 and the four inch lube oil flange leak MPFF on EDG 2-2, the corrective actions were extensive; however, the inspectors noted that corrective actions associated with craft workmanship did not include changes to worker training programs. FENOe acknowledged this oiJservation. Finally, the inspectors reviewed the condition report database and noted that there have been no repeat failures of the components above since corrective Enclosure

actions were implemented.

40A3 Followup of Events and Notices of Enforcement Discretion (71153)

Review of Licensee Event Reports (LERs) (2 samples)

(Closed) LER 05000334/2009-002-00: Feedwater Isolation Initiates Auxiliary Feedwater System During a Refueling Shutdown.

On April 20, 2009, Unit 1 experienced an unplanned 'B' high steam generator water level resulting in an engineered safety feature P14 actuation (normal feedwater isolation and emergency feedwater initiation) due to a bypass feedwater regulating valve (FCV-1 FW-489) failing open. The plant and crew responded as expected with no additional significant complications. The licensee conducted a root cause investigation and determined the most probable cause of the failure to be foreign material in the bypass valve positioner air regulator during vendor assembly. The licensee replaced or inspected all affected valve positioners. The inspector determined that no findings of significance were identified and no violations of NRC requirements occurred. This LER is closed.

{Closed) LER 05000334/2009-004-00: Two Ultrasonic Indications Found in Reactor Coolant System Drain Pipe.

On April 26, 2009, during planned ultrasonic examination of reactor coolant piping in accordance with Materials Reliability Project document MRP-146 (see report 05000334/2009003 and 05000412/2009003, section 1R09 and 40A3.1), two relevant indications were found in a reactor coolant 2-inch pipe segment, which is a stainless steel drain/sample line off the 'A' hot leg. The indication was not through-wall and there was no evidence of leakage. Reactor coolant system integrity was maintained.

Corrective actions included replacing the pipe segment, which was observed by inspectors. The inspectors reviewed the LER, verified the appropriateness of corrective actions and extent of condition regarding other pipe segments. No findings of Significance were identified and no violation of NRC requirements occurred. This LER is closed.

40A5 ,9ther

.1 Quarterly Resident Inspector Observations of Security Personnel And Activities a. Inspection Scope During the inspection period, the inspectors conducted the following observations of security force personnel and activities to ensure that the activities were consistent with licensee security procedures and regulatory requirements relating to nuclear plant security. These observations took place during both normal and off-normal plant working hours.

  • Multiple tours of operations within the Central and Secondary Security Alarm Stations;

.' Tours of selected security towers/security officer response posts;

  • Direct observation of personnel entry screening operations within the plant's Main Access Facility; and Enclosure
  • Security force shift turnover activities.

These quarterly resident inspector observations of security force personnel and activities did not constitute any additional inspection samples. Rather, they were considered an integral part of the inspectors' normal plant status review and inspection activities.

b. Findings No findings of significance were identified.

40A6 Management Meetings

.1 Radiation Monitoring Instrumentation and Protective Equipment On July 10, 2009, the inspectors presented the inspection results to Mr. R. Lieb, Director of Site Operations, and other members of his staff. The inspector confirmed that proprietary information was not provided or examined during the inspection .

.2 Emergency Preparedness On September 3, 2009, the inspectors conducted an exit meeting and presented the preliminary inspection results to Mr. R. Brosi, Director - Performance Improvement, and other members of the FENOC staff. The inspector confirmed that proprietary information was not provided or examined during the inspection .

.3 Quarterly Inspection Report Exit On October 30, the inspectors presented the normal baseline inspection results to Mr.

P. Harden, Beaver Valley Power Station Site Vice President, and other members of his staff. The inspectors confirmed that proprietary information was not retained at the conclusion of the inspection period.

ATTACHMENT: SUPPLEMENTAL INFORMATION Enclosure

A-1 SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee Personnel S. Baker Radiation Protection Manager M. Banko Environmental & Chemistry Supervisor A. Burger Reactor Engineer Supervisor R. Bologna Plant Engineering Manager D. Branch BVPS I&C Supervisor R. Brosi, Director Performance Improvement J. Campbell-Powell Advanced Nuclear Specialist S. Checketts Operations Manager G. Cramer Emergency Planning Manager R. Dinello Environmental Field Specialist M. Helms Advanced Nuclear Specialist D. Hewitt Unit 1 Shift Manager S. Hovanec System Engineering Supervisor L. Huyler Advanced Nuclear Specialist D.Jones 1ST Engineer K. KimmE~rlee Supervisor, Radiation Protection Field Operations R. Lieb Director, Site Operations J. Mauck Regulatory Compliance D. McBride Fleet Oversight Manager J. Miller Site Fire Marshall E. Peace EDG Maintenance Supervisor A. Reardon EDG System Engineer D. Salera Chemistry Supervisor D. Schwer Manager, Work Management P.Sena Site Vice President B. Sepelak Supervisor, Regulatory Compliance R. Williams Nuclear Engineer R. Winters Chemist R. Zupo Electrical Maintenance Supervisor Other Personnel L.Ryan Inspector, Pennsylvania Department of Radiation Protection LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Closed 05000334/2009-002-00 LER Feedwater Isolation Initiates Auxiliary Feedwater System During a Refueling Shutdown (Section 40A3.1 )

Attachment

A-2 05000334/2009-004-00 LER Two Ultrasonic Indications found in Reactor Coolant System Drain Pipe (Section 40A3.1)

LIST OF DOCUMENTS REVIEWED Section 1R01: Adverse Weather Protection Procedures 1/20M-53C.4A.75.1, Rev. 11, "Acts of Nature-Tornado or High Wind Condition" Condition Reports 05-01611 06-01008 09-60033 09-60106 Section 'I R04: Equipment Alignment Procedures 10ST-24.2, "Motor driven AFW Pump Test (1 FW-P-3A)", Rev. 40 Drawings 8700-RM-424-2, Rev. 11 10080-RM-413-1 , Rev. 12 Condition Reports (lR)

06-0052~1 07-12731 07-26409 08-44960 Section 1R05: Fire Protection Pre-Fire Plans 1PFP-SRVB-713, Relay Room Fire Area CR-3 1PFP-INTS-705, Pump Cubicles Fire Area IS-1, 2, 3,4 Other CR 09-62523 CR 09-62533 CR 09-62512 Analysis No. 10080-B-085, Rev. 12 Section 1R06: Flood Protection Procedures 1/2 OM-!53C.4a.75.2, Rev. 24, "Acts of Nature Flood" 1BVT1.33.07, Rev. 3, "Flood Seals Visual Inspection" 2BVT1.33.7, Rev. 2, "Flood Seals Visual Inspection" 1/2 PIP-1M16, Rev. 16, "Penetration Seals" Condition Reports 05-03806 06-04373 08-33072 08-35404 Attachment

A-3 Drawings 8700-RM-63E, Rev. 5, "Penetration Seals-Cooling Tower Pump House and Intake Structure" 1R07: Heat Sink Performance Procedures 20M-30.4.M, Rev. 35, "BV-2 Asiatic Clam and Zebra Mussel Chemical Treatment Program" 1/2-CHM-ADD-7.27, Rev. 17, "Reactor Plant River Water System/Service Water System-Biocide Addition" Condition Reports 05-00847 05-02019 07-23817 07-19621 08-37135 08-3550 09-61081 Other CCP System Maintenance Rule Data of July 2, 2009 2CCP-E2'IA Heat Exchanger Inspection Reports of 3/20108 and 6/24/09 Section 1R11: Licensed Operator Regualification Program Procedures BVBP-OPS-0024, Rev. 2, "Transient Response Guidelines" BVSP-OPS-0029, Rev. 0, "Operator Time-Critical Manual Actions" TRG-1, Training Guide (Instrument Failure and Rod Fault)

TRG-2, Training Guide (MSIV Closure and Faulted S/G)

Section 1R13: Maintenance Risk Assessment and Emergent Work Control Procedures 20M-7.4Q, Rev. 11, "Emergency Soration" NOP-OP-1007, Rev. 5, "Risk Determination" NOP-ER-3004, Rev. 1, "FENOC Maintenance Rule Program" Work Ord,ers 200379204 200380006 200377159 200369748 Condition Reports 09-62429 09-62688 Other Drawing 10080-RM-407-2 Unit 2 Weekly Maintenance Risk Summary for the week of August 3, Revs. 0 and 1 Unit 2 Weekly Maintenance Risk Summary for the week of August 24, Rev. 1 Unit 1 PRA Profile from the week of July 6, 2009 Unit 1 Maintenance Plan from the week of July 6, 2009 NOTF 600552164 NOTF 600556974 PAF 09-01520 Attachment

A-4 Station Risk Profile from the week of July 27,2009 Maintenance Rule Failure Review Form for 2CHS-FT113 dated August 27, 2009 Section 1R15: Operability Evaluations Procedures 20ST-36.1, Rev. 58 Data Sheet 1 10ST-36.2, Rev. 52, "Diesel Generator No.2 Monthly Test" 10M-36.4.AH, Rev. 11, "Diesel Generator No.2 Start-up and Shutdown" Technical Specifications 3.2.1 3.8.1 Condition Reports 09-62702 Other NSAL 09-5, dated August 5, 2009 PAF 09-01520 NOTF 600552164; Calibrate 2EGO-TCV200-1 Lube Oil Temperature Control Valve NOTF 600558190 QFO BV220093794 Fairbank Morse email dated 7/2/09 from Ted Stevenson to Adam Reardon WO 200380006 Section 1R18: Plant Modifications Condition Reports 09-61052 09-62204 09-62285 09-62215 09-61739 09-61611 09-61463 Regulatory Applicability Determination and 10 CFR 50.59 Screens 09-61052 Procedures 1;2-PMP-E-75-200, Issue 4 Rev 10, "Van axial Fan Maintenance" Drawings 616707-23, May 2001, "Reliance Electric & Eng Co. DWG for 445 TENV 6318-6318 FF 149782 Stage Joy Other BV1 Operations Shift Operating Logs, June 27; June 28; July 22, 2009 BV1 Operations Containment Temperature Operating Limits ECP 09-0184, Unit 1 Air Duct Management Changes Problem Solving Plan, 09-61052 Plant Health Committee Presentation for TM 09-0549-001, September 29, 2009 TS 3.6.5 Containment Temperature Unit 1 Plant Computer containment temperature profiles, July 24, 2009 WO 200208558 Attachment

A-5 UFSAR S.4 Internal Containment Systems Section 1R19: Post-Maintenance Testing Procedures 1OM-36.4.AH, Rev. 11, "Diesel Generator No.2 Start-up and Shutdown" 10M-44A.4.L, Rev. 9, "Isolating and Restoring the Control Room Ventilation System" 10M-44A.1.D, Rev. 6 1/2 OST-43.17d, Rev. 38, "Control Room Rad Monitor Functional Test" 1/2 RCP-30A-PC, Rev. 13, "Calibration of Timing Relays" 1/2-PIP-E12, Rev. 5, "Internal Wiring" 1MSP-2.06-1, Rev. 23, "Power Range Neutron Flux Channel N44 Refueling Calibration" Technical Specifications BVPS TS 3.3.1 BV1 LRM LR 3.3.5 Work Orders 200380006 200377637 200377904 200342368 Condition Reports 09-62830 09-62782 09-61743 09-62492 09-62411 Other Unit 1 Shilft Operating Logs dated August 5-6,2009 Drawing 8700-RE-21ML, Rev. 19 Drawing 10080-RE-14A NOTF 600554733 BV1 Operations Logs dated July 14-15, 2009 ECP 08-0660-01, Rev. 1, "BV2 EDG ASP Transfer CKT-Replay Change" Clearance 2BVP-CYC-14-1 2W12-36-EGS-002 Section 1R22: Surveillance Testing Procedures PAF-09-01527, Rev. 33, "Quench Spray Pump Test" Condition Reports 09-61433 09-61333 09-62702 09-62515 09-60191 08-49878 Other ASIVIE OM CVDE-2004 Subsection ISTB Unit 1 'B' Quench Spray Pump Curves 09-02882, Rev. 0, "Quench Spray Pump Test 50.59 Screening" T.S. 3.3.11 T.S. 3.3.21 T.S. 3.7.8 Section 1EP2: Alert and Notification System Evaluation Attachment

A-6 Procedures 1/2-ADM-1107, Alert Notification System (Sirens) Maintenance and Testing (Rev. 9)

1/2-ADM-"1107.F02, BVPS - Alert Notification System Maintenance/Repair Forms (completed February 19, 2008 - August 10, 2009)

1/2-ADM-1107.F03, Maintenance Schedule (completed for calendar year 2008)

1/2-ADM-"1107.F04, Alert Notification System Test Results Documentation Forms (completed August 28, 2008 - June 19, 2009)

Other Beaver Valley Power Station 2009 Emergency Planning Zone Siren System Test Schedule Beaver Valley Power Station ANS-related Condition Reports (dated January 2008 - July 2009)

Emergency Warning Notification System Design Report, Beaver Valley Power Station (dated March 1, 1984)

Supplement to the Beaver Valley Power Station Emergency Warning Notification System De!sign Report (dated May 13, 2002)

Section 1EP3: Emergency Response Organization Staffing and Augmentation System Procedures 1/2 -EPP-IP-1.4, Technical Support Center Activation, Operation and Deactivation, Rev. 32 112 -EPP-IP-1.5, Operations Support Center (OSC) Activation, Operation and Deactivation, Re~v. 21 1/2 - EPP**IP-1.6, Emergency Operations Facility (EO F), Activation, Operation and Deactivation, Rev. 19 1/2 - EPP-IP-1.7, Emergency Response Organization (ERO) Teams, Rev. 19 1/2-ADM-1101, Emergency Response Organization Administration, Rev. 9 1/2 -OST-57.2, Weekly Emergency Beeper Notification System, Rev. 17 1/2 -OST-57.1, Emergency Beeper Notification System, Rev. 14 1/2- EPP-I-3, Alert, Rev. 33 1/2-EPP-IP-1.1, Notifications, Rev. 43 1/2 -ADM-1102, BVPS Emergency Notification Testing, Review and Trending, Rev. 2 1/2 -EPP-IP-7.3, Emergency Preparedness Testing, Rev. 11 1!2-ADM-1110, Emergency Response Organization (ERO) Instructions, Rev. 6 Other Emergency Preparedness Plan, Volume 1, Rev. 27 Section 1EP4: Emergency Action level (EAl) and Emergency Plan Changes Procedures Beaver Valley Power Station 1/2- ADM 1100, Emergency Plan/Procedure Preparation and Revision, (Rev. 3 Emergency Plan Change Evaluations 2008-083**00 2008-084-00 2008-085-00 2008-086-00 2008-087-00 2008-089-00 2008-090-00 2008-091-00 2008-092-00 2008-093-00 2008-094-00 2008-095-00 2008-096-00 2008-099-00 2008-100-00 2008-101-00 2008-102-00 2008-102-00 2008-103-00 2008-104-00 2008-105-00 2008-106-00 2008-107-00 2009-001-00 Attachment

A-7 2009-002-00 2009-005-00 2009-006-00 2009-007-00 2009-008-00 2009-010-00 2009-012-00 2009-013-00 2009-015-00 2009-016-00 2009-017-00 2009-019-00 2009-020-00 2009-022-00 2009-023-00 2009-024-00 Other NOBP-LP-4003A, FENOC 1OCFR 50.59 Guidelines NOP-LP-S400, Equipment Important to Emergency Response, Rev. 0 BVRM-EP-5003, Equipment Important to Emergency Response, Rev. 1 Section 11 EP5: Correction of Emergency Preparedness Weaknesses Other Fleet Oversight Audit Report MS-C-07 -12-24 Fleet Oversight Audit Report MS-C-08-12-24 Quality Field Observation FLT1200728, Interface with State and Local Governments (dated November 30, 2007)

Quality Field Observation FLT1200867, Interface with State and Local Governments (dated November 25, 2008)

Fleet Oversight Quarterly Performance Report BV-PA-08-01 Fleet Oversight Quarterly Performance Report BV-PA-08-02 Fleet Oversight Quarterly Performance Report BV-PA-08-03 Fleet Oversight Quarterly Performance Report BV-PA-08-04 Fleet Oversight Quarterly Performance Report BV-PA-09-01 Fleet Oversight Quarterly Performance Report BV-PA-09-02 SA-BV-09-011, Review of BVPS Emergency Action Levels versus NRC SER EALs SA-BV-09-013, Review of BVPS Emergency Preparedness Plan (EPlan) versus NRC SER EPlan SA-BV-09-032, Beaver Valley Emergency Preparedness Improvement Program Assessment SA-BV-09-033, NRC Performance Indicators for BVPS Emergency Response Quarterly EP Drill Reports, June 2008 July 2009 Condition Reports CR-09-60763, Unusual Event Declared for ERF Substation C02 Discharge with Smoke Detector Alarms (event date June 18,2009)

All EP-related Condition Reports (dated July 20, 2007 - August 28, 2009)

Section 2PS3: Radiological Environmental Monitoring Program and Radioactive Material Control Program Procedures:

1/2-0DC-01.01, Rev. 5, "ODCM: Index, Matrix, and History of ODCM Changes" 1/2-0DC-02.01, Rev. 6, "Overall Environmental Monitoring Program" 1/2-0DC-02.03, Rev. 1, "ODCM: Radiological Environmental Monitoring Programs" 1/2-0DC-03.02, Rev. 2, "ODCM: Bases for ODCM Controls" 1/2-0DC-03.03, Rev. 5, "ODCM: Controls for RETS and REMP Program" 1/2-ENV-02.01, Rev. 6, "Description of Overall Radiological Environmental Monitoring Program" 1/2-ENV-03.01, Rev. 6, "Environmental Sampling" 1I2-ENV-03.02, Rev. 2, "Maintenance & Calibration of Automatic Water Sampling Equipment" 1/2-ENV-03.03, Rev. 1, "Maintenance and Calibration of AVS-28A Environmental Sampler" 1I2-HPP-4.04.024, Rev.1, "NE Technology Small Article Monitor" Attachment

A-8 1MSP-45:17 -1, Rev. 24, "Meteorological Monitoring System Calibration" NOP-WM-7021, Rev. 3, "Radiological Postings and Markings" 1/2-HPP-3.03.005, Rev. 7, "Removing Material from the RCA" 1/2-HPP-4.04.024, Rev. 2, "NE Technology Small Article Monitor (SAM-11)"

1/2-ADM-1601, Rev.1 9, "Radiation Protection Standards" Sampling Sites:

Milk: Nos. 25, 27 Air Particulatellodine: Nos. 27, 29B, 30,32,46.1,47,48, 51 Drinking Water: Nos. 4, 5 Surface Water: Nos. 2.1, 5, 49 Thermolumeniscent Dosimeters: Nos. 27, 28, 29B, 30, 32,46.1, 47,48,51 Nuclear Oversight (NO) Reports:

Fleet Oversight Audit Report (MS-C-008-08-02)

Condition Reports:

07 -22426 07-22429 07-24893 08-35120 08-38873 08-39721 08-45135 08-46558 09-57064 09-59207 09-59875 08-46558 09-61236 09-59850 09-59937 09-58904 09-59207 09-59045 09-59875 09-60287 Calibration Records Air Sampl~3r Nos. 6114,6115,6116,6117,6118,6119,6120,6121,6122, 6126, 6127 Meteorological Primary & Redundant Instrumentation dated 3/18/2009 Small Article Monitors Nos. 135, 136,139, 140, 428, 489, 290 Miscellaneous Reports:

2007 and 2008 Annual Radioactive Effluent Release Reports Environmental Cross Check Samples 2008 REMP General Action Item Orders Section 40A1: Performance Indicator (PI) Verification Procedures 1/2-ADM-1111, NRC EPP Performance Indicator Instructions, Rev. 3 Other DEP PI data, June 2008 - July 2009 ERO Drill Participation PI data, June 2008 - July 2009 ANS Reliability PI data, June 2008 - July 2009 Section 4,oA2: Identification and Resolution of Problems Condition Reports:

09-63018 09-62993 09-62782 09-62702 09-62492 09-62466 09-62432 09-62402 09-61124 09-60404 09-60359 09-59651 09-58657 09-58615 09-58172 09-58032 09-57659 09-55167 09-55143 09-53179 09-52857 09-52491 08-51439 08-50442 Attachment

A-9 08-49681 08-48695 08-48581 08-47663 08-47283 08-46841 08-4558Ei 08-45462 08-44922 08-43312 08-39993 Work Orders:

200344543 200330122 200330121 200330120 200330119 200330118 20027395 Design Basis Documents:

1DBD-36A, Rev. 11, Unit 1 Design Basis Document for EDGs 2DBD-36A, Rev. 8, Unit 2 Design Basis Document for EDGs Notifications:

600500997 Procedures:

1/2-ADM-2053, Rev. 0, EDG Maintenance Program NOP-LP-2001, Rev. 18, Corrective Action Maintenance Rule Failure Review Forms:

09-62402 09-61124 09-58032 09-57659 09-55167 08-48581 08-47663 08-45586 08-45462 08-44922 08-43312 08-39993 07-31825 07-29477 07-28237 Other:

Maintenance Rule (a)(1) Evaluation Form on Unit 2 EDGs event date 12/20/08 Maintenance Rule (a)(1) Evaluation Form on Unit 2 EDGs, Rev. 1, event dates 10/14/08 &

10/28/08 Unit 1 EDG System Health Reports quarters 2007-3 through 2009-2 Unit 2 EDG System Health Reports quarters 2007-3 through 2009-2 Section 40A3: Event Response Event Notification 45022, dated April 26, 2009 ASME Section XI Attachment

A-10 LIST OF ACRONYMS ADM Administrative Procedure ANS Alert and Notification System BCO Basis for Continued Operations BVPS Beaver Valley Power Station CFR Code of Federal Regulations CR Condition Report{s)

CREVS Control Room Emergency Ventilation System DEP Drill/Exercise Performance EAL Emergency Action Level EDG Emergency Diesel Generator EOF Emergency Operations Facility EP Emergency Preparedness ERO Emergency Response Organization FENOC First Energy Nuclear Operating Company FA Functionality Assessment IMC Inspection Manual Chapter 10D Immediate Operability Determination IP Inspection Procedure lSI Inservice Inspection LCO Limiting Conditions for Operations LER Licensee Event Report MPFF Maintenance Preventable Functional Failures MSP Maintenance Surveillance Packages NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission OD Operability Determinations ODCM Off-Site Dose Calculation Manual OST Operations Surveillance Test PI Performance Indicator PI&R Problem Identification and Resolution PMT Post Maintenance Testing POD Prompt Operability Determination RCA Radiologically Controlled Area REMP Radiological Environmental Monitoring Program RETS Radiological Effluent Technical Specification SAM Small Article Monitors TLD Thermoluminescence Dosimeter TS Technical Specification UFSAR Updated Final Safety Analysis Report Attachment

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