IR 05000219/2012004
| ML12312A094 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/07/2012 |
| From: | Hunegs G K NRC/RGN-I/DRP/PB6 |
| To: | Pacilio M J Exelon Nuclear, Exelon Generation Co |
| hunegs, gk | |
| References | |
| IR-12-004 | |
| Download: ML12312A094 (34) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 November 7, 2012 Mr. Michael Chief Nuclear Officer and Senior Vice President Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: OYSTER CREEK GENERATING STATION - NRC INTEGRATED INSPECTION REPORT 05000219/2012004
Dear Mr. Pacilio:
On September 30, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oyster Creek Generating Station. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2012 with Mr. R. Peak, Plant Manager, 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 upon the results of this inspection, no findings were identified.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, 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 the NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Gordon K. Hunegs, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-219 License Nos.: DPR-16
Enclosure:
Inspection Report 05000219/2012004
w/Attachment:
Supplementary Information
cc w/encl: Distribution via ListServ Mr. Michael
SUMMARY OF FINDINGS
IR 05000219/2012004, 7/01/2012 - 9/30/2012; Exelon Energy Company, LLC, Oyster Creek Generating Station, Integrated Report
This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. No findings were identified.
REPORT DETAILS
Summary of Plant Status Oyster Creek began the quarter at 100% power. On July 23, 2012, an unplanned scram occurred due to a loss of all offsite power. Operators commenced startup on July 26, 2012 and returned to full power on July 28, 2012.
On July 29, 2012, operators lowered power to 70% to perform a rod for flow swap. During the subsequent power ascension, "C" feed water regulating valve failed at 83% power and operators performed an unplanned power reduction to 67% power to conduct repairs. Oyster Creek returned to full power on July 31, 2012, following repairs to the "C" feed water regulating valve.
On July 31, 2012, operators lowered power to 70% to perform a rod pattern adjustment and returned the plant to full power on August 1, 2012.
On August 3, 4, 5, 6, and 12, 2012, Oyster Creek performed downpowers to comply with the New Jersey Department of Environmental thermal discharge permit. On August 8, 2012, operators conducted an unplanned downpower to 90% in response to a trip of the reactor water cleanup system. Oyster Creek returned to full power on August 10, 2012.
On August 16, 2012, operators conducted a planned downpower to 98% to place the reactor water cleanup system back in service and returned to full power later that day. On September 1, 2012, operators lowered power to 80% to perform a rod for flow swap and returned the plant to full power later that day.
On September 5, 2012, operators conducted a planned downpower to 95% to perform core spray system 1 surveillance testing. Oyster Creek returned to full power on September 7, 2012.
On September 11, 2012, operators conducted a planned downpower to 92% to perform core spray system 2 surveillance testing. Oyster Creek returned to full power on September 12, 2012.
On September 15, 2012, operators lowered power to 70% to perform a rod for flow swap and returned the plant to full power later that day.
On September 28, 2012, operators conducted an unplanned downpower to 70% in response to a salt water leak on the A-north circulating water discharge piping. Following repairs, Oyster Creek returned to full power on September 29, 2012.
On September 30, 2012, operators lowered power to 70% to perform a rod for flow swap and returned the plant to full power on October 1, 2012.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Readiness for Impending Adverse Weather Conditions
a. Inspection Scope
The inspectors completed two impending adverse weather preparation sample. The inspectors reviewed Exelon's preparations for the onset of hot weather on July 17, 2012 and a tornado watch on September 18, 2012. The inspectors reviewed the implementation of adverse weather preparation procedures before the onset of and during adverse weather conditions. The inspectors, on July 17, 2012, walked down the C and D 4160 volt switchgear rooms and C battery to ensure system availability. The inspectors verified that operator actions defined in Exelon's adverse weather procedure maintained the readiness of essential systems.
The inspectors discussed readiness and staff availability for adverse weather response with operations and work control personnel.
a. Findings
No findings were identified.
1R04 Equipment Alignment
.1 Partial System Walkdowns
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems: Augmented spent fuel pool cooling while normal spent fuel pool cooling system out-of-service for relay replacement on July 16, 2012 Isolation condenser A while isolation condenser B was inoperable for surveillance testing on July 3, 2012 Containment spray system 1 and core spray system 1 on July 2, 2012 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the UFSAR, technical specifications, work orders, condition reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether Exelon staff had properly identified equipment issues and entered them into the corrective action program for resolution with the appropriate significance characterization.
b. Findings
No findings were identified.
.2 Full System Walkdown
a. Inspection Scope
On August 27, 2012, the inspectors performed a complete system walkdown of accessible portions of the standby liquid poison control system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, tests, drawings, equipment line-up check-off lists, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hangar and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related condition reports and work orders to ensure Exelon appropriately evaluated and resolved any deficiencies.
b. Findings
No findings were identified.
1R05 Fire Protection
.1 Resident Inspector Quarterly Walkdowns
a. Inspection Scope
The inspectors conducted tours of the areas listed below to assess the material condition and operational status of fire protection features. The inspectors verified that Exelon controlled combustible materials and ignition sources in accordance with administrative procedures. The inspectors verified that fire protection and suppression equipment was available for use as specified in the area pre-fire plan, and passive fire barriers were maintained in good material condition. The inspectors also verified that station personnel implemented compensatory measures for out of service, degraded, or inoperable fire protection equipment, as applicable, in accordance with procedures. The inspectors verified that portable equipment would operate properly by observing periodic testing of the equipment.
Reactor building (119' elevation) (RB-FZ-1A) on July 18, 2012 Control room (OB-FZ-5) on July 18, 2012 Reactor building (23' elevation) (RB-FZ-1E1) on July 31, 2012 Reactor building (33' elevation) TIP drive area (RB-FZ-1E2) on July 31, 2012 Emergency diesel generator room #1 (DG-FA-15) on August 9, 2012 Portable emergency pump run on August 15, 2012
b. Findings
No findings were identified.
1R11 Licensed Operator Requalification Program
.1 Quarterly Review of Licensed Operator Requalification Testing and Training
a. Inspection Scope
The inspectors observed licensed operator simulator training scenario, 2612.885.0.0911A, Manual Reactor Scram after Security Event, on September 13, 2012.
The inspectors evaluated operator performance during the simulated event and verified completion of risk significant operator actions, including the use of abnormal and emergency operating procedures. The inspectors assessed the clarity and effectiveness of communications, implementation of actions in response to alarms and degrading plant conditions, and the oversight and direction provided by the control room supervisor. The inspectors verified the accuracy and timeliness of the emergency classification made by the shift manager and the technical specification action statements entered by the shift technical advisor. Additionally, the inspectors assessed the ability of the crew and training staff to identify and document crew performance problems.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed the samples listed below to assess the effectiveness of maintenance activities on SSC performance and reliability. The inspectors reviewed system health reports, corrective action program documents, maintenance work orders, and maintenance rule basis documents to ensure that Exelon was identifying and properly evaluating performance problems within the scope of the maintenance rule. For each sample selected, the inspectors verified that the SSC was properly scoped into the maintenance rule in accordance with 10 CFR 50.65 and verified that the (a)(2) performance criteria established by Exelon staff was reasonable. As applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals and corrective actions to return these SSCs to (a)(2). Additionally, the inspectors ensured that Exelon staff was identifying and addressing common cause failures that occurred within and across maintenance rule system boundaries.
Standby liquid poison flow instrument inaccuracy (IR 1363225) on July 5, 2012 Diesel fire pump failures (IR 1374437) on September 18, 2012
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed station evaluation and management of plant risk for the maintenance and emergent work activities listed below to verify that Exelon performed the appropriate risk assessments prior to removing equipment for work. The inspectors selected these activities based on potential risk significance relative to the reactor safety cornerstones. As applicable for each activity, the inspectors verified that Exelon personnel performed risk assessments as required by 10 CFR 50.65(a)(4) and that the assessments were accurate and complete. When Exelon performed emergent work, the inspectors verified that operations personnel promptly assessed and managed plant risk.
The inspectors reviewed the scope of maintenance work and discussed the results of the assessment with the station's probabilistic risk analyst to verify plant conditions were consistent with the risk assessment. The inspectors also reviewed the technical specification requirements and inspected portions of redundant safety systems, when applicable, to verify risk analysis assumptions were valid and applicable requirements were met.
Core spray system 1 unavailable during planned surveillance testing on September 5, 2012 Containment spray and emergency service water system 1 unavailable for planned surveillance testing on July 10, 2012 Yellow shutdown risk due to high decay heat during forced outage on July 25, 2012 Spent fuel pool cooling leak alarm switch planned unavailability on July 16, 2012 Declaration of maximum emergency generation action on July 17, 2012
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
a. Inspection Scope
The inspectors reviewed operability determinations for the following degraded or non-conforming conditions: C and D 4160 volt switchgear rooms increased room temperature (IR 1069881) on July 17, 2012 D electromagnetic relief valve increased tailpipe temperature (IR 1392048) on July 23, 2012 Abnormal containment spray pump suction pressure (IR 1395902) on August 1, 2012 1-3 emergency service water pump motor cable insulation slit (IR 1415395) on September 20, 2012 Standby liquid poison pump motor power cable clamp broken (IR 1406505) on August 30, 2012 Containment high range radiation detector channel 1 spiking (IR 1393167) on July 25, 2012 The inspectors selected these issues based on the risk significance of the associated components and systems. The inspectors evaluated the technical adequacy of the operability determinations to assess whether technical specification operability was properly justified and the subject component or system remained available such that no unrecognized increase in risk occurred. The inspectors compared the operability and design criteria in the appropriate sections of the technical specifications and UFSAR to Exelon's evaluations to determine whether the components or systems were operable. Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were properly controlled by Exelon. The inspectors determined, where appropriate, compliance with bounding limitations associated with the evaluations.
b. Findings
No findings were identified.
1R18 Plant Modifications
.1 Permanent Modifications
a. Inspection Scope
The inspectors evaluated a modification to the low level radiological waste facility implemented by engineering change package 12-000006, "Commercial Change by Work Order for Low Radiation Waste Mechanical Equipment Room Changes." The inspectors verified that the design bases, licensing bases, and performance capability of the affected systems were not degraded by the modification. In addition, the inspectors reviewed modification documents associated with the design change, including modifications to the mechanical equipment room of the dry active waste compaction area of the low level radiological waste building. The inspectors verified that the design bases, licensing bases, and performance capability of the affected systems were not degraded by the modification. In addition, the inspectors reviewed modification documents to ensure the abandonment of the ventilation equipment and HEPA filtration system and the addition of sealed radioactive sources did not negatively affect the design functions described in the FSAR.
b. Findings
No findings were identified.
1R19 Post-Maintenance Testing
a. Inspection Scope
The inspectors reviewed the post-maintenance tests for the maintenance activities listed below to verify that procedures and test activities ensured system operability and functional capability. The inspectors reviewed the test procedure to verify that the procedure adequately tested the safety functions that may have been affected by the maintenance activity, that the acceptance criteria in the procedure was consistent with the information in the applicable licensing basis and/or design basis documents, and that the procedure had been properly reviewed and approved. The inspectors also witnessed the test or reviewed test data to verify that the test results adequately demonstrated restoration of the affected safety functions.
B isolation condenser steam inlet valve (V-14-33) packing replacement (R2157329) on July 24, 2012 Spent fuel pool cooling leak alarm switch replacement (C2025662) on July 16, 2012 Containment system II following component calibrations (R2200896) on July 18, 2012 Service water pump 1-1 after pump replacement (R2196685) on September 20, 2012 Outboard main steam isolation valve, V-1-9, maintenance adjustment after fast valve stroke time (R2188673) on July 25, 2012 #2 Emergency diesel generator following troubleshooting for lockout light illumination (C2308788) on July 25, 2012 C Electromatic relief valve pressure switch replacement (R2206650) on September 25, 2012
b. Findings
No findings were identified.
1R20 Refueling and Other Outage Activities
a. Inspection Scope
The inspectors reviewed the station's work schedule for forced maintenance outage (1F29), which was conducted July 23, 2012 through July 25, 2012. The inspectors reviewed Exelon's development and implementation of outage plans and schedules to verify that risk, industry experience, previous site-specific problems, and defense-in-depth were considered. During the outage, the inspectors observed portions of the cooldown processes and monitored controls associated with the following outage activities: Configuration management, including maintenance of defense-in-depth, commensurate with the outage plan for the key safety functions and compliance with the applicable technical specifications when taking equipment out of service Status and configuration of electrical systems and switchyard activities to ensure that technical specifications were met Monitoring of decay heat removal operations Activities that could affect reactivity Maintenance of secondary containment as required by technical specifications Identification and resolution of problems related to outage activities Additionally, the inspectors monitored startup preparations as well as portions of the reactor startup following the forced outage.
b. Findings
No findings were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors observed performance of surveillance tests and/or reviewed test data of selected risk-significant SSCs to assess whether test results satisfied technical specifications, the UFSAR, and Exelon procedure requirements. The inspectors verified that test acceptance criteria were clear, tests demonstrated operational readiness and were consistent with design documentation, test instrumentation had current calibrations and the range and accuracy for the application, tests were performed as written, and applicable test prerequisites were satisfied. Upon test completion, the inspectors considered whether the test results supported that equipment was capable of performing the required safety functions. The inspectors reviewed the following surveillance tests: Diesel generator #2 load test on July 16, 2012 Containment spray and emergency service water system 1 pump in-service test on July 10, 2012 "B" standby liquid control pump and valve operability and in-service test on July 5, 2012 "B" isolation condenser shell water level instrument calibration on July 3, 2012 Core Spray System 1 Pump Operability and Quarterly In-service Test on September 5, 2012 Electromatic relief valve operability test on July 27, 2012 Reactor coolant system leak rate on July 31, 2012
b. Findings
No findings were identified. Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
.1 Emergency Preparedness Drill Observation
a. Inspection Scope
The inspectors evaluated the conduct of a routine Exelon emergency drill on July 10, 2012 to identify any weaknesses and deficiencies in the classification, notification, and protective action recommendation development activities. The inspectors observed emergency response operations in the simulator, technical support center, and emergency operations facility to determine whether the event classification, notifications, and protective action recommendations were performed in accordance with procedures.
The inspectors also attended the station drill critique to compare inspectors' observations with those identified by Exelon staff in order to evaluate Exelon's critique and to verify whether the Exelon staff was properly identifying weaknesses and entering them into the corrective action program.
b. Findings
No findings were identified.
.2 Training Observations
a. Inspection Scope
The inspectors observed a simulator training evolution for licensed operators on September 13, 2012, 2612.885.0.0911A, Manual Reactor Scram after Security Event, which required emergency plan implementation by an operations crew. Exelon planned for this evolution to be evaluated and included in performance indicator data regarding drill and exercise performance. The inspectors observed event classification and notification activities performed by the crew. The inspectors also attended the post-evolution critique for the scenario. The focus of the inspectors' activities was to note any weaknesses and deficiencies in the crew's performance and ensure that Exelon evaluators noted the same issues and entered them into the corrective action program.
b. Findings
No findings were identified. 2. Radiation Safety Cornerstones: Public Radiation Safety and Occupational Radiation Safety
2RS2 Occupational ALARA Planning and Controls
a. Inspection Scope
The inspectors reviewed the ALARA work activity evaluations, exposure estimates, exposure reduction requirements and measures taken by Exelon to track, trend and reduce occupational doses for ongoing work activities to assess performance with respect to maintaining individual and collective radiation exposures ALARA. This inspection will determine whether the licensee's ALARA program, including administrative, operational, and engineering controls, is effectively maintaining occupational exposure ALARA.
b. Findings
No findings were identified.
2RS3 In-Plant Airborne Radioactivity Control and Mitigation
a. Inspection Scope
The inspectors reviewed the updated final safety analysis report, technical specification, air sample test results, equipment maintenance and test records, inspection and maintenance procedures, and system operational procedures. The inspectors reviewed procedural guidance for use of installed plant systems to reduce dose and assessed whether the systems are used, to the extent practicable, during high-risk activities. The inspectors reviewed instrument setpoints to verify that in-plant airborne concentrations are being controlled consistent with ALARA to the extent necessary to validate plant operations as reported by the performance indicators and to verify that the practices and use of respiratory protection devices on site do not pose an undue risk to the wearer.
The inspectors reviewed a sample of training and medical records to verify that employees were properly qualified to use respiratory protection devices. The inspectors monitored several employees as they demonstrated the use of respiratory protection devices. The inspectors spot check several respiratory protection devices and verified that they were in acceptable material condition and maintained properly.
b. Findings
No findings were identified.
2RS4 Occupational Dose Assessment
a. Inspection Scope
The inspectors reviewed the results of Exelon radiation protection program audits related to internal and external dosimetry. The inspectors reviewed the most recent National Voluntary Laboratory Accreditation Program accreditation report on the licensee vendor's most recent results to determine the status of the accreditation. The inspectors reviewed licensee procedures associated with dosimetry operations, including issuance/use of external dosimetry, assessment of internal dose, and evaluation of and dose assessment for radiological incidents. The inspectors evaluated whether the licensee had established procedural requirements for determining when external dosimetry and internal dose assessments are required. The inspectors waked down and evaluated the onsite storage of dosimeters before issuance, during use, and before processing/reading. The inspectors also reviewed the guidance provided to radiation workers with respect to care and storage of dosimeters. The inspectors reviewed dosimetry occurrence reports or corrective action program documents for adverse trends related to electronic pocket dosimeters. The inspectors reviewed procedures used to assess the dose from internally deposited radionuclides using whole body counting equipment. The inspectors reviewed the documentation for two individuals who had declared pregnancy during the current assessment period and evaluated whether the licensee's radiological monitoring program (internal and external) for declared pregnant workers is technically adequate to assess the dose to the embryo/fetus. The inspectors reviewed exposure results and monitoring controls the licensee implemented. The inspectors evaluated the licensee's neutron dosimetry program, including dosimeter types and/or radiation survey instrumentation.
b. Findings
No findings were identified.
2RS5 Radiation Monitoring Instrumentation
a. Inspection Scope
The inspectors reviewed maintenance records, testing records, source check records, calibration records, alarm setpoint calculations and walked down a sample of various radiation monitors including whole-body counters used to detect workers' surface and internal contamination to verify proper setup and operation. The inspectors reviewed Exelon and third-party evaluation reports of the radiation monitoring program since the last inspection to look for trends. The inspectors reviewed procedures that govern instrument source checks and calibrations, focusing on instruments used for monitoring transient high radiological conditions, including instruments used for underwater surveys.
The inspectors walked down a representative sample of Exelon's effluent radiation monitoring systems and observed Exelon personnel conducting source checks to verify proper operation of the monitors. The inspectors walked down area radiation monitors and continuous air monitors to determine whether they are appropriately positioned relative to the radiation sources or areas they were intended to monitor.
The inspectors reviewed daily performance checks and calibration data to show that the frequency of the calibrations is adequate and there were no indications of degraded performance of laboratory analytical instruments used for radiological analyses.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
.1 Reactor Coolant System (RCS) Specific Activity and RCS Leak Rate (2 samples)
a. Inspection Scope
The inspectors reviewed Exelon's submittal for the RCS specific activity and RCS leak rate performance indicators for the period of July 1, 2011 through June 30, 2012. 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 RCS sample analysis and control room logs of daily measurements for RCS leakage, and compared that information to the data reported by the performance indicator.
b. Inspection Findings No findings were identified.
4OA3 Follow-Up of Events and Notices of Enforcement Discretion
.1 Plant Events
a. Inspection Scope
For the plant events listed 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 appropriate regional personnel, and compared the event details with criteria contained in IMC 0309, "Reactive Inspection Decision Basis for Reactors," for consideration of potential reactive inspection activities. As applicable, the inspectors verified that Exelon made appropriate emergency classification assessments and properly reported the event in accordance with 10 CFR Parts 50.72 and 50.73. The inspectors reviewed Exelon's follow-up actions related to the events to assure that Exelon implemented appropriate corrective actions commensurate with their safety significance.
Oyster Creek emergency planning zone sirens unreliable due to interference on siren activation radio frequency on July 13, 2012. Notice of unusual event due to loss of offsite power and scram on July 23, 2012 Reactor water cleanup system isolation on August 8, 2012
b. Findings
No findings were identified.
4OA5 Other Activities
.1 (Closed) Temporary Instruction 2515/185, Revision 1, Follow-up On the Industry's Groundwater Protection Initiative
a. Inspection Scope
An NRC assessment was performed on the OCGS Groundwater Protection Program from August 6, 2012 to August 10, 2012 to determine whether Exelon fully implemented the voluntary industry groundwater protection initiative, (Nuclear Energy Institute NEI 07-07 Industry Groundwater Protection Initiative - Final Guidance dated August 2007, ADAMS Accession Numbers ML072610036 and ML072600292). The inspectors interviewed personnel, reviewed applicable documents and performed walkdowns of selected areas. In addition, the inspectors followed-up on status of implementation for the seven deviations to the acceptance criteria in NEI 07-07 that were reported in the NRC integrated inspection report 05000219/2009005, dated January 26, 2010: 1.2.g Establish the frequency for periodic reviews of SSCs and work practices.
1.3.f Establish a long-term program for preventative maintenance of groundwater wells.
1.4.a Establish written procedures outlining the decision making process for remediation of leaks and spills or other instances of inadvertent releases. This process is site specific and shall consider migration pathways.
1.4.b Evaluate the potential for detectible levels of licensed material resulting from planned releases of liquids and/or airborne materials. 1.4.c Evaluate and document, as appropriate, decommissioning impacts resulting from remediation activities or the absence thereof.
3.1.a An independent, knowledgeable individual(s) shall perform the initial self-assessment within one year of implementation. For existing plants, this means no later than December 31, 2008; for new plants this means within one year after initial criticality. 3.2.a An independent, knowledgeable individual(s) shall perform the initial review within one year of the initial self-assessment performed per Objective 3.1.a above.
b. Findings and Observations
No findings were identified. The Industry Groundwater Protection Initiative has been fully implemented at OCGS.
Two of the NEI 07-07 acceptance criteria were found by the licensee as not being properly implemented. Groundwater protection program improvements are being taken. Exelon placed these program improvements into their corrective action program (IR 1370473 and IR 1041403).
.2 Temporary Instruction 2515/187 - Inspection of Near-Term Task Force Recommendation 2.3 - Flooding Walkdowns
On August 16, 2012 inspectors commenced activities to independently verify that Exelon conducted external flood protection walkdown activities using an NRC-endorsed walkdown methodology. These flooding walkdowns are being performed at all sites in response to Enclosure 4 of a letter from the NRC to licensees entitled, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (ADAMS Accession No.
ML12053A340). The results of this temporary instruction will be documented in a future inspection report.
.3 Temporary Instruction 2515/188 - Inspection of Near-Term Task Force Recommendation 2.3 - Seismic Walkdowns
On August 20, 2012, inspectors commenced activities to independently verify that Exelon conducted seismic walkdown activities using an NRC-endorsed seismic walkdown methodology. These seismic walkdowns are being performed at all sites in response to Enclosure 3 of a letter from the NRC to licensees entitled, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (ADAMS Accession No.
ML12053A340). When complete, the results of this temporary instruction will be documented in a future inspection report.
4OA6 Meetings, Including Exit
On October 16, 2012, the inspectors presented the inspection results to Mr. R. Peak, Plant Manager and other members of the Exelon staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
4OA7 Licensee-Identified Violations
None ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- M. Massaro, Site Vice-President
- R. Peak, Plant Manager
- M. Ford, Director, Operations
- G. Malone, Director, Engineering
- J. Dostal, Director, Maintenance
- C. Symonds, Director, Training
- D. DiCello, Director, Work Management
- J. Barstow, Manager, Regulatory Assurance
- T. Farenga, Radiation Protection Manager
- D. Cherneski, Manager, Environmental/Chemistry
- T. Keenan, Manager, Site Security
- W. Trombley, Senior Manager, Plant Engineering
- H. Ray, Senior Manager, Design Engineering
- G. Flesher, Shift Operations Superintendent
- J. Chrisley, Regulatory Assurance Specialist
- D. Moore, Regulatory Assurance Specialist
- J. Kerr, Regulatory Assurance Specialist
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened/Closed
None
Opened
None
Closed
- None
- Attachment
LIST OF DOCUMENTS REVIEWED
Section 1R01: Adverse Weather Protection
Procedures
- OP-CC-108-109-1001, Severe Weather Preparation T&RM for Oyster Creek, Revision 9
- ABN-60, Grid Emergency, Revision 10
- ABN-36, Loss of Off-Site Power, Revision 20 341, Emergency Diesel Generator Operation, Revision 96
- OP-AA-106-101, Significant Event Reporting, Revision 14
- OP-AA-102-102, General Area Checks and Operator Field Rounds, Revision 10
Condition Reports
- 1069881
Miscellaneous
- Calculation Sheet, 1302-821-5360-002, 4160 Switchgear Loss of Ventilation, Revision 0
- Calculation Sheet,
- C-1302-821-5360-006, 4160V SWGR & 'C' Battery Room Temp, Revision 0
Section 1R04: Equipment Alignment
Procedures
- 310, Containment Spray System Operation, Revision 103
- 307, Isolation Condenser System, Revision 117 311, Fuel Pool Cooling System, Revision 106 304, Standby Liquid Control system Operation, Revision 46
Drawings
- GE 885D781, Core Spray System Flow Diagram, Revision 71
- GE 148F723, Liquid Poison System, Revision 39 3E-611-17-009, Electrical Elementary Diagram Control Panel 3F-ANNUN. G, Revision 11
- GE 157B6350, Liquid Poison System Electrical Elementary Diagram, Revision 15
- Maintenance Orders/Work Orders R2126324
Section 1R05: Fire Protection
Procedures
- OP-OC-201-008-1001, Reactor Building (119' Elevation) (RB-FZ-1A), Revision 1
- OP-OC-201-008-1018, Control Room (OB-FZ-5), Revision 1
- OP-OC-201-008-1005, Reactor Building (23' Elevation) (RB-FZ-1E1), Revision 1
- OP-OC-201-008-1007, Reactor Building (33' Elevation) Tip Drive Area (RB-FZ-1E2), Revision 0
- OP-OC-201-008-1035, Emergency Diesel Generator Room #1 (DG-FA-15), Revision 2
- 333.2, General Guidance for the Operation of the B.5.b Portable Pump for Non-Emergency Conditions, Revision 6
- Maintenance Orders/Work Orders R2196065
- Attachment
Section 1R11: Licensed Operator Requalification Program
Miscellaneous
- 2612.885.0.0911A, Manual Reactor Scram after Security Event
Section 1R12: Maintenance Effectiveness
Procedures
- 612.4.001, Standby Liquid Control Pump and Valve Operability and In-Service Test, Revision 42 645.4.036, Fire Pump 2 Operability Test, Revision 20
- 101.2, Oyster Creek Site Fire Protection Program, Revision 68
- ER-AA-310, Implementation of Maintenance Rule, Revision 8
- ER-AA-310-1005, Maintenance Rule - Disposition Between (a)(1) and (a)(2), Revision 6 LS-
- AA-125-1003, Apparent Cause Evaluation Manual, Revision 10
- ER-AA-310-1001, Maintenance Rule - Scoping, Revision 4
Condition Reports
- 1385071
- 1374437
- 1387002
- 1458806
- 1336412
- Maintenance Orders/Work Orders R2157398 R2157397 R2157367
Miscellaneous
- Maintenance Rule Scoping Document, Revision 28 System Health Reports
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
Procedures
- WC-OC-101-1001, Online Risk Management and Assessment, Revision 9
- OP-AA-108-117, Protected Equipment Program, Revision 2
- ER-AA-600-1042, On-Line Risk Management, Revision 7
- 311, Fuel Pool Cooling System, Revision 106
- 607.4.014, Containment Spray and ESW System 1 Pump Operability, IST and Containment Spray Pumps Trip, Revision 42
- ABN-60, Grid Emergency, Revision 10
- OP-AA-108-107-1001, Station Response to Grid Capacity Conditions, Revision 4
- WC-AA-101, On-Line Work Control Process, Revision 18
- MA-AA-716-230-1003, Thermography Program Guide, Revision 4
- OP-AA-106-101, Significant Event Reporting, Revision 14
- OP-AA-102-102, General Area Checks and Operator Field Rounds, Revision 10
Condition Reports
- 1390871
- 1390285
- 1389933
- Maintenance Orders/Work Orders
- C2025662 R21905350 R2190074
- Attachment Miscellaneous Oyster Creek Nuclear Generating Station Operations Logs dated July 18, 2012
- Oyster Creek Nuclear Generating Station Operations Logs dated July 17, 2012 PJM Emergency Messages dated July 18, 2012 PJM Emergency Messages dated July 17, 2012
Section 1R15: Operability Determinations and Functionality Assessments
Procedures
- LS-AA-120, Issue Identification and Screening Process, Revision 10
- OP-AA-108-115, Operability Determinations (CM-1), Revision 10
- OP-AA-106-101-1006, Issue Resolution Documentation Form, Revision 11
Condition Reports
- 1415395
- 1069881
- 1392048
Miscellaneous
- 1302-821-5360-002, Calculation, 4160 Switchgear Loss of Ventilation, Revision 0
- C-1302-821-5360-006, Calculation, 4160 V SWGR & 'C' Battery Rm Temp, Revision 0
- ODM 1392048, D EMRV Increased Tailpipe and Downcomer Temperatures, dated July 23, 2012 PJM Grid Operator Emergency Message 77369
Section 1R18: Plant Modifications
Procedures
- CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 22
- CC-AA-103, Attachment F Screening Criteria for Commercial Changes, Revision 22
- CC-AA-104-1000, EXELON 50.59 Resource Manual, Revision 6
- CC-AA-309-101, Engineering Technical Evaluations, Revision 13
- HU-AA-1212, Technical Task Risk/Rigor Assessment, Pre-Job Brief, Independent Third Party Review and Post Job-Review, Revision 4
Drawings
- 3E-155-02-001, General Arrangement New Radwaste BLDG Plan Floor, Revision 9
- GA 904202, Bldg Service HVAC Truck Bay Cell Storage Daw Compaction and Daw Storage
- HVAC System, Revision 0
- Energy Particulate Absorber Exhaust System, Revision 1
Condition Reports
- 1375627
- 1300420
- 2292911
- Maintenance Orders/Work Orders R2200895
- A2292911
Miscellaneous
- Oyster Creek Nuclear Generating Station Updated Final Safety Analysis Report section 11.4.3, Storage Facilities Attachment GPU Nuclear, SE No. 402.533.001, Safety Evaluation Report in Support of an On-site Low Level Radioactive Storage Facility at Oyster Creek Nuclear Generating Station, Revision 5 A2292911, Technical Evaluation for LLRWSF Changes, dated December 9, 2011 OCGS Radiological Survey No.
- WAA-12-00665, LLRWSF- Radiac Facility, dated February 6, 2012 OCGS Radiological Survey No.
- WAA-12-04664, Radiac Facility NRC Inspection, dated
- August 23, 2012
Section 1R19: Post-Maintenance Testing
Procedures
- 609.4.001, Isolation Condenser Valve Operability and In Service Test, Revision 73
- OP-MA-109-101, Clearance and Tagging, Revision 13
- MA-AA-716-012, Post Maintenance Testing, Revision 16
- 311, Fuel Pool Cooling System, Revision 106
- MA-AA-716-040, Control of Portable Measurement and Test Equipment Program, Revision 7
- MA-AA-716-012, Post Maintenance Testing, Revision 16 607.3.002, Containment Spray Component Calibration, Revision 60 607.4.017, Containment Spray and Emergency Service Water Pump System 2 Operability and Quarterly InService Test, Revision 30
Condition Reports
- 01392624
- 01392668
- 01389635
- 01389627
- 14145450
- 1416284
- 1416282
- Maintenance Orders/Work Orders R2188673 R2157329
- C2025662 R2203998 R2196685 R2200896
- R2206650
Section 1R20: Refueling and Other Outage Activities
Procedures
- OP-AA-108-108, Unit Restart Review
- EP-AA-1010, Exelon Nuclear Radiological Emergency Plan Annex for Oyster Creek Station, Oyster, Revision 4
Condition Reports
- 1394173
- 1394083
- 1391926
- 1391790
- 1391785
- 1391773
- 1391771
- 1392155
- 1392654
- 1393719
- 1393167
- 1393674
- 1393734
- 1393750
Miscellaneous
- Departmental Startup Checklists, dated July 24, 2012 and July 25, 2012
- 1392048-03, Operational Decision Making Issue Resolution Documentation Form, "Elevated Temperature in D EMRV Tailpipe"
- OP-AA-108-114 Attachment 4, Post Transient Review - BWR, dated July 24, 2012
- 1392080, Prompt Investigation for Reactor Building Low Differential Pressure Alarm
- 1392155, Troubleshooting Log for Emergency Diesel Generator #2
- Plant Process Computer Trend Data for Condenser Vacuum, Dated July 26 and 27, 2012
- Attachment
Section 1R22: Surveillance Testing
Procedures
- 602.4.003, Electromatic Relief Valve Operability Test, Revision 35 636.4.013, Diesel Generator #2 Load Test, Revision 32
- 2.4.001, Standby Liquid Control Pump and Valve Operability and In-Service Test, Revision 40
- 609.3.008, Isolation Condenser "B" Shell Water Level Instrument Calibration (IG06B),
- Revision 28 312.9, Primary Containment Control, Revision 53
- ER-AB-331-1006, BWR Reactor Coolant System Leakage Monitoring and Action Plan,
- Revision 2 607.3.002, Containment Spray Component Calibration - System 1, Revision 61
- 2.4.003, Electromatic Relief Valve Operability, Revision 35
- Condition Reports/IR
- 1385071
- 01385071
- 1384837
Miscellaneous
- C-1302-862-5360-002, Calculation Diesel Generator Fuel Requirements, Usable Tank Volume and Pump NPSH, Revision 5
- C-1302-211-E320-126, Calculation Isolation Condenser Shell Level Uncertainty (Normal Environment), Revision 4 681.4.004, Technical Specification Log Sheet, performed 4/11/11
- OC 02-00927 000, Evaluate Core Spray Pump and Valve IST Acceptance Criteria, dated September 2, 2002 Design Analysis
- C-1302-212-5310-091, Revision 1a (ECR
- AC-573-1202-0001, Adverse Condition Monitoring and Contingency Plan, UILR monitoring with unknown leakage source, Revision 2 681.4.004, Technical Specification Log Sheet, dated August 27, 2012
Section 1EP6: Drill Evaluation
Condition Reports
- 1387595
- 1389573
- 1387613
- 1392383
- 1392398
- 1392342
- 1392344
- 1387587
- 1387585
- 1387570
- 1387841
- 1387687
- Section 2RSO2:
- Occupational ALARA Planning and Controls
Procedures
- RP-AA-402, Radiation Protection Dose Excellence Planning Process, Revision 3
Condition Reports
- 1161318
Miscellaneous Documents
- OC Radiation Protection O1R23 - 2010 Refueling Outage Report OC Outage ALARA Plan Dose Estimates vs. Actual Dose R-20 to R-24, August 21, 2012
- ALARA Plan 12-519 Drywell In-Service Inspection
- ALARA Plan 12-511 CRD Exchange Attachment ALARA Plan 12-503 Under-vessel Maintenance Activities ALARA Plan 12-402 Reactor Disassembly/Fuel Shuffle/Reactor Reassembly
- 2012 Shielding Packages for R24, dated August 20, 2012 OCGS Radiological Survey 12-04587
- RWP 12-01802
- RP-AA-401 Attachment 2 ALARA Plan 12-1802 Replace #1 TIP Detector, dated August 20, 2012 OCGS Radiological Survey
- WAA-12-00665
- LLRWSF-Radiac Calibration Room, dated
- February 6, 2012 OCGS Radiological Survey
- WAA-12-04664 Radiac Facility -
- LLRWSF-NRC Inspection, dated August 23, 2012
- Section 2RSO3:
- In-Plant Airborne Radioactivity Control and Mitigation
Procedures
- CY-OC-120-940, Drywell Atmosphere Analysis & CAPGRMS Sampling, Revision 7
- RP-AA-440, Respiratory Protection Program, Revision 10
- RP-AA-443, Quantitative Respirator Fit Testing, Revision 11
- RP-AA-825, Maintenance Care and Inspection of Respiratory Protection Equipment, Revision 4
- RP-OC-825-1002, Use of Compressed Air for Supplied Air Respirator, Revision 2
- RP-OC-826, Inspection of MSA Firehawk Mask Mounted Regulator SCBAS, Revision 5
- RP-OC-827, Flow Testing MSA Firehawk (MMR) SCBAS, Revision 2
- RP-AA-825-1013, Operation and Inspection of the 3M Air-Mate Hood and Paper Blower Unit, Revision 3
- RP-AA-825-1012, Inspection and use of the MURUROA Blu Ethfuge PVC Paper suit, Revision 2
- RP-AA-825-1011, Inspection and use of the MURUROA V4 MTH2 AND V4 F1 Air Supplied Suit, Revision 4
- RP-AA-825-1020, Operation and Use of Air Line Supplied Respirators, Revision 0
- 21.3.042, Containment Airborne, Particulate, Gaseous, Radiation Monitoring System Calibration, Revision 14 621.3.002, SGTS Particulate Filter In-Place Leak Test, Revision 28
- 21.3.003, SGTS Charcoal Filter In-Place Testing, Revision 25
Condition Reports
- 1154042
- 1390691
- 1390694
- 1390698
- 1168173
- 1227347
- 1176846
- 1279769
- 1304181
- 1304892
Miscellaneous Documents
- System Health Report 2nd Quarter 2012 for Reactor Building Ventilation, dated July 12, 2012 System Health Report 2nd Quarter 2012 for Control HVAC, dated July 13, 2012
- LS-AA-126-1005 Attachment 2, Check-In Self-Assessment Template
- 1134316-02, 2011 RP Nuclear Regulatory Commission Check-In Self-Assessment, dated January 28, 2011 TRI Air Testing, Inc. Compressed Air Quality Testing, dated July 8, 2011
- TRI Air Testing, Inc. Compressed Air Quality Testing, dated August 20, 2012
- TSI Certificate for Testing for Portacount Bench 2 Serial 15965, dated July 19, 2012 Sperian Certificate of Calibration 20080811L04092 for EXELON Corp. Biosystems PosiChek3 Performance Tester Serial No. L04092, dated August 8, 2011 Lawrence Factor Certified Pure Breathing Air/Gas CGA Class E, dated January 7, 2011
- OC Vacuum Cleaner Inventory, dated August 23, 2012
- Attachment OC HEPA Ventilation Inventory, dated August 23, 2012 Portacount Fit Test Report for Millenium Full-face Respirator Medium, dated August 22, 2012
- RP-OC-826 Attachment 7, July 2012 Emergency Equipment - SCBA Check Off sheet, dated August 2, 2012 NCS Corporation, Radioiodine Penetration/Efficiency Test Record SBGT System #1, dated December 7, 2011 NCS Corporation, Radioiodine Penetration/Efficiency Test Record SBGT System #2, dated December 7, 2011
- DW Undervessel Maintenance, dated January 13, 2012
- CRD Exchange and Support Work, dated January 13, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #700044, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #700036, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #1857, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #2760, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #700052, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #2756, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #2758, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for
- AMS-3 #2761, dated August 5, 2012
- RP-AA-301 Attachment 2 Airborne Radioactivity Calculation Sheet for Lo-Vol #70192, dated August 5, 2012 NIOSH Mine Safety Appliances Company Firehawk M7 Responder Air mask, Open Circuit, Pressure Demand, CBRN, Entry and Escape Self Breathing Apparatus Rad Pro Technician Daily Routine Checklist includes Weekly Routine Air Sample Check and Filter Change and Chart Paper Change, dated August 12, 2012
- Section 2RSO4:
- Occupational Dose Assessment
Procedures
- RP-AA-11, External Dose Control Program Description, Revision 0
- RP-AA-12, Internal Dose Control Program Description, Revision 1
- RP-AA-201-1001, Radiological Instruction Sheet for Escorted Visitors, Revision 1
- RP-AA-203-1001, Personnel Exposure Investigations, Revision 6
- RP-AA-210, Dosimetry Issue, Usage and Control, Revision 22
- RP-AA-210-1001, Dosimetry Logs and Forms, Revision 7
- RP-AA-210-1003, REMS Access Control Outage Guidance, Revision 0
- RP-AA-211, Personnel Dosimetry Performance Verification, Revision 9
- RP-AA-220, Bioassay Program, Revision 8
- RP-AA-221-1001, Collection and Handling of In Vitro Bioassay Samples, Revision 0
- RP-AA-221, Whole Body Count Data Review, Revision 1
- Attachment
- RP-AA-222, Method for Estimating Internal Exposure from In Vivo and In Vitro Bioassay Data, Revision 1
- RP-MA-210-1005, Issuing and Terminating Dosimetry in PIMS, Revision 0
Condition Reports
- 1173163
- 1246277
- 1266640
- 1264461
- 1307239
- 1364762
- 1377166
- 1382418
- 1359080
- 1399412
- 1375832
Miscellaneous Documents
- OC-12-02 Radiation Protection Calculation and Position Paper:
- 2012
- ARGOS-5AB Gamma Sensitivity Study, June 28, 2012 NAVLAP Certification for Landauer Inc., NAVLAP Lab Code 100518-0, dated April 23, 2012
- 2011 Exelon Nuclear Oyster Creek Dose Deviations Between Estimate & Official Dose of Record Read Greater than 25%, dated August 21, 2012 1st Quarter 2012 Exelon Nuclear Oyster Creek Dose Deviations Between Estimate & Official Dose of Record Read Greater than 25%, dated August 21, 2012 2nd Quarter 2012 Exelon Nuclear Oyster Creek Dose Deviations Between Estimate & Official Dose of Record Read Greater than 25%, dated August 21, 2012 OC Personnel Exposure Investigation Log 2011, dated August 21, 2012 OC Personnel Exposure Investigation Log 2012, dated August 21, 2012
- LS-AA-126-1005 Attachment 2 Check In Self-Assessment Report #1134316-02-2011 RP Nuclear Regulatory Commission Check-In Self-Assessment, dated January 28, 2011
- RP-AA-270 Attachment 4 Embryo/Fetus Dose Report, dated May 3, 2012
- RP-AA-270 Attachment 4 Embryo/Fetus Dose Report, dated July 30, 2011
- Section 2RSO5: Radiation Monitoring Instrumentation
Procedures
- RP-AA-230, Operation of the Canberra Fastscan Whole Body Counter, Revision 0
- RP-AA-700, Controls for Radiation Protection Instrumentation, Revision 3
- RP-AA-700-1100, Operation of the Eberline
- RO-2-2A-20, Bicron
- RSO 50E, Revision 0
- RP-AA-700-1101, Calibration of the
- RO-2,
- RO-2A,
- RO-20 and
- RSO-50F Ion Chambers, Revision 0
- RP-AA-700-1200, Operation of the Eberline
- RM-14-20-25, Revision 0
- RP-AA-700-1201, Operation of the MGP Instrument Telepole, Revision 0
- RP-AA-700-1203, Calibration of the MGP Instruments Telepole, Revision 0
- RP-AA-700-1204, Operation of the
- SAC-4 Alpha Counter, Revision 1
- RP-AA-700-1206, Operation of the Eberline
- RO-7, Revision 0
- RP-AA-700-1207, Calibration of the
- RO-7, Revision 0
- RP-AA-700-1208, Operation of Shepherd Model 89 Calibrator, Revision 0
- RP-AA-700-1209, Calibration of the Shepherd Box Irradiator, Revision 0
- RP-AA-700-1214, Calibration of the
- PCM-1 Personnel Monitor, Revision 0
- RP-AA-700-1215, Calibration of the Radeco Low-Vol Air Samplers, Revision 0
- RP-AA-700-1216, Calibration of Hi-Vol Air Samplers, Revision 0
- RP-AA-700-1225, Calibration of In-Air Gamma Sources, Revision 0
- RP-AA-700-1237, Performance of Smear Testing for Automated Contamination Monitors, Revision 0
- RP-AA-700-1239, Operation and Calibration of the Model
- SAM-12 Small Article Monitor, Revision 0
- RP-AA-700-1240, Operation and Calibration of the Canberra
- ARGOS-5 Personnel Contamination Monitor, Revision 0
- Attachment
- RP-AA-700-1246, Operation of Air Samplers, Revision 2
- RP-AA-700-1249, Operation of the Ludlum Model 3, Revision 0
- RP-AA-700-1300, Calibration, Operation, and Source Check of the Eberline Beta Air Monitor, Model
- AMS-3, Revision 2
- RP-AA-700-1301, Calibration, Source Check, Operation and Set-up of the Eberline Beta Air Monitor
- AMS-4, Revision 0
- RP-AA-700-1302, Operation and Calibration of Portable Neutron Monitors, Revision 0
- RP-AA-700-1303, Bicron Micro-Rem Survey Meter, Revision 0
- RP-AA-700-1401, Operation and Calibration of the Eberline Model
- PM-7 Personnel Contamination Monitor, Revision 1
- RP-AA-700-1500, Operation and Source Check of the Ludlum 3030PAlpha-Beta Sample Counter, Revision 2
- RP-AA-700-1501, Operation and Calibration of the Model
- SAM-9/11Small Article Monitor, Revision 1
- RP-AA-700-1303, Bicron Micro-REM Survey Meter, Revision 0
- RP-OC-301-1002, Background, Efficiency, Operational Check Determination, and Performance of the Scaler Counting System, Revision 8
- RP-OC-700-1100, Operation and Calibration of the
- CRONOS-11 Contamination Monitor, Revision 2 621.3.001, ARM Radiation Monitoring Calibration and Test, Revision 38 621.3.002, Air Ejector Off Gas Radiation Monitor Check Source Functional Test, Revision 28
- 21.3.003, Main Steam Line Radiation Monitor Check Source Functional Test, Revision 29
- 21.3.004, Process Radiation Monitor Test- RBCCW, Revision 27
- 21.3.005, High Radiation Monitor - RX. Bldg, Isolation - Calibration, Revision 51
- 21.3.010, New Rad Waste Area Radiation Monitor Calibration and Test, Revision 19 621.3.012, Radwaste Overboard Discharge Radiation Monitoring System Channel Test, Revision 15 621.3.014, Radwaste Overboard Discharge Radiation Monitoring System Channel Calibration, Revision 12 621.3.017, Calibration of Domestic Effluent Radiation Monitoring System, Revision 28 621.3.018, Domestic Effluent Radiation Monitoring System - Test, Revision 23 621.3.019, Area Radiation Monitoring Trip Point Check and Power Supply Calibration, Revision 11 621.3.020, Off Gas Building Area Radiation Monitoring System Calibration Test, Revision 17
- 21.3.021, AOG Ventilation Monitoring System Channel Calibration, Revision 32
- 21.3.023, Stack RAGEMS Sample and Effluent Flow Calibrations, Revision 25 621.3.024, Stack RAGEMS Sample and Effluent Flow - Functional Test, Revision 5 621.3.025, Stack RAGEMS Noble Gas Monitor Calibration, Revision 31
- 21.3.026, Stack RAGEMS Noble Gas Monitor Functional Test, Revision 30
- 21.4.029, Containment High Range Radiation Monitoring System Front Panel Test, Revision 10
- 621.3.030, Containment High Range Radiation Monitoring System Calibration, Revision 15 621.3.031, Main Steam Line Radiation Monitor Calibration, Revision 15
- 21.3.032, Air Ejector Off Gas Radiation Monitor Calibration Check, Revision 13
- 21.3.033, Air Ejector Off Gas Radiation Monitor Calibration, Revision 15
- 21.3.034, Turbine Building RAGEMS Sample and Effluent Flow - Calibration, Revision 15
- 21.3.036, Turbine Building RAGEMS Noble Gas Channel Calibration, Revision 12 621.3.037, Turbine Building RAGEMS Noble Gas Monitor - Functional Test, Revision 27 621.3.038, Stack and Turbine Building RAGEMS High Range Monitor - Calibration, Revision 15
- 21.3.041, Service Water Radiation Monitoring System Calibration (RN01A, M-3-001, RN08C and RN31B), Revision 16
- Attachment 621.3.042, Containment Airborne Particulate Gaseous Radiation Monitoring System (CAPGRMS) Calibration, Revision 14 621.3.043, Service Water Radiation Monitor Functional Test, Revision 10 621.3.045, Turbine Building RAGEMS Sample and Effluent Flow - Functional Test, Revision 12
Condition Reports
- 1309349
- 1337077
- 1347158
- 1390691
- 1390694
- 1390698
- 1393167
- 1393217
- 1310764
- 1402349
- 1402348
- 1402346
- 1402347
- 1403723
- 1403744
Miscellaneous
- LS-AA-126-1005 Attachment 1 Check In Self Assessment
- AR 1378949 Nuclear Regulatory Commission Inspection
- IP 71124.05 Radiation Monitoring Instruments, August 6, 2012 Station Procedure 116 Revision 86 Attachment 116-1 Surveillance Test Coversheet WO R2094472 - 021.3.030 Containment High Range Monitor Detector Calibration, dated November 2, 2008 Station Procedure 116 Revision 89 Attachment 116-1 Surveillance Test Coversheet WO R2173269, 621.3.038A Stack Radiation Monitor High Range Calibration, dated July 13, 2012 Station Procedure 116 Revision 86 Attachment 116-1 Surveillance Test Coversheet, WO R2136309, 621.3.038B Turbine Stack High Range Monitor Calibration, dated May 25,
- 2010 Station Procedure 116 Revision 87 Attachment 116-1 Surveillance Test Coversheet, WO R2166694, 621.3.023 Stack Radiation Monitor Effluent Flow Calibration, dated May 27, 2011 Station Procedure 116 Revision 87 Attachment 116-1 Surveillance Test Coversheet, WO R2147672, 621.3.034 Turbine Building Radiation Monitor Effluent Flow Calibration, dated February 18, 2011 Station Procedure 116 Revision 89 Attachment 116-1 Surveillance Test Coversheet, WO R2204712, 621.4.029 Containment High Range Radiation Monitoring System Front Panel Test, dated August 2, 2012 Station Procedure 116 Revision 86 Attachment 116-1 Surveillance Test Coversheet, WO R2198102, 621.3.043, Service Water Radiation Monitor Functional Test, dated June 24, 2012 Station Procedure 116 Revision 86 Attachment 116-1 Surveillance Test Coversheet, WO R2151948 Service Water Radiation Monitoring System Calibration, dated August 9, 2011 Amergen
- SDBD-OC-661 Revision 3 Design Basis Document for Radiation Monitoring System, dated September 14, 2009
- RP-OC-1001-08-011 Revision 0, Stack Radiation Gas Emissions Monitoring System (RAGEMS)
- Low Range Radiation Monitoring Alarm Set Point Determination, dated August 22, 2008
- RP-OC-1001-08-012 Revision 0, Turbine Building Radiation Gas Emissions Monitoring System (RAGEMS) Low Range Radiation Monitoring Alarm Set Point Determination, dated August 22, 2008 Operability Evaluation Number
- OC-2012-OE-006 OC Post Accident Monitoring System #644 OC Radiation Protection Calculation and Position Paper: 2011 Periodic Alpha Characterization, dated October 14, 2011 OC Radiation Protection Calculation and Position Paper:
- 2011 10 CFR Part 61, Waste Stream
- Analysis, dated October 7, 2011
- OC Radiation Protection Calculation and Position Paper:
- WBC Calibration Report for 2011, dated July 18, 2012
- Attachment
- RP-AA-700-1401 Attachment 3 Calibration Data Sheet
- PM-7 Portal Monitor #702451, dated May 15, 2012 OC
- PM-7 Calibration Report for
- PM-7 #448, dated December 5, 2011
- RP-AA-700-1501 Attachment 3 SAM Calibration Data Sheet #
- 702317, dated March 14, 2012
- RP-AA-700-1501 Attachment 3 SAM Calibration Data Sheet #
- 702319, dated March 14, 2012
- RP-AA-700-1501 Attachment 3 SAM Calibration Data Sheet # 114, dated March 14, 2012
- OC
- SAM-9 Setup Record #
- 702318, dated August 21, 2012
- RP-AA-700-1240 Attachment 1 Argos-5 Calibration Data Sheet #0912166, dated July 24, 2012
- RP-AA-700-1240 Attachment 1 Argos-5 Calibration Data Sheet #1104047, dated June 6, 2012 Exelon PowerLabs, Certificate of Calibration #
- 079468 MGP Telepole, dated February 28, 2012 Exelon PowerLabs, Certificate of Calibration #
- 079147 MGP Telepole, dated February 27, 2012
- Exelon PowerLabs, Certificate of Calibration #
- 077431 Gilian
- HFS 513A Lapel Air Sampler, dated July 30, 2012
- Exelon PowerLabs, Certificate of Calibration #
- 077542 Gilian
- HFS 513A Lapel Air Sampler, dated July 30, 2012 Exelon PowerLabs, Certificate of Calibration #
- 073357 Eberline
- RO-2, dated December 2, 2011
- Exelon PowerLabs, Certificate of Calibration #
- 073356 Eberline
- RO-2, dated November 18, 2011 Exelon PowerLabs, Certificate of Calibration #
- 079952 Eberline
- ASP-1 Neutron Meter, dated August 4, 2011 Exelon PowerLabs, Certificate of Calibration #
- 0014485 Eberline
- ASP-1/NRD, June 12, 2012
- Exelon PowerLabs OJT #: 209, Processing and Calibration Check of Electronic Dosimetry, Revision 4
- Exelon Work Order R2181153, Perform Calibration of PASS System Radiation Monitor, July 5,
- 2012 Exelon Work Order M2278754, Investigate Air In Leakage in Stack RAGEMS, June 23, 2011 Gamma Irradiation Services, Irradiation Inspection/Performance Calibration Test Report for Oyster Creek Nuclear Power Plant Sheppard and Air Irradiation Table, May 24, 2012
- PowerLab:
- Oyster Creek Rad Pro - Electronic Dosimeter Cal/Check Data from 5/1/12 to
- 8/23/12, August 23, 2012 (new) OC Radiological Survey
- WAA-12-04664 Radiac Facility - LLRWSF: NRC Inspection,
- August 23, 2012
Section 4OA1: Performance Indicator Verification
Miscellaneous
- Performance Indicator Summary Data for July 2010 through June 2012, dated July 19, 2012 Reactor Coolant Activity Spreadsheet, June 2010 through June 2012
- Oyster Creek Unidentified Leakage Trend Spreadsheet November 2010 through June 2012
Section 4OA3: Follow-up of Events and Notices of Enforcement Discretion
Procedures
- EP-AA-1010, Radiological Emergency Planning Annex for Oyster Creek Station, Revision 4
- 303, Reactor Cleanup Demineralizer System, Revision 132
- 2.1, Power Operation, Revision 130
Drawings
- GE148F437, Radioactive Waste Processing System Flow Diagram, Revision 40
- GE148F144, Clean-up Demineralizer System Flow Diagram, Revision 101
- Attachment
Condition Reports
- 1391942
- 1400717
- 1399245
- 1398759
- 1398719
- 1398718
- 1398687
- 1398647
- 1392048
- 1394041
- 1394181
- 1394166
- 1394139
- 1394164
- 1394173
- 1394083
- 1391926
- 1391790
- 1391785
- 1391773
- 1391771
- 1392155
- 1392654
- 1391864
- 1391868
- 1393221
- 1393088
Miscellaneous
- Event Notice 48102 Event Notice 48125
- NEI Position Statement, Guidance To licensees on Complying with the Licensed Power Limit, dated June 12, 2008 NRC, Regulatory Issue Summary 2007-21, Adherence to Licensed Power Limits, Revision 1
- OC-PPC-SRS-0004, System Requirements Specification for the Oyster Creek Heat Balance Calculations and Displays, Revision 3 Oyster Creek Operational Logs, dated August 10, 2012
- Exelon
- Memorandum, "Oyster Creek Generating Station, 07/23/12, Notice of Unusual Event Report, (2012-1)", dated August 16, 2012
- 1391942, Operational Decision Making Issue Resolution Documentation Form, "The N-1028, O-1029, and S-2045 230kV Lines Tripped on a Single Fault" Oyster Creek Nuclear Generating Station Updated Final Safety Analysis Report Section 15.2, Decrease in Heat Removal by the Secondary System, Revision 16 Oyster Creek Nuclear Generating Station Updated Final Safety Analysis Report Section 7.2, Reactor Trip System, Revision 16 Oyster Creek Nuclear Generating Station Updated Final Safety Analysis Report Figure 8.2-2, 230 kV Substation - One Line Diagram, Revision 13 Oyster Creek Nuclear Generating Station Technical Specification 3.7, Auxiliary Electrical Power, Revision 256 Oyster Creek Nuclear Generating Station Operational Logs, dated July 23, 2012 Plant Process Computer Drywell Unidentified Leak Rate Data, dated July 22, 2012
- Plant Process Computer Drywell Unidentified Leak Rate Data, dated July 23, 2012
Section 4OA5: Other Activities
Procedures
- CY-OC-120-706, GW Remediation Process Sample Collection, Revision 4
- EN-AA-408, Radiological Groundwater Protection Program, Revision 0
- EN-AA-408-4000 Radiological Groundwater Protection Program Implementation, Revision 2
- EN-OC-408-4001 RGPP Onsite and Offsite Sample Results Comparison, Revision 0
- EN-OC-408-4160 RGPP Reference Material for Oyster Creek Generating Station, Revision 5
- OP-AA-106-101-1006 Operational Decision Making Process, Revision 11
Condition Reports
- 1302794
- 708870
- 924237
- 983400
- 987696
- 809549
- 1041403
- 1370473
- 1041403
Miscellaneous
- Oyster Creek Environmental Assessment FMEA Component Risk Assessment, November 22,
- 2011
- Attachment Conestoga Rovers & Associates Report No. 055875(6) Hydrogeological Investigation Report,
- Fleetwide Assessment - Oyster Creek Generating Station, Forked River, NJ, April 2011
- LS-AA-126-1005 Check in Self Assessment Report Template, Assignment 825808-23/857066-
- 02, Radiological Groundwater Protection Program (RGPP) Assessment as Required by
- NEI-07-07, December 22, 2008
- LS-AA-126-1005 Check in Self-Assessment Report Template, Assignment
- 1324405,
- Implementation of
- NEI 07-07 in Preparation for
- TI 2515/185, May 24, 2012
- NEI Groundwater Protection Initiative Peer Assessment Report for Oyster Creek Generating Station, February 19, 2010