IR 05000271/2015008
| ML15211A011 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/30/2015 |
| From: | Marc Ferdas, Stephen Hammann NRC/RGN-I/DNMS/NMSB3 |
| To: | Wamser C Entergy Nuclear Operations |
| References | |
| IR 2015001, IR 2015008 | |
| Download: ML15211A011 (21) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION uly 30, 2015
SUBJECT:
NRC INSPECTION REPORT NO. 05000271/2015008 AND ISFSI REPORT NO.
07200059/2015001, ENTERGY NUCLEAR OPERATIONS, INC., VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VERMONT
Dear Mr. Wamser:
On June 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed its quarterly inspection under Inspection Manual Chapter 2561, Decommissioning Power Reactor Inspection Program," at the permanently shut down Vermont Yankee Nuclear Power Station (VY).
Inspection activities were performed between April 1 and June 30, 2015, and included in-office reviews of information supplied by Entergy Nuclear Operations, Inc. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and the conditions of your license. The inspection consisted of observations by the inspectors, interviews with personnel, and a review of procedures and records. The results of this inspection were discussed with Mr. C. Wamser, Site Vice President, and other members of your staff on July 9, 2015, and are described in the enclosed report. No findings of safety significance were identified.
In accordance with 10 Code of Federal Regulations (CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Steve Hammann at 610-337-5399 if you have any questions regarding this matter.
Sincerely,
/RA/
Marc Ferdas, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Docket Nos: 050-00271, 072-00059 License No: DPR-28 Enclosure: Inspection Report 05000271/2015008 and 07200059/2015001 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ
EXECUTIVE SUMMARY
Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station NRC Inspection Report Nos. 05000271/2015008 and 07200059/2015001 An announced quarterly inspection was completed at VY on June 30, 2015. On-site inspections and in-office reviews of information supplied by Entergy were performed during the inspection period from April 1 to June 30, 2015. The inspection included a review of: organizational and management controls, design changes, plant modifications, self-assessments, corrective action program (CAP), site operations, maintenance, surveillance testing, spent fuel pool (SFP) safety,
Independent Spent Fuel Storage Installation (ISFSI) operation, occupational radiation exposure, radioactive material transportation, and emergency preparedness (EP). The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.
The U.S. Nuclear Regulatory Commissions (NRC's) program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561,
Decommissioning Power Reactor Inspection Program." VY is currently in the Post Operation Transition Phase of decommissioning as described in IMC 2561. The NRCs program for overseeing the safe operation of an ISFSI is described in IMC 2690, Inspection Program for Dry Storage of Spent Reactor Fuel at Independent Spent Fuel Storage Installations and for 10 CFR Part 71 Transportation Packages.
Based on the results of this inspection, no findings of safety significance were identified.
REPORT DETAILS
1.0 Background On January 12, 2015, VY certified the permanent removal of fuel from the reactor vessel
[Agencywide Document and Access Management System (ADAMS) Accession No.
ML15013A426]. This met the requirements of 10 CFR 50.82(a)(1)(i) and 50.82(a)(1)(ii).
On January 20, 2015, the NRC notified VY that the Operating Reactor Assessment Program would cease on January 24, 2015 and that implementation of the Decommissioning Power Reactor Inspection Program would begin on January 25, 2015 (ADAMS Accession No. ML15020A482). VY is currently in the Post Operation Transition Phase of decommissioning as described in IMC 2561.
2.0 Post Operation Transition Phase Performance and Status Review 2.1 Organization, Management, and Cost Controls at Permanently Shutdown Reactors
[Inspection Procedure (IP) 36801]
a. Inspection Scope
The inspectors conducted document reviews, performed observations, and interviewed plant personnel to verify the following:
- Entergy established procedures and processes to resolve employee and safety concerns and effectively resolved identified problems;
- Entergy appropriately implemented the Technical Specifications, Technical Requirements Manual, and Fire Protection Plan requirements and commitments;
- Regulatory requirements were properly implemented with respect to the site organization and staff qualifications;
- Entergy appropriately addressed generic communications from the NRC;
- Certified fuel handler and employee training programs were implemented in accordance with Entergy procedures and NRC requirements; and
- Entergys decommissioning activities were initiated, sequenced and performed in a manner consistent with the Post Shutdown Decommissioning Activities Report (PSDAR).
The inspectors also observed security drills conducted by Entergy on May 6, 2015.
b. Observations and Findings
Entergy appropriately implemented organizational and management controls in accordance with regulatory requirements, license conditions and the Technical Specifications. Entergys transition activities were in accordance with the PSDAR. The inspectors noted that Entergy reviewed 10 CFR Part 21 notifications and information notices issued by the NRC and placed them in their CAP as needed. The inspectors noted that the certified fuel handlers had met the requirements of the certified fuel handler training program, and that the training program matched the one approved by the NRC. Items identified by Entergy as areas for improvement were placed in their CAP.
c. Conclusions
No findings of significance were identified.
2.2 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors (IP 37801)
a. Inspection Scope
The inspectors conducted document reviews and interviews with plant personnel to verify the following:
- Entergy procedures and processes conform to the regulations and guidance associated with 10 CFR 50.59;
- Procedures and controls were followed and the applicable changes were effectively implemented in the field, plant procedures, drawings, and training programs;
- Changes made by Entergy under 10 CFR 50.59 did not require prior NRC approval; and
- Changes to preventive maintenance, corrective maintenance and operational procedures for required equipment were implemented in accordance with Entergys processes and procedures.
The inspectors reviewed the modification of a small, air-cooled diesel generator to power loads formerly supplied by the emergency diesel generators, and the planned abandonment of the emergency diesel generators. The inspectors also reviewed the addition of filters and demineralizers to the SFP to replace the previously abandoned ones. The inspectors reviewed the completed engineering change packages for planned changes to the direct current power supply system, the service water system, and the condensate transfer system.
b. Observations and Findings
The inspectors determined that the changes made to plant systems did not require prior NRC approval. Entergy adequately implemented safety reviews, design changes and modifications in accordance with applicable regulatory requirements, license conditions and the Technical Specifications.
c. Conclusions
No findings of significance were identified.
2.3 Self-Assessment, Auditing, and Corrective Actions at Permanently Shutdown Reactors (IP 40801)
a. Inspection Scope
The inspectors conducted document reviews and interviews with plant personnel to verify the following:
- Entergy management performed observations of maintenance and surveillance activities, operations evolutions, and training;
- Entergy performed benchmarking and self-assessments; and
- Issues or problems were identified and corrected in accordance with the CAP.
The inspectors reviewed CAP documents on a daily basis to determine:
- If a sufficiently low threshold for problem identification existed;
- If follow-up evaluations were of sufficient quality, including extent of condition; and
- If Entergy assigned timely and appropriate prioritization for issue resolution commensurate with the significance of the issue.
The inspectors verified that Entergy evaluated issues with the potential for safety or regulatory consequence for apparent and/or common causes. The inspectors observed a sample of condition report review group meetings.
b. Observations and Findings
The inspectors determined that issues were identified by Entergy at an appropriate threshold and entered into the CAP. Issues were effectively screened, prioritized and evaluated commensurate with safety significance during condition report review group meetings. Entergys evaluations determined the significance of issues and included appropriate corrective actions. The inspectors noted that Entergy management attended pre-job briefs and surveillances at an appropriate frequency and retained their oversight role.
The inspectors attended the corrective action review board meeting on April 2 that discussed the apparent cause evaluation performed for condition report (CR)-VTY-2015-403, on the failure of the A and B service water pumps to develop pressure and flow due to icing in the service water bay. Additional information concerning this issue is described in NRC Inspection Report 05000271/2015007, dated May 8, 2015 (ML15131A237). The inspectors noted that Entergy determined the correct cause of the failures and that the proposed corrective actions addressed the cause. However, the apparent cause evaluation had a limited extent of condition discussion, in that it only covered the pumps that draw from the service water bay, which includes the service water pumps and the fire water pumps, but did not consider the need for ice prevention in the deep basin, which supplies water for the B.5.b pump. Additionally, the apparent cause evaluation did not include an equipment failure evaluation, contrary to the instructions in procedure V-EN-LI-102, Performance Improvement Program. Entergy wrote CR-VTY-2015-599 to document the observation and revised the apparent cause evaluation to include the missing information. No new corrective actions were needed to address either the expanded extent of condition or the results of the equipment failure evaluation.
c. Conclusions
No findings of significance were identified.
2.4 Spent Fuel Pool Safety at Permanently Shutdown Reactors (IP 60801)
a. Inspection Scope
The inspectors verified the safe wet storage of spent fuel in the SFP. The review included criticality controls and SFP instrumentation and leakage detection. The inspectors reviewed SFP drawings, integrated logic diagrams and calibration records for the SFP level, temperature and leakage detectors. The inspectors also reviewed operator rounds to verify Entergy was checking the telltale drains for leakage.
The inspectors reviewed the results of SFP neutron absorber testing conducted in 2014.
The inspectors verified that the test results did not show significant degradation of the boral neutron absorbers. The inspectors also reviewed Entergys heavy loads program document and the work package for a heavy lift that occurred over the fuel pool to verify Entergy minimized the risk of a load drop that could crush the spent fuel into a critical geometry.
b. Observations and Findings
The inspectors determined that Entergy was safely storing spent fuel in wet storage.
Spent fuel pool instrumentation, alarms, and leakage detection systems were being appropriately maintained. Entergys criticality controls for the wet storage of spent fuel were appropriate.
c. Conclusions
No findings of significance were identified.
2.5 Maintenance and Surveillance at Permanently Shutdown Reactors (IP 62801)
a. Inspection Scope
The inspectors conducted plant tours throughout the inspection period to observe the impact of work activities on site operations, and how worker safety was being maintained.
During these walk-downs, the inspectors evaluated the housekeeping and the material condition of structures and components that support decommissioning. The inspectors also assessed area radiological condition and radiological access controls, including posting and labeling.
The inspectors observed surveillances conducted on the service water pumps and on the electric fire pump. The inspectors also reviewed surveillance records on the station blackout diesel generator (SBODG) enclosure fire protection system. The inspectors observed post-maintenance testing on the A standby fuel pool cooling pump. The inspectors reviewed troubleshooting associated with degraded performance of the A standby fuel pool cooling heat exchanger, (CR-VTY- 2015-0984) including observing the state of the heat exchanger when it was opened for inspection and cleaning.
The inspectors also reviewed Entergys maintenance rule monitoring of the SBODG, buildings and structures, standby fuel pool cooling system and service water system to verify they were appropriately monitoring system performance.
b. Observations and Findings
The inspectors noted that throughout the inspection period housekeeping and plant material condition standards were being maintained. Changing radiological conditions were addressed in a prompt and timely manner by Entergy. Workers followed work plans, surveillance procedures and industrial safety protocols and were aware of job controls specified in work instructions. Entergy appropriately prioritized corrective maintenance on the remaining systems required for permanent cessation of operations.
The inspectors verified that when equipment issues occurred, Entergy staff implemented the appropriate troubleshooting procedures to identify and correct the equipment deficiency identified.
On May 4, while conducting a surveillance on the SBODG enclosure fire protection system, technicians inadvertently caused a lockout of the SBODG (CR-VTY-2015-0798).
The diesel generator was not running at the time. Entergy was performing the surveillance for the first time since it had been put in service in 2013, and the work order had not been updated to reflect that the work could affect the availability of the SBODG.
The inspectors determined that the technicians did not employ human performance error prevention tools that could have prevented the lockout. The lockout was reset promptly, so it did not impact the ability of the SBODG to provide station loads within two hours of a station blackout.
On May 27, operators switched standby fuel pool cooling trains from A to B and noticed that the A train required significantly more service water flow for cooling than the B train. The inspectors determined that Entergy performed appropriate testing on the A standby fuel pool cooling train to determine the cause of the degraded performance, verified the fuel pool cooling function was maintained, and performed timely corrective maintenance (heat exchanger cleaning) to restore the train to full cooling capacity.
The inspectors identified that service water bay freezing documented in condition report CR-VTY-2015-403 had not been recorded as a maintenance rule functional failure.
Although the service water system maintained its functionality while the bay was partially frozen, the A and B trains of the service water system experienced functional failures.
Entergy entered this into their corrective action program as CR-VTY-2015-1119 and updated the maintenance rule database to include the functional failures. Because these were the only functional failures on the A and B trains in the last three years, Entergy did not need to take further actions.
c. Conclusions
No findings of significance were identified.
2.6 Decommissioning Performance and Status Reviews at Permanently Shutdown Plants (IP 71801)
a. Inspection Scope
The inspectors observed site meetings which were used by Entergy to plan, review, assess, and schedule site activities. The inspectors reviewed portions of Entergys activities associated with the abandonment of systems and equipment not needed to support decommissioning operations.
The inspectors conducted document reviews, observations and interviews with plant personnel to verify:
- Activities were in accordance with license conditions and docketed commitments, as well as within the bounds of the docketed PSDAR;
- Appropriate plant staffing was maintained and management oversight of licensee and supplemental activities were performed;
- Pre-job briefs were conducted for facility operations including maintenance, surveillance, operations, and decommissioning activities;
- Plant material condition of structures, systems and components was maintained at a high level to ensure safe storage of spent fuel;
- The storage of combustibles and flammables were in accordance with plant procedures and the Fire Protection Plan for the subject location;
- Installed fire detection and suppression systems were effectively maintained, surveillances performed, and systems were capable of performing their intended function; and
- Site fire brigade training was effective.
The inspectors assessed operability and functionality of systems necessary for safe decommissioning through control room and plant walk-downs of the following systems:
radioactive effluent monitoring, SFP cooling (including level and temperature control), and radiation protection monitors and alarms. The inspectors also assessed the operability and functionality of equipment that was important to emergency preparedness or provided normal and standby electrical power. The inspectors reviewed ongoing in-plant work activities to ensure they were evaluated for risk and potential plant impacts. The inspectors verified that operations shift turnovers appropriately communicated pertinent plant status.
b. Observations and Findings
The inspectors determined that Entergy conducted decommissioning activities in accordance with the regulations and license requirements. The inspectors also verified that the activities to transition to a SAFSTOR condition were in accordance with Technical Specifications, the Updated Safety Analysis Report and the PSDAR.
During a walk-down of the control room on June 22, 2015, the inspectors informed Entergy of an ongoing G4-class geomagnetic disturbance. The operators contacted the independent system operator, who confirmed the disturbance, and stated that Entergy had not been notified because they are no longer a generating station. The geomagnetic disturbance had the potential to affect off-site power distribution. Entergy began performing the actions specified in procedures OPOP-PHEN-3127, Natural Phenomena, and MTAP-10084, Work Management Process. Entergy wrote CR-VTY-2015-1143 to evaluate the need for a change to site procedures to reflect the reduced impact of a loss of off-site power in the current defueled configuration.
c. Conclusions
No findings of significance were identified.
2.7 Operation of an Independent Spent Fuel Storage Installation (IP 60855)
a. Inspection Scope
The inspectors evaluated Entergys activities related to long-term operation and monitoring of their ISFSI, and verified that activities were being performed in accordance with the Certificate of Compliance (CoC), technical specifications, regulations, and licensee procedures. The NRCs program for overseeing the safe operation of an ISFSI is described in IMC 2690.
The inspectors performed tours of the ISFSI pad to assess the material condition of the pad and the loaded HI-STORM 100 over packs (HI-STORMs), and to verify that transient combustibles were not being stored in the vicinity of the HI-STORMs. The inspectors observed an operator performing the daily HI-STORM surveillances in accordance with TS requirements. The inspectors also confirmed that physical inventories (material control and accountability) were conducted annually and were maintained as required by the regulations.
The inspectors reviewed radiological records from periodic dry fuel storage pad surveys to confirm that radiation levels measured around the casks did not increase. The inspectors reviewed radiation protection procedures and radiation work permits (RWPs)associated with ISFSI operations.
The inspectors also reviewed the CAP, to ensure that issues were appropriately being entered, prioritized, and evaluated commensurate with their safety significance.
b. Observations and Findings
The inspectors determined that Entergy operated their ISFSI in accordance with the regulatory requirements and the CoC. There were no 10 CFR 72.48 screenings since the last inspection in April 2013.
c. Conclusions
No findings of significance were identified.
2.8 Decommissioning Emergency Preparedness Scenario Review and Exercise Evaluation (IP82401)
a. Inspection Scope
The inspectors performed an on-site inspection on May 12-15, 2015, of the biennial EP exercise to assess the adequacy of Entergys conduct of the exercise and its capability to assess emergency response organization (ERO) performance via a formal critique process. Entergy designed the exercise scenario and objectives to satisfy the requirement of 10 CFR 50, Appendix E, Section IV.F.2.j to provide the opportunity for their ERO to demonstrate proficiency in the key skills necessary to respond to a hostile action directed at the plant site.
Prior to the May 13, 2015, EP exercise, the NRC inspectors conducted an in-office review of the exercise objectives and scenario, which Entergy had submitted to the NRC, to determine if the exercise would test major elements of the Vermont Yankee Nuclear Power Station Emergency Plan.
The exercise evaluation consisted of observation and assessment of Entergys performance in the biennial full-participation exercise, the overall adequacy of Entergys emergency response facilities, and a review of other performance areas, which included:
the EROs recognition of abnormal plant conditions; command and control; intra-and inter-facility communications; prioritization of mitigating activities; interface with offsite agencies; and the overall implementation of the emergency plan and its implementing procedures. Following the exercise, the inspectors observed Entergys critique process to ensure the process identified and corrected weaknesses associated with the May 13, 2015, exercise.
b. Observations and Findings
The inspectors noted that the scenario developed by Entergy was plausible based on current plant conditions and that it included opportunities that allowed for the demonstration of proficiency in key skills necessary to implement the principle functional areas of emergency response.
The inspectors performed independent observations of emergency response organization performance in the simulator control room, emergency operations facility, alternate facility and joint information center. The inspectors noted areas for improvement associated with the conduct of the exercise, however, Entergys critique process identified those issues and entered them into the CAP (CR-VTY-2015-0857, CR-VTY-2015-0873, CR-VTY-2015-0878). Additionally, the inspectors determined the areas for improvement identified were minor in nature and would not impact Entergys ability to implement their emergency plan in the event of an actual radiological emergency.
c. Conclusions
No findings of significance were identified.
2.9 Occupational Radiation Exposure (IP 83750) and Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP 86750)
a. Inspection Scope
Inspectors reviewed radiation work permits, as low as reasonably achievable (ALARA)plans, procedures, and radiological survey data for the work activities to remove control rod drive mechanisms (CRDMs) to determine the effectiveness of site radiological programs and to verify radiation work activities were pre-planned effectively to limit worker exposure. Inspectors compared the dose results achieved with the intended dose established in the ALARA planning for the CRDM removal project to assess Entergys performance with respect to maintaining individual and collective radiation exposures ALARA and to ensure occupational dose is appropriately monitored. The inspectors evaluated the reasons for differences between the intended and actual work activity doses.
The inspectors observed radiological surveys being performed on transport containers for waste from the CDRM project and interviewed the radiation protection technicians (RPTs) performing the surveys. The inspectors reviewed the records of shipment packaging, surveying, labeling, marking, placarding, vehicle checks, and emergency instructions. The inspectors also reviewed the shipping papers inside the transport vehicle and interviewed the driver of the vehicle to ensure compliance with the applicable NRC and Department of Transportation regulations.
b. Observations and Findings
The inspectors determined that post-job reviews were conducted and identified problems were entered into the CAP. The inspectors determined that survey records were clear and complete and the RPTs were using appropriate instrumentation with current calibrations. Surveys were being performed as described in plant procedures. The inspectors verified that radioactive waste shipping paperwork was properly completed and Entergy personnel were knowledgeable of their duties and responsibilities.
Inspectors noted that all but two of the CRDMs were removed and shipped. The radioactive waste characterization of the CRDMs for shipment was performed by WMG Inc. and the CRDMs were shipped back to the manufacturer.
c. Conclusions
No findings of significance were identified.
3.0 Exit Meeting On July 9, 2015, the inspectors presented the inspection results to Mr. C. Wamser, Site Vice President, and other members of the Entergy staff who acknowledged the inspection results. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Vermont Yankee Personnel
- C. Wamser, Site Vice President
- M. Romeo, Decommissioning Plant Manager
- J. Boyle, Engineering and Technical Director
- P. Paradis, Decommissioning Director
- E. Harms, Senior Operations Manager
- M. McKenney, Emergency Preparedness Manager
- P. Ryan, Security Manager
- C. Chappell, Licensing and CA&A Manager
- J. Rogers, Design Engineering Manager
- M. Pletcher, Radiation Protection and Chemistry Manager
- J. Laughney, QA Manager
- A. Zander, Shift Manager
- T. Marstaller, Shift Manager
- N. Jennison, Shift Manager
- M. Prusak, Mechanical Maintenance Supervisor
- H. Breite, Mechanical Systems Engineer
- M. Flynn, Electrical Design Engineer
- J. Stasolla, I&C Systems Engineer
- J. Paradis, Operations Instructor
- C. Dissinger, Emergency Planner
- P. Jerz, Work Week Manager
- M. OBrien, Civil Design Engineer
- M. Ball, Mechnical Design Engineer
- R. Burns, Programs Engineer
- J. Card, Mechanical Systems Engineer
ITEMS OPENED, CLOSED, AND DISCUSSED
None
LIST OF DOCUMENTS REVIEWED
2.1 Organization, Management, and Cost Controls at Permanently Shutdown Reactors
(IP 36801)
Condition Reports
CR-VTY-2015-0181 CR-VTY-2015-0448 CR-VTY-2015-0486
CR-VTY-2015-0296 CR-VTY-2015-0449 CR-VTY-2015-0499
CR-VTY-2015-0447 CR-VTY-2015-0485
Miscellaneous
Certified Fuel Handler Training Program Description Task - Training Matrix, 3/27/15
Long Range Retraining Schedule, 3/27/15
Certified Fuel Handler Qualification Standard, 8/18/14
Refuel Activities JPM Records
WT-WTVTY-2013-230
Qualification/Exemption Approval Forms
2.2 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown
Reactors (IP 37801)
Procedures
PP 7023, Control of Heavy Loads Program Document, Revision 4
Work Orders
WO 379932, EC48595 - Safstor Modification - Use the Torus as a CST
WO 386198, Install Underwater Demin/Filter; EC 54243
Miscellaneous
B-191300, Sheet 19, Power Distribution & Motor Data, 480V MCC-7A, Revision 25
B-191300, Sheet 19A, Power Distribution & Motor Data, 480V MCC-7A, Revision 31
EC 48595, Use the Torus as the CST Safstor Modification
EC 55437, Route 2.5 Lines thru Doorway Vice Corebore
EC 54243, Use of Tri Nuclear Demin and Filter Units in SFP
2.3 Self-Assessment, Auditing, and Corrective Actions at Permanently Shutdown
Reactors (IP 40801)
Miscellaneous
2.4 Spent Fuel Pool Safety at Permanently Shutdown Reactors (IP 60801)
Procedures
V-EN-LI-102, Performance Improvement Program, Revision 24
Condition Reports
CR-VTY-2015-0742 CR-VTY-2015-0403
CR-VTY-2015-0612 CR-VTY-2015-599
Drawings
G-191173, Sheet 1, Flow Diagram Fuel Pool Cooling and Cleanup System, Revision 40
G-191173, Sheet 2, Flow Diagram Fuel Pool Cooling and Cleanup System, Revision 10
G-191219, Reactor Fuel Storage Pool Piping Plans and Sections, Revision 8
G-191691, Pool Liner and Gates - Sheet 4, Revision 9
20-3364, North and West Walls of Fuel Storage Pool, Revision 0
Miscellaneous
ARS 21002, CRP 9-4 Alarm Response Sheets, Revision 17
ARS 21009, FPC Alarm Response Sheets, Revision 3
EC 57228, Relocation of B.5.b Pump
2.5 Maintenance and Surveillance at Permanently Shutdown Reactors (IP 62801)
Procedures
AP 0211, Predictive Maintenance Process - Vibration Monitoring, Revision 15
OP 4181, Service Water/Alternate Cooling System Surveillance, Revision 82
AP 10088, Safstor Work Schedule Risk Management, Revision 2
OP 43106, Fuel Pool Level Functional/Calibrating, Revision 8
OP 4179, Standby Fuel Pool Cooling Surveillance, Revision 23
VYOPF 2179.01, SFPC Operating Data, February 5 - May 5, 2015
OP 2179, Standby Fuel Pool Cooling, Revision 18
V-EN-DC-150, Condition Monitoring of Maintenance Rule Structures, Revision 8
VY-RPT-13-00010, Maintenance Rule RFO 30 Summary Report, Revision 0
OPSP-SBO-10067-01, Monthly Station Blackout Diesel Generator Load Bank Test, Revision 6
EN-MA-125, Troubleshooting Control of Maintenance Activities, Revision 17
V-EN-DC-205, Maintenance Rule Monitoring, Revision 6
Condition Reports
CR-VTY-2015-0196 CR-VTY-2015-0799
CR-VTY-2015-0403 CR-VTY-2015-0801
CR-VTY-2015-0465 CR-VTY-2015-0984
CR-VTY-2015-0639 CR-VTY-2015-1119
CR-VTY-2015-0738 CR-VTY-2015-0984
Maintenance Rule Scoping Documents
Maintenance Rule Database
Work Orders
WO 52608119, P-19-2A Pump and Coupling Lubrications
WO 52593154, Service Water Valve and Pump Operability Testing
WO 52543075, OP4339 (1Y) Test Misc. Non-Vital Areas Fire Protection Zones
WO 00362648, Inspect and Replace Gaskets on Fuel Pool Gate-1
WO 02-001440, Replace Fuel Pool Gate Gaskets
WO 00362650, Inspect and Replace if Required Gaskets on Fuel Pool Gate-2
WO 52216892, V19-220; Perform MC2 Testing Per OP 5217
WO 52327811, V19-220; Routine Inspection of Limitorque Operator per OP 5220
WO 52216893, Perform MC2 Testing per OP 5217
WO 52327812, V19-221; Routine Inspection of Limitorque Operator OP 5220
WO 52513387, V19-224 IST Closure Test; OPST-4028-02 (RFO)
WO 52199503, Check Valve Disassembly & Inspection; V19-224
WO 05000113, Check Valve Inspection for Swing Type Check Valves (Standard PM)
WO 05-001272, Check Valve Indication for Swing Type Check Valves (Standard PM)
WO 00321103, Check Valve Indication for Swing Type Check Valves (Standard PM)
WO 00321111, LT-19-63B; Perform Required EQ Maintenance
WO 52416810, Replace Cover O-Ring after Calibration, EQ Maintenance
WO 52416811, Replace Cover O-Ring after Calibration, EQ Maintenance
WO 52416812, Replace Cover O-Ring after Calibration, EQ Maintenance
WO 52115409, Inspect 1M Contactor in 71UPP to Verify no damage was caused
Miscellaneous
BVY 15-022, Notification of Changes to Regulatory Commitments, updated March 27, 2015
VYOPF 4105.02, Eighteen Month Fire Pump Operational Performance and Capacity Check
and Diesel Fire Pump Alarm/Shutdown Test, completed 6/17/15
2.6 Operation of an Independent Spent Fuel Storage Installation (IP 60855)
Procedures
V-EN-NF-200, Special Nuclear Material Control, Revision 12
V-EN-DC-215, Fuel Selection for Holtec Dry Cask Storage, Revision 6
OP 0150, Conduct of Operations and Operator Rounds, Revision 195
Condition Reports
CR-VTY-2013-0604 CR-VTY-2014-2665
CR-VTY-2013-0787 CR-VTY-2014-3114
CR-VTY-2013-1093 CR-VTY-2014-3563
CR-VTY-2013-4002 CR-VTY-2014-4039
CR-VTY-2013-4840 CR-VTY-2014-4077
CR-VTY-2013-4841 CR-VTY-2014-4089
CR-VTY-2013-5744 CR-VTY-2015-0266
CR-VTY-2014-0641 CR-VTY-2015-0275
CR-VTY-2014-2234 CR-VTY-2015-0276
CR-VTY-2014-2406 CR-VTY-2015-0280
Miscellaneous
CFR 72.212 Report, Docket 72-0059, HI-STORM 100 System, Revision 5
2.7 Decommissioning Performance and Status Reviews at Permanently Shutdown
Plants (IP 71801)
Procedures
OPOP-PHEN-3127, Natural Phenomena, Revision 19
Condition Reports
2.8 Decommissioning Emergency Preparedness Scenario Review and Exercise
Evaluation (82401)
Procedures
AP 3125, Emergency Plan Classification and Action Level Scheme, Revision 25
EPOP-AFA-10083, Alternate Facility Activation, Revision 0
EPOP-CR-3540, Control Room Actions during an Emergency, Revision 4
EPOP-MED-3508, On-Site Medical Emergency, Revision 0
EPOP-OSC-3544, Operation of the Operations Support Center, Revision 1
EPOP-TSC-3542, Operation of the Technical Support Center, Revision 3
OP 3020, Fire Emergency Response Procedure, Revision 59
OPOP-SECU-3132, Operations Department Response to Security Events, Rev 4
V-EN-EP-307, Hostile Action Based Drills & Exercises, Revision 2
Condition Reports
CR-VTY-2015-0856 CR-VTY-2015-0871
CR-VTY-2015-0857 CR-VTY-2015-0873
CR-VTY-2015-0858 CR-VTY-2015-0875
CR-VTY-2015-0859 CR-VTY-2015-0876
CR-VTY-2015-0864 CR-VTY-2015-0877
CR-VTY-2015-0866 CR-VTY-2015-0878
CR-VTY-2015-0867 CR-VTY-2015-0880
Miscellaneous
Emergency Plan Full Participation Exercise Scenario Package, dated March 24, 2015
Vermont Yankee Emergency Plan, Revision 51
Vermont Yankee Nuclear Power Station Emergency Action Level Technical Basis, Revision 15
2.9 Occupational Radiation Exposure (IP 83750) and Solid Radioactive Waste
Management and Transportation of Radioactive Materials (IP 86750)
Procedures
EN-RW-102, Radioactive Shipping Procedure, Revision 12
ERP-105-DP, Radiological Work Permits, Revision 0
EN-RP-110-DP, ALARA Program, Revision 0
EN-RP-110-05-DP, Decommissioning Plant ALARA Planning and Controls, Revision 0
Miscellaneous
ALARA Plan # 150019
Alternate Straight Bill of Lading, 2015-18
Radioactive Material Manifest, 2015-18
Survey Logbook: #15-258, CRD Box # 1347-S; #15-259, CRD Box # 1350-S; #15-260, CRD
Box # 1341-S
WMG, Package Characterization Report, 2015-18
WMG, DOT Classification Summary, 2015-18
Procedures-Completed Surveillance Procedures
EN-RW-102, Attachment 9.1, Radioactive Shipment Document Checklist, 2015-18
EN-RW-102, Attachment 9.2, Shipping Checklist - LSA/SCO/Exclusive Use and Domestic,
2015-18
EN-RW-102, Attachment 9.13, Radioactive Material Shipment Truck Survey Form, 2015-18
EN-RW-102, Attachment 9.14, Instructions for Maintenance Exclusive Use Shipment Controls,
2015-18
LIST OF ACRONYMS USED
ADAMS Agencywide Document Access and Management System
ALARA As Low As Reasonably Achievable
CAP Corrective Action Program
CFR Code of Federal Regulations
CoC Certificate of Compliance
CR Condition Report
CRDM Control Rod Drive Mechanism
Entergy Entergy Nuclear Operations, Inc.
ERO Emergency Response Organization
FSAR Final Safety Analysis Report
IMC Inspection Manual Chapter
IP Inspection Procedure
ISFSI Independent Spent Fuel Storage Installation
NRC U.S. Nuclear Regulatory Commission
PSDAR Post Shutdown Decommissioning Activities Report
RPT Radiation Protection Technician
RWP Radiation Work Permit
SAFSTOR Safe Storage of Spent Fuel
SBODG Station Blackout Diesel Generator
SFP Spent Fuel Pool
TS Technical Specification
Attachment