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| issue date = 10/22/2015
| issue date = 10/22/2015
| title = IR 05000271/2015009 on 7/20-23/2015, 9/14-17/2015 and 9/30/2015, Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Vernon, VT
| title = IR 05000271/2015009 on 7/20-23/2015, 9/14-17/2015 and 9/30/2015, Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Vernon, VT
| author name = Powell R J
| author name = Powell R
| author affiliation = NRC/RGN-I/DNMS/NMSB3
| author affiliation = NRC/RGN-I/DNMS/NMSB3
| addressee name = Wamser C
| addressee name = Wamser C
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:October 22, 2015 Docket No.
{{#Wiki_filter:October 22, 2015


05000 271License No.
==SUBJECT:==
NRC INSPECTION REPORT NO. 05000271/2015009, ENTERGY NUCLEAR OPERATIONS, INC., VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VERMONT


DPR-28 Mr. Christopher Wamser Site Vice President Entergy Nuclear Operations, Inc.
==Dear Mr. Wamser:==
On September 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). On-site inspections were performed on July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy Nuclear Operations, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Mike Romeo, Plant Manager, and other members of the VY staff on October 5, 2015, and are described in the enclosed report. No findings of safety significance were identified.


Vermont Yankee Nuclear Power Station
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure(s), and your response, 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.


Vernon, VT 05354
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).


SUBJECT: NRC INSPECTION REPORT NO. 05000271/201500 9, ENTERGY NUCLEAR OPERATIONS, INC., VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VERMONT
UNITED STATES NUCLEAR REGULATORY COMMISSION


==Dear Mr. Wamser:==
==REGION I==
On September 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). On-site inspections were performed on July 20-23, and September 14
2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 No reply to this letter is required. Please contact Steve Hammann, at 610-337-5399, if you have any questions regarding this matter.
-17, 2015. In
-office reviews of information supplied by Entergy Nuclear Operations, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Mike Romeo, Plant Manager, and other members of the VY staff on October 5, 2015, and are described in the enclosed report. No findings of safety significance were identified.


In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure(s), and your response, 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
Sincerely,
-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.
/RA/  


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
Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety
-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).


UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406
Enclosure:
-2713 No reply to this letter is required. Please contact Steve Hammann, at 610
Inspection Report 05000271/2015009
-337-5399, if you have any questions regarding this matter.


Sincerely,
cc w/encl:
/RA/ Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety Enclosure:
Inspection Report 05000 271/201500 9 cc w/encl:
Distribution via ListServ
Distribution via ListServ


Line 53: Line 49:
Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc.


Vermont Yankee Nuclear Power Station NRC Inspection Report No. 05000 271/201500 9  An announced quarterly inspection was completed at Vermont Yankee Nuclear Power Station (VY) on September 30, 2015. O n-site inspection s were conducted on July 20-23 , and September 14-17 , 2015. In-office reviews of information supplied by Entergy Nuclear Operations, Inc. (Entergy) were also performed during the inspection period. The inspection included a review of operations
Vermont Yankee Nuclear Power Station NRC Inspection Report No. 05000271/2015009
, management oversight, site radiological programs, Independent Spent Fuel Storage Installation (ISFSI), and decommissioning performance.


T he inspection consisted of observations by the inspector s, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The 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."
An announced quarterly inspection was completed at Vermont Yankee Nuclear Power Station (VY) on September 30, 2015. On-site inspections were conducted on July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy Nuclear Operations, Inc. (Entergy) were also performed during the inspection period. The inspection included a review of operations, management oversight, site radiological programs,
Independent Spent Fuel Storage Installation (ISFSI), and decommissioning performance. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The 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."


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


3 Inspection Report No. 05000271/2015009 C:\Users\ajk\Documents\LDPR-28.201500910222015.docx
Inspection Report No. 05000271/2015009 C:\\Users\\ajk\\Documents\\LDPR-28.201500910222015.docx


=REPORT DETAILS=
=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 Code of Federal Regulations (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.
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 Code of Federal Regulations (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
2.0 Post Operation Transition Phase Performance and Status Review


====a. Inspection Scope====
====a. Inspection Scope====
(Inspection Procedures (IPs) 37801, 608 5 6 , 83750, 84750)   The inspector s performed on
(Inspection Procedures (IPs) 37801, 60856, 83750, 84750)  
-site inspection s the week s of Ju ly 2 0-2 3 , and September 14-17, 2015. In-office reviews of information supplied by Entergy were also performed during the inspection period.


The inspection consisted of observations by the inspector s, interviews with Entergy personnel, a review of procedures and records, and plant walk
The inspectors performed on-site inspections the weeks of July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy were also performed during the inspection period. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.
-downs.


The inspector s observed chemistry technicians collect, prepare, and analyze spent fuel pool water samples; radiation protection (RP) technicians performing routine radiological inspections; and RP technicians performing source checks of instrumentation. The inspector s also toured the calibration lab and observed a demonstration of instrument calibration.
The inspectors observed chemistry technicians collect, prepare, and analyze spent fuel pool water samples; radiation protection (RP) technicians performing routine radiological inspections; and RP technicians performing source checks of instrumentation. The inspectors also toured the calibration lab and observed a demonstration of instrument calibration. The inspectors reviewed radiation work permits (RWPs), As Low As Reasonably Achievable (ALARA) committee meeting minutes, ALARA reports, and procedures associated with occupational exposure.


The inspector s reviewed radiation work permits (RWPs), As Low As Reasonably Achievable (ALARA) committee meeting minutes, ALARA reports, and procedures associated with occupational exposure.
The inspectors performed a walk-down of groundwater monitoring wells and site effluent monitoring points, observed RP technicians collect and prepare environmental air samples, and toured the Sample Preparation Facility. The inspectors reviewed documentation associated with radioactive effluent control and site radiological environmental monitoring program (REMP) to determine the effectiveness of site radiological programs. The inspectors reviewed procedures, diagrams of effluent monitoring systems, annual REMP report, annual radioactive effluent report, and the Off-Site Dose Calculation Manual.


The inspector s performed a walk
The inspectors reviewed the modifications to abandon the condensate storage tank (CST) and instead use the Torus for primary water storage during the SAFSTOR phase of decommissioning. The inspectors performed a walk-down of the modification, interviewed personnel, and observed work in-progress. The inspectors reviewed engineering change (EC) packages, condition reports, and plant drawings to determine if the Torus as CST project would fulfill its function as specified in the Final Safety Analysis Inspection Report No. 05000271/2015009 C:\\Users\\ajk\\Documents\\LDPR-28.201500910222015.docx Report (FSAR), Technical Specifications, and plant procedures. The inspectors also reviewed post implementation functional test results to determine if the modification results were acceptable.
-down of groundwater monitoring wells and site effluent monitoring points, observed RP technicians collect and prepare environmental air samples, and toured the Sample Preparation Facility. The inspector s reviewed documentation associated with radioactive effluent control and site radiological environmental monitoring program (REMP) to determine the effectiveness of site radiological programs. The inspector s reviewed procedures, diagrams of effluent monitoring systems, annual REMP report, annual radioactive effluent report, and the Off
-Site Dose Calculation Manual.


The inspector s reviewed the modifications to abandon the condensate storage tank (CST) and instead use the Torus for primary water storage during the SAFSTOR phase of decommissioning.
The inspectors performed an in-office review of ISFSI pad design documentation to determine if the storage pad would adequately support both static and dynamic loads, as required by 10 CFR 72.212(b)(5)(ii). The inspectors reviewed the assumptions the licensee used in the seismic and liquefaction analyses for the storage pad. The inspectors reviewed the licensees conclusions about the acceptability of the storage pads design with respect to the sites hydrology, geology and seismology. The inspectors also determined if the various design loads were in accordance with Vermont Yankee FSAR.


The inspector s performed a walk
====b. Observations and Findings====
-down of the modification , interviewed personnel, and observed work in
The inspectors determined that survey records were clear and complete and RP staff and maintenance supervision effectively controlled work activities. The inspectors determined dose assessments were being performed in accordance with plant procedures and that ALARA dose reports indicate that Entergy is currently meeting their occupational dose projections for the year.
-progress. The inspector s reviewed engineering change (EC) packages, condition reports , and plant drawings to determine if the Torus as CST project would fulfill its function as specified in the Final Safety Analysis 4 Inspection Report No. 05000271/2015009 C:\Users\ajk\Documents\LDPR-28.201500910222015.docx Report (FSAR), Technical Specifications, and plant procedures.


The inspector s also reviewed post implementation functional test results to determine if the modification results were acceptable.
The inspectors verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix I. The inspectors also determined that waste treatment systems were maintained and operated in accordance with site procedures. The inspectors verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations.


The inspector s performed an in
The inspectors verified the Torus as CST modification was completed and the Torus was placed into service as the source of primary water storage. The inspectors also verified that the engineering changes (ECs) were performed in accordance with site procedures and safety reviews had been performed adequately. The inspectors determined Entergy effectively evaluated the post implementation functional test results of the modification.
-office review of ISFSI pad design documentation to determine if the storage pad would adequately support both static and dynamic loads, as required by 10 CFR 72.212(b)(5)(ii). The inspector s reviewed the assumptions the licensee used in the seismic and liquefaction analyses for the storage pad. The inspector s reviewed the licensee's conclusions about the acceptability of the storage pads design with respect to the site's hydrology, geology and seismology.


The inspector s also determined if the various design loads were in accordance with Vermont Yankee FSAR.
The inspectors noted the construction of the ISFSI pad expansion is tentatively scheduled to start in 2016. The inspectors verified the second pad will be constructed directly west of the existing pad and will expand the Entergy dry cask storage capacity by allowing an additional 25 Holtec HI-STORM 100S, Version B (218) overpacks to be stored.


====b. Observations and Findings====
====c. Conclusions====
The inspector s determined that survey records were clear and complete and RP staff and maintenance supervision effectively controlled work activities. The inspector s determined dose assessments were being performed in accordance with plant procedures and that ALARA dose reports indicate that Entergy is currently meeting their occupational dose projections for the year.
Based on the results of this inspection, no findings of safety significance were identified.


The inspector s verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix I. The inspector s also determined that waste treatment systems were maintained and operated in accordance with site procedures.
Inspection Report No. 05000271/2015009 C:\\Users\\ajk\\Documents\\LDPR-28.201500910222015.docx 3.0


The inspector s verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations.
===Exit Meeting Summary===
On October 5, 2015, the inspectors presented the inspection results, via teleconference, to Mike Romeo, Plant Manager, and other members of Entergys staff. The inspectors confirmed that proprietary information was not removed from the site.


The inspector s verified the Torus as CST modification was completed and the Torus was placed into service as the source of primary water storage. The inspectors also verified that the engineering changes (ECs) were performed in accordance with site procedures and safety reviews had been performed adequately. The inspector s determined Entergy effectively evaluated the post implementation functional test results of the modification.
PARTIAL LIST OF PERSONS CONTACTED


The inspector s noted the construction of the ISFSI pad expansion is tentatively scheduled to start in 2016. The inspectors verified the second pad will be constructed directly west of the existing pad and will expand the Entergy dry cask storage capacity by allowing an additional 25 Holtec HI
Licensee M. Ball, Mechnical Design Engineer J. Card, Mechanical Systems Engineer C. Chappell, Licensing and CA&A Manager S. Christmas, RP Technician P. Jerz, Work Week Manager J. Meyer, Licensing M. Morgan, RP Supervisor M. Odman, Sr. Chemistry Technician M. Pletcher, Radiation Protection and Chemistry Manager G. Roediger, Sr. Chemistry Technician J. Rogers, Design Engineering Manager M. Romeo, Decommissioning Plant Manager K. Whippie, Chemistry Supervisor A. Zander, Shift Manager
-STORM 100S, Version B (218) overpacks to be stored.


====c. Conclusions====
ITEMS OPEN, CLOSED, AND DISCUSSED
Based on the results of this inspection, no findings of safety significance were identified.


Inspection Report No. 05000271/2015009 C:\Users\ajk\Documents\LDPR-28.201500910222015.docx 3.0
None


=====Exit Meeting Summary=====
LIST OF  
On October 5, 2015 , the inspector s presented the inspection results, via teleconference, to Mike Romeo, Plant Manager, and other members of Entergy's staff. The inspector s confirmed that proprietary information was not removed from the site
.
PARTIAL LIST OF PERSONS CONTACTED Licensee M. Ball, Mechnical Design Engineer J. Card, Mechanical Systems Engineer C. Chappell, Licensing and CA&A Manager S. Christmas, RP Technician P. Jerz, Work Week Manager J. Meyer, Licensing M. Morgan, RP Supervisor M. Odman, Sr. Chemistry Technician M. Pletcher, Radiation Protection and Chemistry Manager G. Roediger, Sr. Chemistry Technician J. Rogers, Design Engineering Manager M. Romeo, Decommissioning Plant Manager K. Whippie, Chemistry Supervisor A. Zander, Shift Manager ITEMS OPEN, CLOSED, AND DISCUSSED None  LIST OF  


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=
Line 124: Line 115:
Audits and Reports
Audits and Reports
2014 Annual Radiological Environmental Operating Report
2014 Annual Radiological Environmental Operating Report
Chemistry Audit, 2013, Standardized Audit Template, Checklist QA
Chemistry Audit, 2013, Standardized Audit Template, Checklist QA-2-6-2013-VY-1
-2-6-2013-VY-1 Radioactive Effluent Release Report for 2014
Radioactive Effluent Release Report for 2014
Teledyne Brown Engineering, Inc., Report of Analysis/Certificate of Conformance, PO#
Teledyne Brown Engineering, Inc., Report of Analysis/Certificate of Conformance, PO#
10147241, 4/15/2015
10147241, 4/15/2015
VT Y Daily ALARA
VTY Daily ALARA Report, September 17, 2015
Report, September 17, 2015
VTY Daily ALARA Report, July 21, 2015
VTY Daily ALARA Report, July 21 , 2015 WMG 13-150-RE-193, Rev. 0, Vermont Yankee Dose Rate Assessment Using
WMG 13-150-RE-193, Rev. 0, Vermont Yankee Dose Rate Assessment Using Monte Carlo
Monte Carlo
Methodology
Methodology
Calculations
Calculations
VYC-3176, Development of Response Spectra Consistent Time Histories for ISFI Expansion
VYC-3176, Development of Response Spectra Consistent Time Histories for ISFI Expansion
Concrete Storage Pad , Rev.1. VYC-3177, Development of Strain Dependent Soil Properties for ISFSI Expansion Concrete
Concrete Storage Pad, Rev.1.
Storage P ad , Rev.1. VYC-3178, Soil
VYC-3177, Development of Strain Dependent Soil Properties for ISFSI Expansion Concrete
-Structure Interaction Analysis and Cask/Stability Sliding of ISFSI Expansion
Storage Pad, Rev.1.
Concrete Storage Pad , Rev.0   VYC-3179, Liquefaction Potential for ISFSI Expansion Concrete Storage Pad
VYC-3178, Soil-Structure Interaction Analysis and Cask/Stability Sliding of ISFSI Expansion
, Rev.1 VYC-3181, Structural concrete design for ISFSI Expansion Concrete Storage Pad , Rev. 0
Concrete Storage Pad, Rev.0
Attachment
VYC-3179, Liquefaction Potential for ISFSI Expansion Concrete Storage Pad, Rev.1
Drawings Drawing No
VYC-3181, Structural concrete design for ISFSI Expansion Concrete Storage Pad, Rev. 0
s. G-191148, G-191169, G-191173, G-191175, G-191176 SH.3
 
Drawings
Drawing Nos. G-191148, G-191169, G-191173, G-191175, G-191176 SH.3
Evaluations
Evaluations
EC No. 48595, Rev. 0
EC No. 48595, Rev. 0
Line 149: Line 141:
EN-RP-203, Dose Assessment, Rev. 6
EN-RP-203, Dose Assessment, Rev. 6
EN-RP-206, Dosimeter of Legal Record Quality Assurance, Rev. 5
EN-RP-206, Dosimeter of Legal Record Quality Assurance, Rev. 5
EN-RP-301, Radiation Protection Instrument Control, Rev. 7 EN-RP-302, Operation of Radiation Protection Instrumentation, Rev. 2   EN-RP-303, Source Checking of Radiation Protection Instrumentation, Rev. 4 EN-RP-303-01, Automated Contamination Monitor Performance Testing, Rev. 0 EN-RW-102, Radioactive Shipping Procedure, Rev. 11
EN-RP-301, Radiation Protection Instrument Control, Rev. 7
FO-OP-025, Dewatering Procedure for EnergySolutions
EN-RP-302, Operation of Radiation Protection Instrumentation, Rev. 2
Inch Diameter Disposable Pressure
EN-RP-303, Source Checking of Radiation Protection Instrumentation, Rev. 4
Vessels, Rev. 6 OP 0631, Appendix B, Alpha and Gamma Determinations, Rev. 28
EN-RP-303-01, Automated Contamination Monitor Performance Testing, Rev. 0
EN-RW-102, Radioactive Shipping Procedure, Rev. 11
FO-OP-025, Dewatering Procedure for EnergySolutions 24 Inch Diameter Disposable Pressure
Vessels, Rev. 6
OP 0631, Appendix B, Alpha and Gamma Determinations, Rev. 28
OP 0631, Appendix C, Tritium Measurement, Rev. 28
OP 0631, Appendix C, Tritium Measurement, Rev. 28
OP 0634, Operation of the Dionex Ion Chromatograph, Rev. 20
OP 0634, Operation of the Dionex Ion Chromatograph, Rev. 20
OP 4605, Environmental Radiation Sampling and Analysis, Rev. 47 Procedures
OP 4605, Environmental Radiation Sampling and Analysis, Rev. 47
-Completed Surveillance Procedures
Procedures-Completed Surveillance Procedures
EN-DC-117 R007, Attachment 9.6, ECT
EN-DC-117 R007, Attachment 9.6, ECT-48595-01, Torus as CST Post Implementation
-48595-01, Torus as CST Post Implementation
Functional Test
Functional Test
EN-RP-203, Attachment 9.3, Dosimetry Investigation Report, 8/18/15
EN-RP-203, Attachment 9.3, Dosimetry Investigation Report, 8/18/15
Miscellaneous
Miscellaneous
ALARA Committee Meeting Minutes, 4/2/15
ALARA Committee Meeting Minutes, 4/2/15
Decommissioning ALARA Planning Data and ALARA Plan, Rev. 0
Decommissioning ALARA Planning Data and ALARA Plan, Rev. 0  
  -Torus as CST mod  
-Torus as CST mod - EC 48595  
- EC 48595  -Transfer and Processing of RWCU resin from CUPS to Cask
  -Transfer and Processing of RWCU resin from CUPS to Cask
Gaseous Effluent Filter Sample and Analysis, 6/29/15
Gaseous Effluent Filter Sample and Analysis, 6/29/15
GEL Laboratories LLC, Analytical Results for samples received May 29, 2015 and June 4, 2015
GEL Laboratories LLC, Analytical Results for samples received May 29, 2015 and June 4, 2015
Main Stack Grab Sample and Analysis, 6/15/15
Main Stack Grab Sample and Analysis, 6/15/15
Plan of the Day Meeting/OPS Focus Agenda, 7/21/2015
Plan of the Day Meeting/OPS Focus Agenda, 7/21/2015
RSCS, A Summary of Sr
RSCS, A Summary of Sr-90 Levels in the Environment, April 15, 2015
-90 Levels in the Environment, April 15, 2015
RWP, 20150621, Revs. 00,01,02, Transfer and Processing of RWCU Resin from CUPS to Cask
RWP, 20150621, Revs. 00,01,02, Transfer and Processing of RWCU Resin from CUPS to Cask
Stack Tritium Analysis, 6/29/15
Stack Tritium Analysis, 6/29/15
Line 177: Line 171:
Vermont Yankee Offsite Dose Calculation Manual (ODCM) Revisions for Decommissioning,
Vermont Yankee Offsite Dose Calculation Manual (ODCM) Revisions for Decommissioning,
prepared by RSCS, July 7, 2015
prepared by RSCS, July 7, 2015
Attachment
 
LIST OF ACRONYMS USED
LIST OF ACRONYMS USED
ADAMS Agencywide Document and Access Management System
ADAMS
ALARA As Low As Reasonably Achievable
Agencywide Document and Access Management System
CFR   Code of Federal Regulations
ALARA
CST   Condensate
As Low As Reasonably Achievable
Storage Tank EC   Engineering Change
CFR  
Entergy   Entergy Nuclear Operations, Inc.
 
FSAR   Final Safety Analysis Report IMC   Inspection Manual Chapter
Code of Federal Regulations
IP   Inspection Procedure
CST  
ISFSI   Independent Spent Fuel Storage Installation
 
NRC   U.S. Nuclear Regulatory Commission
Condensate Storage Tank
REMP   Radiological
EC  
Environmental
 
Monitoring
Engineering Change
Program RWP   Radiation Work Permit
Entergy
VY   Vermont Yankee Nuclear Power Station
Entergy Nuclear Operations, Inc.
FSAR
Final Safety Analysis Report
IMC  
 
Inspection Manual Chapter
IP  
 
Inspection Procedure
ISFSI
Independent Spent Fuel Storage Installation
NRC  
 
U.S. Nuclear Regulatory Commission
REMP
Radiological Environmental Monitoring Program
RWP
Radiation Work Permit
VY  
 
Vermont Yankee Nuclear Power Station
}}
}}

Latest revision as of 06:52, 10 January 2025

IR 05000271/2015009 on 7/20-23/2015, 9/14-17/2015 and 9/30/2015, Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station, Vernon, VT
ML15299A041
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 10/22/2015
From: Racquel Powell
NRC/RGN-I/DNMS/NMSB3
To: Wamser C
Entergy Nuclear Operations
References
IR 2015009
Download: ML15299A041 (11)
v • d • e


Text

October 22, 2015

SUBJECT:

NRC INSPECTION REPORT NO. 05000271/2015009, ENTERGY NUCLEAR OPERATIONS, INC., VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VERMONT

Dear Mr. Wamser:

On September 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). On-site inspections were performed on July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy Nuclear Operations, Inc. were also performed during the inspection period. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Mike Romeo, Plant Manager, and other members of the VY staff on October 5, 2015, and are described in the enclosed report. No findings of safety significance were identified.

In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its enclosure(s), and your response, 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).

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 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/

Raymond Powell, Chief Decommissioning and Technical Support Branch Division of Nuclear Materials Safety

Enclosure:

Inspection Report 05000271/2015009

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EXECUTIVE SUMMARY

Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station NRC Inspection Report No. 05000271/2015009

An announced quarterly inspection was completed at Vermont Yankee Nuclear Power Station (VY) on September 30, 2015. On-site inspections were conducted on July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy Nuclear Operations, Inc. (Entergy) were also performed during the inspection period. The inspection included a review of operations, management oversight, site radiological programs,

Independent Spent Fuel Storage Installation (ISFSI), and decommissioning performance. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs. The 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."

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

Inspection Report No. 05000271/2015009 C:\\Users\\ajk\\Documents\\LDPR-28.201500910222015.docx

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 Code of Federal Regulations (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

a. Inspection Scope

(Inspection Procedures (IPs) 37801, 60856, 83750, 84750)

The inspectors performed on-site inspections the weeks of July 20-23, and September 14-17, 2015. In-office reviews of information supplied by Entergy were also performed during the inspection period. The inspection consisted of observations by the inspectors, interviews with Entergy personnel, a review of procedures and records, and plant walk-downs.

The inspectors observed chemistry technicians collect, prepare, and analyze spent fuel pool water samples; radiation protection (RP) technicians performing routine radiological inspections; and RP technicians performing source checks of instrumentation. The inspectors also toured the calibration lab and observed a demonstration of instrument calibration. The inspectors reviewed radiation work permits (RWPs), As Low As Reasonably Achievable (ALARA) committee meeting minutes, ALARA reports, and procedures associated with occupational exposure.

The inspectors performed a walk-down of groundwater monitoring wells and site effluent monitoring points, observed RP technicians collect and prepare environmental air samples, and toured the Sample Preparation Facility. The inspectors reviewed documentation associated with radioactive effluent control and site radiological environmental monitoring program (REMP) to determine the effectiveness of site radiological programs. The inspectors reviewed procedures, diagrams of effluent monitoring systems, annual REMP report, annual radioactive effluent report, and the Off-Site Dose Calculation Manual.

The inspectors reviewed the modifications to abandon the condensate storage tank (CST) and instead use the Torus for primary water storage during the SAFSTOR phase of decommissioning. The inspectors performed a walk-down of the modification, interviewed personnel, and observed work in-progress. The inspectors reviewed engineering change (EC) packages, condition reports, and plant drawings to determine if the Torus as CST project would fulfill its function as specified in the Final Safety Analysis Inspection Report No. 05000271/2015009 C:\\Users\\ajk\\Documents\\LDPR-28.201500910222015.docx Report (FSAR), Technical Specifications, and plant procedures. The inspectors also reviewed post implementation functional test results to determine if the modification results were acceptable.

The inspectors performed an in-office review of ISFSI pad design documentation to determine if the storage pad would adequately support both static and dynamic loads, as required by 10 CFR 72.212(b)(5)(ii). The inspectors reviewed the assumptions the licensee used in the seismic and liquefaction analyses for the storage pad. The inspectors reviewed the licensees conclusions about the acceptability of the storage pads design with respect to the sites hydrology, geology and seismology. The inspectors also determined if the various design loads were in accordance with Vermont Yankee FSAR.

b. Observations and Findings

The inspectors determined that survey records were clear and complete and RP staff and maintenance supervision effectively controlled work activities. The inspectors determined dose assessments were being performed in accordance with plant procedures and that ALARA dose reports indicate that Entergy is currently meeting their occupational dose projections for the year.

The inspectors verified that the annual radiological effluent and the annual REMP reports demonstrated that calculated doses were below regulatory dose criteria of 10 CFR 50, Appendix I. The inspectors also determined that waste treatment systems were maintained and operated in accordance with site procedures. The inspectors verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations.

The inspectors verified the Torus as CST modification was completed and the Torus was placed into service as the source of primary water storage. The inspectors also verified that the engineering changes (ECs) were performed in accordance with site procedures and safety reviews had been performed adequately. The inspectors determined Entergy effectively evaluated the post implementation functional test results of the modification.

The inspectors noted the construction of the ISFSI pad expansion is tentatively scheduled to start in 2016. The inspectors verified the second pad will be constructed directly west of the existing pad and will expand the Entergy dry cask storage capacity by allowing an additional 25 Holtec HI-STORM 100S, Version B (218) overpacks to be stored.

c. Conclusions

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

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Exit Meeting Summary

On October 5, 2015, the inspectors presented the inspection results, via teleconference, to Mike Romeo, Plant Manager, and other members of Entergys staff. The inspectors confirmed that proprietary information was not removed from the site.

PARTIAL LIST OF PERSONS CONTACTED

Licensee M. Ball, Mechnical Design Engineer J. Card, Mechanical Systems Engineer C. Chappell, Licensing and CA&A Manager S. Christmas, RP Technician P. Jerz, Work Week Manager J. Meyer, Licensing M. Morgan, RP Supervisor M. Odman, Sr. Chemistry Technician M. Pletcher, Radiation Protection and Chemistry Manager G. Roediger, Sr. Chemistry Technician J. Rogers, Design Engineering Manager M. Romeo, Decommissioning Plant Manager K. Whippie, Chemistry Supervisor A. Zander, Shift Manager

ITEMS OPEN, CLOSED, AND DISCUSSED

None

LIST OF

DOCUMENTS REVIEWED

Condition Reports

CR-VTY-2015-00973, 01072, 01246, 01294, 01528

Audits and Reports

2014 Annual Radiological Environmental Operating Report

Chemistry Audit, 2013, Standardized Audit Template, Checklist QA-2-6-2013-VY-1

Radioactive Effluent Release Report for 2014

Teledyne Brown Engineering, Inc., Report of Analysis/Certificate of Conformance, PO#

10147241, 4/15/2015

VTY Daily ALARA Report, September 17, 2015

VTY Daily ALARA Report, July 21, 2015

WMG 13-150-RE-193, Rev. 0, Vermont Yankee Dose Rate Assessment Using Monte Carlo

Methodology

Calculations

VYC-3176, Development of Response Spectra Consistent Time Histories for ISFI Expansion

Concrete Storage Pad, Rev.1.

VYC-3177, Development of Strain Dependent Soil Properties for ISFSI Expansion Concrete

Storage Pad, Rev.1.

VYC-3178, Soil-Structure Interaction Analysis and Cask/Stability Sliding of ISFSI Expansion

Concrete Storage Pad, Rev.0

VYC-3179, Liquefaction Potential for ISFSI Expansion Concrete Storage Pad, Rev.1

VYC-3181, Structural concrete design for ISFSI Expansion Concrete Storage Pad, Rev. 0

Drawings

Drawing Nos. G-191148, G-191169, G-191173, G-191175, G-191176 SH.3

Evaluations

EC No. 48595, Rev. 0

Procedures

DP 4580, Operation of Whole Body Counting System, Rev. 8

EN-RP-203, Dose Assessment, Rev. 6

EN-RP-206, Dosimeter of Legal Record Quality Assurance, Rev. 5

EN-RP-301, Radiation Protection Instrument Control, Rev. 7

EN-RP-302, Operation of Radiation Protection Instrumentation, Rev. 2

EN-RP-303, Source Checking of Radiation Protection Instrumentation, Rev. 4

EN-RP-303-01, Automated Contamination Monitor Performance Testing, Rev. 0

EN-RW-102, Radioactive Shipping Procedure, Rev. 11

FO-OP-025, Dewatering Procedure for EnergySolutions 24 Inch Diameter Disposable Pressure

Vessels, Rev. 6

OP 0631, Appendix B, Alpha and Gamma Determinations, Rev. 28

OP 0631, Appendix C, Tritium Measurement, Rev. 28

OP 0634, Operation of the Dionex Ion Chromatograph, Rev. 20

OP 4605, Environmental Radiation Sampling and Analysis, Rev. 47

Procedures-Completed Surveillance Procedures

EN-DC-117 R007, Attachment 9.6, ECT-48595-01, Torus as CST Post Implementation

Functional Test

EN-RP-203, Attachment 9.3, Dosimetry Investigation Report, 8/18/15

Miscellaneous

ALARA Committee Meeting Minutes, 4/2/15

Decommissioning ALARA Planning Data and ALARA Plan, Rev. 0

-Torus as CST mod - EC 48595

-Transfer and Processing of RWCU resin from CUPS to Cask

Gaseous Effluent Filter Sample and Analysis, 6/29/15

GEL Laboratories LLC, Analytical Results for samples received May 29, 2015 and June 4, 2015

Main Stack Grab Sample and Analysis, 6/15/15

Plan of the Day Meeting/OPS Focus Agenda, 7/21/2015

RSCS, A Summary of Sr-90 Levels in the Environment, April 15, 2015

RWP, 20150621, Revs. 00,01,02, Transfer and Processing of RWCU Resin from CUPS to Cask

Stack Tritium Analysis, 6/29/15

System Abandonment Spreadsheet

Vermont Yankee Offsite Dose Calculation Manual (ODCM) Revisions for Decommissioning,

prepared by RSCS, July 7, 2015

LIST OF ACRONYMS USED

ADAMS

Agencywide Document and Access Management System

ALARA

As Low As Reasonably Achievable

CFR

Code of Federal Regulations

CST

Condensate Storage Tank

EC

Engineering Change

Entergy

Entergy Nuclear Operations, Inc.

FSAR

Final Safety Analysis Report

IMC

Inspection Manual Chapter

IP

Inspection Procedure

ISFSI

Independent Spent Fuel Storage Installation

NRC

U.S. Nuclear Regulatory Commission

REMP

Radiological Environmental Monitoring Program

RWP

Radiation Work Permit

VY

Vermont Yankee Nuclear Power Station

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