IR 05000271/2015009
| 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) | |
Text
October 22, 2015 Docket No.
05000 271License No.
DPR-28 Mr. Christopher Wamser Site Vice President Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station
Vernon, VT 05354
SUBJECT: NRC INSPECTION REPORT NO. 05000271/201500 9, 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 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-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 05000 271/201500 9 cc w/encl:
Distribution via ListServ
EXECUTIVE SUMMARY
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
, 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."
Based on the results of this inspection, no findings of safety significance were identified.
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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, 608 5 6 , 83750, 84750) The inspector s performed on
-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
-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 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 inspector s 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 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 inspector s performed a walk
-down of the modification , interviewed personnel, and observed work in
-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 inspector s 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 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.
b. Observations and Findings
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.
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.
The inspector s verified that effluent releases to the environment were being properly controlled, monitored, and quantified as required by NRC regulations.
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.
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
-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 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
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
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 P ad , 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
Attachment
Drawings Drawing No
s. 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
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
Attachment
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