ML20204F243
| ML20204F243 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 03/12/1999 |
| From: | Alexander Adams NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9903250241 | |
| Download: ML20204F243 (25) | |
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March 12, 1999 j
LICENSEES: Saxton Nuclear Experimental Corporation (SNEC) and GPU Nuclear Corporation (GPUN)
FACILITY: Saxton Nuclear Experimental Facility (SNEF)
SUBJECT:
SUMMARY
OF MEETING BETWEEN SNEC, GPUN AND THE NRC STAFF On March 11,1999, representatives of the NRC staff met at NRC headquarters with ,
representatives of SNEC and GPUN, the licensees for the SNEF. Enclosure one is a list of I meeting attendees. Enclosure two is the briefing material provided by the licensees at the meeting.
The purpose of the meeting was to present an overview of the Saxton decommissioning project and the recently submitted license termination plan (LTP). The licensees gave a brief description of the operational and licensing history of the facility. The licensees then presented '
an overview of their LTP and their final status survey including release criteria, final status j survey methodology, determination of derived concentration guideline levels, quality assurance, training, conduct of the final status survey and reporting of final status survey results. The NRC staff commented that the first step in the NRC review of the LTP would be an acceptance review to determine if all required topics were discussed in the licensees' submittal. ;
in response to a question from the NRC staff, the licensees discussed the issue of buoyancy of the containment vessel (CV). The water table at the SNEF site is near the surface. The CV i extends about 50 feet below ground level. There is a concem that as the weight of.the CV is ,
reduced by removal of contaminated and activated material, the CV may become buoyant and !
shift in position, raising structural stability concems. The licensees are planning to drill soil cores near the CV to determine soil properties. Friction between the CV and soil could increase significantly the amount of material that could be removed from the CV without buoyancy l becoming an issue. The licensees also plan to study the internal structure of the CV to understand the effect of the polar crane on the CV structure and the effect of removing ;
concrete on the intemal structural stability of the CV.
Docket No 50-146
Enclosures:
As stated Ahnder Adss, Jr., Smitr Project %nger l cc w/ enclosures: See next page ed W g Projet nieterate o \ g(
Divisim of Ikilatnry Ingmmmt Progtms V DISTRIBUTION: office of NrGr lhetar Ik>1nHm HARD COPY E-MAIL COPY Docket File 50-146 SCollins/RZimmerman(SJC1/RPZ) CBassett(CHB 1)
PUBLIC BBoger (BAB2) TBurdick (TMB)
PDND r/f DMatthews (DBM) PDoyle (PVD)
AAdams SWeiss (SHW)- TDragoun (TFD)
OGC (QL5-B18) TMartin (SLM3) WEresian (EJW)
Biyltai LPittiglio (CLP) - SHolmes (SWH)
BMCabe (BCM), MMendonca (MMM) e ", ', " n ,M TMichaels (TSM1) d on 3 / 1/99 j / $/99 '3 /\tf99 .
OF:lCIAL RECORD CO Y. DOCUMENT NAME: G:\SECY\ ADAMS \146 MEET 2. SUM 9903250241 990312 PDR P
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%.....p March 12, 1999 LICENSEES: Saxton Nuclear Experimental Corporation (SNEC) and GPU Nuclear Corporation (GPUN)
FACILITY: Saxton Nuclear Experimental Facility (SNEF)
SUBJECT:
SUMMARY
OF MEETING BETWEEN SNEC, GPUN AND THE NRC STAFF
~
. On March 11,1999, representatives of the NRC staff met at NRC headquarters with representatives of SNEC and GPUN, the licensees for the SNEF. Enclosure one is a list of meeting attendees. Enclosure two is the briefing material provided by the licensees at the meeting.-
The purpose of the meeting was to present an overview of the Saxton decommissioning project l and the recently submitted license termination plan (LTP). The licensees gave a brief
' description of the operational and licensing history of the facility. The licensees then presented an overview of their LTP and their final status survey including release criteria, final status survey methodology, determination of derived concentration guideline levels, quality assurance, training, conduct of the final status survey and reporting of final status survey results. The NRC staff commented that the first step in the NRC review of the LTP would be an acceptance review to determine if all required topics were discussed in the licensees' submittal.
In response to a question from the NRC staff, the licensees discussed the issue of buoyancy of the containment vessel (CV). The water table at the SNEF site is near the surface. The CV extends about 50 feet below ground level. There is a concem that as the weight of the CV is '
reduced by removal of contaminated and activated material, the CV may become buoyant and ,
shift in position, raising structural stability concerns. The licensees are planning to drill soil cores near the CV to determine soil properties. Friction between the CV and soil could increase significantly the amount of material that could be removed from the CV without buoyancy becoming an issue. The licensees also plan to study the internal structure of the CV to understand the effect of the polar crane on the CV structure and the effect of removing concrete on the intemal structural stability of the CV.
M .,
Alexander Adams, Jr., ni Project Manager Non-Power Reactors an ecommissioning Project Directorate Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Cocket No. 50-146
Enclosures:
As stated cc w/ enclosures: See next page
March 129 1999 LICENSEES: Saxton Nuclear Experimental Corporation (SNEC) and GPU Nuclear Corporation (GPUN) l FACILITY: Saxton Nuclear Experimental Facility (SNEF) 1
SUBJECT:
SUMMARY
OF MEETING BETWEEN SNEC, GPUN AND THE NRC STAFF On March 11,1999, representatives of the NRC staff met at NRC headquarters with representatives of SNEC and GPUN, the licensees for the SNEF. Enclosure one is a list of meeting attendees. Enclosure two is the briefing material provided by the licensees at the meeting.
The purpose of the meeting was to present an overview of the Saxton decommissioning project and the recently submitted license termination plan (LTP). The licensees gave a brief description of the operational and licensing history of the facility. The licensees then presented an overview of their LTP and their final status survey including release criteria, final status survey methodology, determination of derived concentration guideline levels, quality assurance, training, conduct of the final status survey and reporting of final status survey results. The NRC waff commented that the first step in the NRC review of the LTP would be an acceptance review to determine if all required topics were discussed in the licensees' submittal.
In response to a question from the NRC staff, the licensees discussed the issue of buoyancy of the containment vessel (CV). The water table at the SNEF site is near the surface. The CV extends about 50 feet below ground level. There is a concern that as the weight of the CV is reduced by removal of contaminated and activated material, the CV may become buoyant and shift in position, raising structural stability concerns. The licensees are planning to drill soil cores near the CV to determine soil properties. Friction between the CV and soil could increase significantly the amount of material that could be removed from the CV without buoyancy becoming an issue. The licensees also plan to study the internal structure of the CV to understand the effect of the polar crano on the CV structure and the effect of removing concrete on the internal structural stability of the CV.
Docket No 50-146
Enclosures:
As stated Alexmkr Ahm, Jr., Smiar Projmt Itntger cc w/ enclosures: See next page es M W Projmt Dirmtarate DISTRIBUTION:
HARD COPY h h N M N tar E-MAIL COPY b
Docket File 50-146 SCollins/RZimmerman (SJC1/RPZ) CBassett (CHB 1)
PUBLIC- BBoger (BAB2) TBurdick (TMB)
PDND r/f DMatthews (DBM) PDoyle (PVD)
AAdams SWeiss (SHW) TDragoun (TFD)
OGC (015-B18) TMartin (SLM3) WEresian (EJW)
Hiyltm LPittiglio (CLP) SHolmes (SWH)
BMCabe (SCM) MMendonca (MMM)
TMichmb (TSM1)
PDN P = :LA AAd - ton s 3 / 3/99 9 / f./99 '3 / v/99 OFJICIAL RECORD COPY DOCUMENT N(AME: G:\SECY\ ADAMS \146 MEET
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Saxton Nuclear Docket No. 50-146 Experimental Corporation (PAGE 1 OF 2) cc:
Mr. Michael P. Murphy, Nuc: ear Engineer Carbon Township Supervisors Bureau of Radiation Protection ATTN: Penny Brode, Secretary Department of Environmental Protection R. D. #1, Box 222-C 13th Floor, Rachel Carson State Saxton, PA 16678 Office Building P.O. Box 8469 Hopewell Township Supervisors Harrisburg, PA 17105-8469 ATTN: Sally Giornesto, Secretary RR 1 Box 95 Mr. Jim Tydeman James Creek, PA 16657-9512 1402 Wall Street Saxton, PA 16678 Mr. D. Bud McIntyre, Chairman Broad Top Township Supervisors Mr. James H. Elder, Chairman Broad Top Municipal Building Concerned Citizens for SNEC Safety Defiance, PA 16633 Wall Street Ext.
Saxton, PA 16678 Mr. Don Weaver, Chairman Liberty Township Supervisors Mr. Ernest Fuller R.D.#1 R.D.#1 Saxton, PA 16678 Six Mile Run, PA 16679 U.S. Army Corps of Engineers Saxton Borough Council Baltimore District ATTN: Peggy Whited, Secretary ATTN: S. Snarski/P. Juhle 9th and Spring Streets P.O. Box 1715 Saxton, PA 16678 Baltimore, MD 21203 Ms. Norma ickes, Chair The Honorable Robert C. Jubelirer Bedford County Commissioners President Pro-Temp Senate of County Court House Pennsylvania 203 South Juliana Street 30th District Bedford, PA 15522 State Capitol Harrisburg, PA 17120 Mr. Larry Sather, Chairman Huntingdon County Commissioners Mr. William G. Heysek County Court House Licensing Department Huntingdon, PA 16652 TMI Nuclear Station P.O. Box 480 Saxton Community Library Middletown, PA 17057 Front Street Saxton, PA 16678
0 Saxton Nuclear Docket No. 50-146 Experimental Corporation (PAGE 2 OF 2) cc:
Mr. Arthur Rone Charles Barker Vice President Nuclear RD 1 Box 143 Safety and Technical Services James Creek, PA 16657 GPU Nuclear Inc.
1 Upper Pond Road James Fockler, Chairman Parsippany, NJ 07054 Saxton Citizens Task Force 1505 Liberty Street Mr. Manuel Delgado Saxton, PA 16678 2799 Battlefield Road Fishers Hill, VA 22626 Dr. Rodger W. Granlund Saxton Independent Inspector Mr. Eric Blocher Radiation Science and Engineering Center 216 Logan Avenue The Pennsylvania State University Wyomissing, PA 19610 Breazeale Nuclear Reactor University Park, PA 16802-2301 Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts, and Mr. Gareth McGrath Trowbridge Altoona Mirror 2300 N Street, NW 301 Cayuga Avenue Washington, D.C. 20037 Altoona, PA 16603 Mr. David Sokolsky 4241 Liberty Bell Ct.
Eureka, CA 95503 l l
l Mr. Gene Baker 501 16th Street ]
Saxton, PA 16678 Mr. Dick Spargo 1004 Main Street Saxton, PA 16678 Mr. Tom Strnad TLG Services 148 New Milford Road East Bridgewater, CT 06752 l
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Enclosure 1 MEETING BETWEEN THE NRC STAFF AND SAXTON l
l l March 11, 1999 r
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- Enclosure 2 ,
Saxton Nuclear Experimental Corporation (SNEC)
Facility Site License Termination Plan Meeting USNRC Rockville MD March 11,1999 SNEC License Termination Plan SNEC Overview:
- SNEC Organization
- Transition Information
- Citizens Task Force
- Saxton Independent Inspector Program 1
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SNEC License Tennination Plan )
SNEC Overview:
- Decommissioning Funding:
- Schedule: l Concrete Removal: till Spring 2000 Site Remediation: Spring- Summer 2000 Final Survey: Fall- Winter 2000/01 License Termination: Spring 2001 l
SNEC License Termination Plan l BriefHistory:
- Westinghouse PWR Design
- 23.5 MWTh/ ~ 7 MWE ,
- Single Loop
- Construction Authorization February 1960 l
-Initial Critically April 1962
( 2
SNEC License Termination Plan !
BriefHistory: 1
- Operational Period 1962 - 1972 Three Fuel cycles )
Mixed Oxides Fuels Failed Fuel Operation Unplanned Releases I
I SNEC License Termination Plan BriefHistory:
- Final Shutdown May 1972 ,
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- Spent Fuel Removed 1972
- Placed in "SAFSTOR" February 1975 1
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SNEC License Termination Plan BriefHistory:
- Phased Remediation:
Decon'annination and Demolition of Support l
. Buildings (1986-1989) l Soil Remediation Project (1994)
CV Characterization (1995-)
Asbestos Abatement (1996-1997)
Electrical System Modifications (1996-1997) i SNEC License Termination Plan !
l BriefHistory: l 1
- Decommissioning T/S Approved April 1998 .
- Major Decommissioning Activities: :
CV Ventilation System System Dismantlement Large Component Removal l
Demins Disposal
- Shield Plug / Concrete Removal i
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. License Termination Plan Covers Issues in the Standard Review Plan (NUREG-1700):
- Site Characterization
- Remaining Dismantlement Activities
- Site Remediation Plans License Tennination Plan
- Covers Issues in the Standard Review Plan (NUREG-1700):
- End use of site
- Project Funding
- Environmental Changes
- Final Status Survey Plan 5
C l
License Termination Plan LTP process:
- The LTP has been submitted as a supplement to L
the SNEC Facility Updated Safety Analysis Report (USAR)
Final Status Survey
Purpose:
- Demonstrates compliance to the NRC that the SNEC Facility Site is below the unrestricted radiological release criteria.
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Final Status Survey
- Site Specific Release Criteria:
- Below USNRC Unrestricted Site Release Criteria (10 CFR Part 20 ). Less than 25 mrem per year (TEDE) to the average member of the critical group
- Below the EPA National Primary Drinking Water Standard for Radioactivity (40 CFR Part 141) Less than 4 mrem per year Final Status Survey
- Site Specific Release Criteria:
- Exposure rates from gamma emitters: .
5 micro- rem per hour @ l meter (average) 10 micro- rem per hour (maximum)
- Below the applicable Derived Concentration Guideline Levels (DCGL) valves for soil, concrete and other structural materials.
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Final Status Survey FSS Methodology:
- Taken mainly from MARSSIM (NUREG-1575)
- Using a form of the Data Quality Objectives (DQO) Process Seven steps per MARSSIM Use to phn the FFS process Final Status Survey FSS Methodology:
- Impacted: . ,
- Areas that have the potential for radioactive contamination. l
- Impacted areas are further divided into three classifications.
l - Initial screening indicates possibly as much as l l 29 acres ,
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Final Status Survey
- FSS Methodology:
- Class 1 Areas:
Areas or locatiens that have a potential for radioactive contamination based on knowledge of site operating history, of known contamination levels or previous radiological surveys.
Final Status Survey FSS Methodology:
- Class 2 Areas:
These areas have or had a potential for radioactive contamination that is not expected to exceed the DCGI,w.
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l Final Status Survey FSS Methodology:
- Class 3 Areas:
Any impacted areas that are not expected to contain any residual radioactivity, or are expected to contain levels of residual radioactivity at a very small fraction of the DCGLw.
Final Status Survey 1
FSS Methodology:
- Non-impacted: l Areas that have no reasonable potential for residual contamination i
- Background reference areas will be selected from non-impacted areas I
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a Final Status Survey Contamination Identification:
- Based on continued site characterization process
- Radiological surveys
- Historical Site Assessment (HSA)
Final Status Survey Determination of Derived Concentration Guideline Levels (DCGL) .
- Current work in progress
- Establishing background level
- Establishing Site Modeling 11
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Final Status Survey 1
Quality Assurance: l
- Instrumentation Selection Calibration and operation
- Survey Documentation
- Quality Control Surveys (internal) ,
- Written Proccdures 1
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i Final Status Survey Quality Assurance:
- Chain of Custody
- Records Management
- Access Controls
- Control of Vendor Supplied Services
- Independent Review of Survey Results l
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Final Status Survey
- Training:
- Overview and Objectives
- Procedures
- Instrumentation
- Sample Collection
- Documentation Final Status Survey Final Survey Phases:
- CV Structure ,
- Remaining Structures
- All On-site areas
- Remaining Impacted Areas l
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l Final Status Survey Area Turnover for FSS:
- Decommissioning activities that have the l potential to re-contaminate the survey area must be completed
- Housekeeping effort completed !
1 Final Status Survey l Turnover for FSS:
- Final Remediation support surveys are ;
completed and may consist of:
Scan surveys Smear (loose surface) surveys I
- Access control measures in place l l
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Final Status Survey
- Access Control Measures (one or more of the following):
- Site personnel awareness
- Barriers
- Postings
- Locking entrances Final Status Survey FFS Performed:
- Basically per MARSSIM
- Per FSS Table 4-4 4
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s Final Status Survey Final Survey Results Report:
- Consist of:
Detailed and summary data reporting for each survey unit. i Final TEDE Evaluation Independently Verified i
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l SNEC License Termination Plan 1
Conclusions:
- No On-site spent fuel .
- Decommissioning Costs are covered
- Unrestricted Release Criteria and Drinking Water Limits) 16 m._
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SNEC License Termination Plan
Conclusions:
- MARSSIM Methodology
- LTP Ongoing Process
- License Termination: Spring 2001
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