ML021420172
| ML021420172 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 06/04/2002 |
| From: | Alexander Adams NRC/NRR/DRIP/RORP |
| To: | |
| Adams A, NRC/NRR/DRIP/RORP, 415-1127 | |
| Shared Package | |
| ML021420336 | List: |
| References | |
| -nr | |
| Download: ML021420172 (10) | |
Text
June 4, 2002 LICENSEES: Saxton Nuclear Experimental Corporation (SNEC) and GPU Nuclear, Inc. (GPU)
FACILITY:
Saxton Nuclear Experimental Facility (SNEF)
SUBJECT:
SUMMARY
OF MEETING BETWEEN SNEC, GPU AND THE NRC STAFFS On May 8, 2002, representatives of the NRC staff met at NRC Headquarters in Rockville, Maryland, with representatives of the SNEC and GPU, the licensees for the SNEF. Attachment one is a list of meeting attendees. The slides used by the licensees during the meeting are attachment two.
The plant was operated between 1962 and 1972, and it was shut down in May 1972. In February 1975, the plant was placed in SAFSTOR until 1986, when phased dismantlement began with the removal of the support buildings, contaminated soil, and some materials in the containment. The licensees decommissioning plan became the Post-Shutdown Decommissioning Activities Report. The resubmitted License Termination Plan (LTP) was accepted for detailed technical review in March 2000.
Technical review of the LTP has generated requests for additional information (RAI). These issues were generally discussed with the licensees during a meeting on April 8, 2002. The May 8, 2002, meeting was a follow on to the April 8, 2002, meeting in the area of dose modeling that the licensees presented to the NRC in their response to RAI2 (RAI dated November 8, 2000, from the NRC). Discussion topics for the meeting were forwarded to the licensees in a letter from the NRC dated May 13, 2002 (ADAMS Accession No. ML021290289).
The discussions with the licensees technical staff and consultants provided clarification and a better understanding of the site specific technical data and related information.
The following points were discussed:
SNEC will use volumetric DCGL values for embedded pipes. SNEC will analyze the effect of exposure from the embedded pipe in conjunction with contaminated building structures. It is likely that some type of building renovation scenario will be used. SNEC also agreed to update Table 5-2 to show specifically which DCGL values (i.e., surface or volumetric) will be used in each survey unit.
NRC agreed to recheck its evaluation of SNEC Calculation Report No. E900-01-005.
NRC agreed that area factors based upon use of RESRAD-Build 3.0 can be used provided that staff can verify the derivation.
Contact:
Alexander Adams, Jr.
301-415-1127
SNEC agreed to use a probabilistic approach in conducting their sensitivity analysis.
DandD default parameter values for behavioral and metabolic parameters will be used as constants. Parameters with a calculated sensitivity equal to or greater than 0.25, based on the PRCC method, will be considered as sensitive parameters. The 25th or 75th percentile parameter value of the parameter distribution will be used in the deterministic analysis used to develop DCGL values depending upon whether the parameter has a negative or positive effect on the result. A check will be made to ensure that the 75th percentile value captures the mean of the distribution. Sensitivity analysis and development of DCGL values will be conducted on each radionuclide individually.
Distribution coefficients, using the site-derived ranges, will be included in the sensitivity analysis.
SNEC will include justification for the 10,000 m2 contamination area and 1 m contamination zone thickness in Section 6 of the LTP.
SNEC will use the same approach for developing surface and subsurface DCGL values (i.e., evaluating each isotope individually); however, the mass balance model will be used for developing DCGL values for the subsurface.
NRC agreed to review by May 22, 2002, SNECs approach for screening out radionuclides. This topic will be briefly discussed during a meeting planned for May 22, 2002, to discuss health physics issues.
A follow-up meeting will be held in July to further discuss the SNEC dose modeling analysis.
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-146 Attachments: 1. List of Attendees
- 2. Briefing Materials cc w/attachments: Please see next page
Saxton Nuclear Docket No. 50-146 Experimental Corporation cc:
Mr. Michael P. Murphy Bureau of Radiation Protection Department of Environmental Protection 13th Floor, Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mr. Jim Tydeman 1402 Wall Street Saxton, PA 16678 Mr. James H. Elder, Chairman Concerned Citizens for SNEC Safety Wall Street Ext.
Saxton, PA 16678 Mr. Ernest Fuller 1427 Kearney Hill Road Six Mile Run, PA 16679 Saxton Borough Council ATTN: Judy Burket 707 9th Street Saxton, PA 16678 Mr. David J. Thompson, Chair Bedford County Commissioners County Court House 203 South Juliana Street Bedford, PA 15522 Mrs. Alexa Cook, Chairman Huntingdon County Commissioners County Court House Huntingdon, PA 16652 Saxton Community Library P.O. Box 34 Saxton, PA 16678 Carbon Township Supervisors ATTN: Penny Brode, Secretary R. D. #1, Box 222-C Saxton, PA 16678 Hopewell Township - Huntingdon County Supervisors ATTN: Reba Fouse, Secretary RR 1 Box 95 James Creek, PA 16657-9512 Mr. D. Bud McIntyre, Chairman Broad Top Township Supervisors Broad Top Municipal Building Defiance, PA 16633 Mr. Don Weaver, Chairman Liberty Township Supervisors R. D. #1 Saxton, PA 16678 U.S. Army Corps of Engineers Baltimore District ATTN: S. Snarski/P. Juhle P.O. Box 1715 Baltimore, MD 21203 The Honorable Robert C. Jubelirer President Pro-Temp Senate of Pennsylvania 30th District State Capitol Harrisburg, PA 17120 Mr. James J. Byrne Three Mile Island Nuclear Generating Station P.O. Box 480 Middletown, PA 17057 Mr. Robert F. Saunders First Energy Corp.
76 South Main Street Akron, OH 44308 Ms. Mary E. OReilly First Energy Legal Department 76 South Main Street Akron, OH 44308
Mr. Manuel Delgado 2799 Battlefield Road Fishers Hill, VA 22626 Mr. Eric Blocher 216 Logan Avenue Wyomissing, PA 19610 Mr. David Sokolsky 1000 King Salmon Avenue Eureka, CA 95503 Mr. Gene Baker 501 16th Street Saxton, PA 16678 Mr. Dick Spargo 1004 Main Street Saxton, PA 16678 Mr. Mark E. Warner AmerGen Energy Co., LLC P.O. Box 480 Middletown, PA 17057 Mr. G. A. Kuehn, Jr.
Vice President SNEC and Program Director SNEC Facility GPU Nuclear, Inc.
P.O. Box 480 Middletown, PA 17057-0480 James Fockler, Chairman Saxton Citizens Task Force 1505 Liberty Street Saxton, PA 16678 Dr. Rodger W. Granlund Saxton Independent Inspector Radiation Science and Engineering Center The Pennsylvania State University Breazeale Nuclear Reactor University Park, PA 16802-2301 Mr. Gareth McGrath Altoona Mirror 301 Cayuga Avenue Altoona, PA 16603 Dr. William Vernetson Director of Nuclear Facilities Department of Nuclear Engineering Sciences University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Mrs. Bunny Barker Box 143, RR 1 James Creek, PA 16657 Mr. William Kanda
First Energy Operating Corp.
10 Center Road Perry, OH 44081
MEETING BETWEEN THE NRC STAFF AND THE SAXTON EXPERIMENTAL CORPORATION May 8, 2002 NAME TITLE ORGANIZATION Alexander Adams, Jr.
Project Manager USNRC Sam Nalluswami Project Manager (NMSS)
USNRC Patrick Madden Chief, Research & Test Reactors USNRC Patrick Isaac Examiner, RORP/R&TR USNRC Robert D. Holmes Projext Consultant GPU/FE Art Paynter RSO, FSS Manager GPU/FE Barry Brosey GPU Tech. Analyst USNRC Pat Donnachie GPU Consultant USNRC Jim Byrne Manager, D&D Eng.
GPU Mark Thaggard Sr. Systems Performance Analyst NRC/NMSS Rodger Granlund Independent Inspector Penn State Concerned Citizens Ernest Fuller Citizen For SNEC Safety Daniel Hughes Project Manager USNRC June 4, 2002
SNEC agreed to use a probabilistic approach in conducting their sensitivity analysis.
DandD default parameter values for behavioral and metabolic parameters will be used as constants. Parameters with a calculated sensitivity equal to or greater than 0.25, based on the PRCC method, will be considered as sensitive parameters. The 25th or 75th percentile parameter value of the parameter distribution will be used in the deterministic analysis used to develop DCGL values depending upon whether the parameter has a negative or positive effect on the result. A check will be made to ensure that the 75th percentile value captures the mean of the distribution. Sensitivity analysis and development of DCGL values will be conducted on each radionuclide individually.
Distribution coefficients, using the site-derived ranges, will be included in the sensitivity analysis.
SNEC will include justification for the 10,000 m2 contamination area and 1 m contamination zone thickness in Section 6 of the LTP.
SNEC will use the same approach for developing surface and subsurface DCGL values (i.e., evaluating each isotope individually); however, the mass balance model will be used for developing DCGL values for the subsurface.
NRC agreed to review by May 22, 2002 SNECs approach for screening out radionuclides. This topic will be briefly discussed during a meeting planned for May 22, 2002, to discuss health physics issues.
A follow-up meeting will be held in July to further discuss the SNEC dose modeling analysis.
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Section Operating Reactor Improvements Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-146
Enclosures:
- 1. List of Attendees
- 2. Briefing Materials cc w/enclosures: Please see next page DISTRIBUTION:
PUBLIC REXB/R&TR r/f PDoyle FGillespie TDragoun MMendonca AAdams WBeckner OGC EHylton SHolmes CBassett DMatthews WEresian PIsaac JPeckenpaugh (NMSS)
CCraig (NMSS)
PMadden GHill (2) (T5-C3)
SSchneider (NMSS)
SNalluswami (NMSS)
ADAMS ACCESSION NO: ML021420172 TEMPLATE #: NRC-001 OFFICE RORP:LA RORP:PM NMSS RORP:SC NAME EHylton:rdr AAdams SNalluswami PMadden DATE 05/ 28 /2002 05/ 30 /2002 06/ 03 /2002 06/ 03 /2002 C = COVER E = COVER AND ENCLOSURE N = NO COPY OFFICIAL RECORD COPY