E910-03-048, Containment Vessel (Cv) Radiation Survey

Containment Vessel (Cv) Radiation Survey

ML033650106
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/22/2003
From:	Kuehn G GPU Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-RFPFR, E910-03-048
Download: ML033650106 (5)

Text

GPU Nuclear, Inc.

v G NUCLEARU NUCLEAR Three Mile Island

~~~~~~~~~~~~~~~~~~~~~~~~N Station Route 441 South Post Office Box 480 Middletown, PA 17057-0480 Tel 717-948-8461 December 22, 2003 E910-03-048 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen,

Subject:

Saxton Nuclear Experimental Corporation (SNEC)

Operating License No., DPR-4 Docket No. 50-146 Containment Vessel (CV) Radiation Survey In our December 5. 2002 letter (E910-02-058) GPU Nuclear provided responses to seven (7)requests for additional information (RAI) questions. These questions and responses were related to the SNEC Facility Technical Specifications Change Request (TSCR No. 62) to allow removal of the CV upper dome following Final Status Survey of the below grade portions of the CV. From that letter the GPU Nuclear committed to taking the following action to RAI question 7.

Question 7 Please provide survey information on radiation levels on the operating floor level of the CV after backfilling and isolation activities are complete.

Response

GPU Nuclear agrees to provide survey information on radiation levels on the operating floor" level of the CV after backfilling and isolation activities are complete. Note that the term operating floor" has traditionally referred to the original 818'/812' elevation concrete floor of the CV. Since all the concrete has been rem6ved from the CV this floor is no longer in place. Following back fill and isolation activities, a cover will be placed on top of the back fill to prevent cross contamination during removal of the upper CV dome. This cover, and any exposed portion of the CV liner, which will remain following license termination, will be included in the Final Status Survey (FSS).

The purpose of this letter is to provide you the information on radiation levels on the operating floor of the CV since backfilling and isolaton activities have been completed. A nominal six-inch concrete cap has been poured over the backfill materials at approximately the 803.9' elevation. This elevation represents the new operating floor level. Radiation readings were taken on this elevation.

Twenty nine (29) general area radiation readings were taken at waist level. Survey information is provided in Attachment 1. The radiation survey results are consistent with natural background and are listed as follows:

Average radiation dose rate: 0.0035 +/-0.0016 mrlhr Range of readings: 0.002 - 0.006 mrhr A 0 &O0

If you have any questions on this information, please contact Mr. Art Paynter at (814) 635-4384.

Sincerely,

@S\ \\ 1)%s P.-,o, ke- 2Z Of G. A Kuehn Program Director, SNEC cc: NRC Project Manager, NRR NRC Project Scientist, Region I Attachments:

Attachment I - CV Radiation Survey Results

Attachment 1 CV Radiation Survey Results Location: New CV Ops Floor @803.9' elevation - post concrete cap installation Survey Date: 12/18/2003 Technician: Bill Horton Instrument Bicron microrem meter Serial # C233J Cal. Due Date 3/11/2004 Item Reading (mr/hr) 1 0.004 2 0.004 3 0.003 4 0.004 5 0.003 6 0.003 7 0.002 8 0.004 9 0.004 10 0.003 11 0.003 12 0.003 13 0.004 14 0.003 15 0.002 16 0.005 17 0.003 18 0.003 19 0.003 20 0.003 21 0.004 22 0.004 23 0.005 24 0.003 25 0.004 26 0.005 27 0.004 28 0.003 29 0.003 Mean 0.0035 Uncertainty (2a) 0.0016 Comments: 1. Concrete cap poured on 12/17/03. Radiation readings required per NRC RAI 07 for TSCR#62.

2. Survey readings taken at waist level.

OR~~~iIi

_ SNECFSSRADIOLOGICALSURVEY I SurveyUnits CV1-1 I Survey# 200-03-1658 Location Containment Vessel General Area at elevation 808 ft Grid # WA Area Classification WA SR # NIA Reason For Survey General Area Survey after Concrete Cap Installation Date of Survey l 12118103 Time of Survey 1315 Technician W. Horton )! ) d I Technician NIA GRCS Review R. Shepnerd Date Of Review I2- /,5 Radiological Instrument Data Radiological Instrument Data Radiological Instrument Data InstJProbe Type micro Rem InstJProbe Type N/A InstJProbe Type N/A Serial Number(s) C233J Serial Number(s) Serial Number(s)

Cal. Due Date(s) 3/11/04 Cal. Due Date(s) Cal. Due Date(s)

Efficiency (%) N/A Efficiency (%) Efficiency (%)

ABCR (cpm) N/A ABCR (cprn) ABCR (cpm)

BRA Average N/A BRA Average BRA Average BRA Location N/A BRA Location BRA Location Source Checks Sat l 0 Source Checks Un Source Checks Sat l I Unsat O Comments All readings are general area at approximately waist level.

Survey Map Please refer to the attached map.

NOTES: [l] = Location where general area dose rates were taken

Containment vessel radiation survey Survey # 200-03-1658 Technician: W. Horton Instrument: C233J microR Date: 12/18/03 N