ML20058L941
| ML20058L941 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/08/1993 |
| From: | Vitkus T AFFILIATION NOT ASSIGNED |
| To: | Fauver D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| CON-FIN-A-9076 NUDOCS 9306150124 | |
| Download: ML20058L941 (7) | |
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e-ORISE OAK RfDGE INSTITUTt FOR SCIENCE AND TDUCATtON '
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February 8,1993 -
~ Mr. Dave Fauver
. Division of Low-Level Waste Management - NMSS
- U.S. Nuclear Regulatory Commission E
One White Flint North
.11555 Rockville Pike Rockville,'MD 20852 SUBJ ECT:
PROPOSED CONFIRMATORY SURVEY PLAN FOR TIIE TURBINE INTERNAL -
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' COMPONENTS, SIIOREIIAM NUCLEAR POWER STATION, BROOKIIAVEN,
. NEW YORK - DOCKET FILE NO. 50-322.
Dear Mr. Fauver:
Enclosed is the subject document for your review and comment. ESSAP will incorporate any comments you may have into the final survey plan.
I
. ESSAP would also 1ike to take this opportunity to request a written response from the licensee regarding the comments provided in our January 12,1993 correspondence, particularly, the third, fifth, and ninth specific comments. We feel that resolution of these items is critical to evaluating the licensee's
- documentation and planning the confirmatory survey activities.
Please do not hesitate to contact either Michele Landis at (615) 576-2908 or myself at (615) 576-5073
- should you have any questions.
Sincerely,
- Timothy J. Vitkus Environmental Project Izader Environmental Survey and Site Assessment Program TJV: sis cc:
T. Mo, NRC/NMSS, 6H3 D. Tiktinsky, NRC/NMSS, 6E6
' J. Swift /F. Brown, NRC/6H3 -
R. Nimitz, NRC/ REGION I J. Berger, ORISE 09 m 7 M. Landis, ORISE 7
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I PROPOSED CONFIRhfATORY SURVEY PLAN FOR TIIE TURBINE INTERNAL COMPONENTS i
SIIOREIIAM NUCLEAR POWER STATION BROOKIIAVEN, NEW YORK l
INTRODUCTION AND SITE IIISTORY r
The long Island Power Authority (LIPA) operated a boiling water reactor known as the j
i Shoreham Nuciear Power Station (SNPS). The plant was designed to provide a gross electrical output of 849 Megawatts and achieved initial criticality in February 1985. The U.S. Nuclear Regulatory Commission (NRC) license (NRC Docket File No. 50-322) issued for the facility allowed reactor operations at power levels not to exceed 5% of full power. Ixw power testing in accordance with the license then commenced in July 1985 and continued intermittently until i
January 1989, at which time power generating operations were terminated. The total reactor operating history was equivalent to 2.03-effective full power days of fuel exposure. The irradiated fuel was subsequently removed from the reactor vessel and placed into the spent fuel j
pool in August 1989.
Various reactor components, piping systems, and other equipment became radiologically contaminated as a result of reactor operations. The primary contaminants which have been i
Prepared by the Environmental Survey and Site Assessment Program of Oak Ridge Institute for Science and Education, Oak Ridge, TN, under interagency agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and The U.S. Department of Energy.
Shmtham NPS - f ebruary 8,1993
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identified during characterization studies include iron-55 (Fe-55), cobalt-60_(Co-60), nickel-63
~(Ni-63), and smaller quantities of tritium. (H-3),, carbon-14 (C-14), nickel-59 (Ni-59),
manganese-54 (Mn-54), zinc-65 (Zn-65), and europium-152 (Eu-152).
LIPA plans to decommission the facility and release the site for unrestricted use. The LIPA-Decommissioning Plan was approved for implementation by the NRC in June 1992 and will-include decontamination or removal of contaminated portions of the reactor and other plant systems and equipment. The decommissioning will be conducted in several' phases, terminating in the removal of the spent fuel. The first phase, which is the subject of this survey plan, will involve the interior components of the turbine which is located inside of the Turbine Building -
-It is the policy of the NRC to perform confirmatory surveys of facilities that have undergone decommissioning and have requested NRC license termination. NRC's Division of Low-Level Waste Management and Decommissioning, Headquarters Office has requested that' the Environmental Survey and Site Assessment Program (ESSAF) of the Oak Ridge Institute for Science and Education (ORISE) conduct a confirmatory radiological survey of the turbine components.
SITE DESCRIPTION The site is approximately 80 km (50 miles) east of the confluence of the East River and Long _
Island Sound near La Guardia Airport. The SNPS is located on a 32.4 ha (80 acres) portion of:
Shurcham NPS - Fcbruary 8,1993 2
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a larger 202 ha (499 acre) parcel ofland owned by the Long Island Lighting Company.(LILCO).
"The site is bounded on the north by Long Island Sound on the east by the Wading River ~
Marshland, on the west by other LILCO property, and on the south by Route 25A.
OBJECTIVE The objectives of the confirmatory survey are to provide independent document reviews and radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee's radiological status report relative to the established guidelines.
RESPONSIBILITY Work described in this survey plan will be performed under the direction of Michele Landis, i
Project Manager and Tim Vitkus, Project Leader of ESSAP. The cognizant site supervisor has the authority to make appropriate changes to the survey with the approval of the NRC site representative. Deviations to this survey plan will be documented in the site log book.
PROCEDURES ESSAP will perform reviews of pertinent documents and field data, developed by LIPA for the i
turbine components. In addition, a survey team from ESSAP will perform independent visual' inspections, measurements, and sampling.
Shardam NPS - I%ruary 8,199) 3 nmss^runonni^u'.snonai^uui:
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.x Field survey activities will be conducted in accordance with the applicable sections of the ESSAP Survey Procedures and Quality Assurance Manuals.
SURFACE SCANS Alpha, beta, and gamma surface scans will be performed on representative portions of the various turbine components. Locations of elevated direct radiation detected by scans will be -
marked for further investigation. Scans will be performed using ZnS, GM, and Nal detectors, coupled to ratemeters or ratemeter-scalers with audible indicators.
SURFACE ACTIVITY MEASUREMENTS Total alpha and total beta surface activity measurements will be performed at up to 10% of the locations selected for survey by LIPA. Measurements will be performed using ZnS and GM detectors, coupled to ratemeter-scalers. A smear sample will be collected from each direct measurement location to determine removable activity levels.
SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data will be returned to ESSAP's Oak Ridge laboratory for analysis and interpretation. Smears will be analyzed for gross alpha and gross beta activity using a low.
background proportional counter.
Shorrham NPS - Fetnuary 8.1993 4
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r-Analytical data and direct measurement data will be converted to units of dpm/100cm' and-compared to the NRC' guidelines.
The applicable guidelines' for beta-gamma emitters (radionuclides with decay modes other than alpha emission or spontaneous fission) except Sr-90 are:
Total Activity L
2 2
5,000 S-y dpm/100 cm, average in a im area 2
2 15,000 S-y dpm/100 cm, maximum in a 100 cm area Removable Activity 2
1000 S-y dpm/100 cm The applicable guidelines for U-natural, U-235, U-238, and associated decay products are:
Total Activity 2
2 5,000 a dpm/100 cm, average over a Im area 2
2 15,000 a dpm/100 cm, maximum in a 100 cm area Removable Activity 2
1,000 a dpm/100 cm The survey results will be presented m a draft letter report and submitted to the NRC for review-and comment.
Shordam NPS - Febn=ry 8, IW3 WTASAP.SHORDMESHORUMM.W1
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LIST OF CURRENT PROCEDURES
' Applicable procedures from ORISE ESSAP Survey Procedures Manual include:
.i Section 6.0 Measurement Techniques f
6.1 Alpha Radiation Measurement t
6.2 Beta-Gamma Radiation Measurement
.i 6.3 Gamma Radiation (Exposure Rate) Measurement
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i 6.4 Surface Scanning 6.10 Instrument Calibration Section 7.0 Sarpling Procedures 7.7 Determination of Transferable Contamination 7.10 Sample Identification and Labeling Section 8.0 Integrated Survey Procedures f
8.2 General Survey Approaches and Strategies 8.4 Surveys ofIndoor Areas i
Section 9.0 Health, Safety and Contamination Control I
Section 10.0 Quality Assurance and Quality Control st-h wrs ret,rory s. m3 6
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