ML060870631
| ML060870631 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/06/1996 |
| From: | Essig T Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2005-0293, TAC M92295, TAC M92296 NUDOCS 9606110367 | |
| Download: ML060870631 (6) | |
Text
June. 6, 1996 MEMORANDUM TO:
John Stolz, Director Project Directorate 1-2 Division of Reactor Projects -
I/11 Office of Nuclear Reactor Regulation FROM:
Thomas H. Essig, Chief Original signed by:
Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS I AND 2, ONSITE DISPOSAL OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR 20.2002 The Emergency Preparedness and Radiation Protection Branch has completed its review of the PECO Energy Company's (the licensee) application, dated April 6, 1995, as supplemented on November 15, 1995, for approval, pursuant to 10 CFR 20.20)02, to dispose of contaminated soil, sediment, and sludges on the Limerick Generating Station site.
Attachment I to this memorandum provides our evaluation of the licensee's application. Attachment 2 provides a SALP input.
We find the licensee's application to be acceptable, with the added requirement that the licensee incorporate the analysis used to support this application into its Radiological Process Control Program. Any changes made, by tEe licensee, to the analysis of this approved application must be submitted to the NRC for approval prior to implementation. This is to ensure that all disposals conducted under this approved application remain within the analyzed bounding conditions.
This completes our review under TAC Nos. M92295 and M92296.
Docket Nos.
50-352 50-353 Attachments:
- 1.
Safety Evaluation
- 2.
SALP Input CONTACT:
Stephen Klementowicz, NRR/PERB 415-1084 U13 WUI K
TION Docket File FRinaldi JWhite RI PERB Rleading File HAstwood BGrime!S CMiller SKlemEntowicz TEssig DOCUMENT NAME:
G:\\LIMERICK.SPK To receive a copy of this document. Indicate In the box:
C' Copy without attachment/enclosure
'E' a Copy with attachmentlenclosure
'N-No copy FOFFCE IPERB E a s E I C-:PERB / !lv I
I NAME Vtementowfcz TESSig DATE 06/
/96 061
/9 19 OFFICIAL RECORD COPY
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 6, 1996 MEMORANDUM TO:
John Stolz, Director Project Directorate I-2 Division of Reactor Projects -
I/11 Office of Nuclear Reactor Regulation FROM:
Thomas H. Essig, Chief Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
LIMERICK GENERATING STATION, UNITS I AND 2, ONSITE DISPOSAL OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR 20.2002 The Emergency Preparedness and Radiation Protection Branch has completed its review of the PECO Energy Company's (the licensee) application, dated April 6, 1995, as supplemented on November 15, 1995, for approval, pursuant to 10 CFR 20.21)02, to dispose of contaminated soil, sediment, and sludges on the Limerick Generating Station site. to this memorandum provides our evaluation of the licensee's application. Attachment 2 provides a SALP input.
We find the licensee's application to be acceptable, with the added requirement that the licensee incorporate the analysis used to support this application into its Radiological Process Control Program. Any changes made, by the licensee, to the analysis of this approved application must be submitted to the NRC for approval prior to implementation. This is to ensure that all disposals conducted under this approved application remain within the analyzed bounding conditions_
This completes our review under TAC Nos. M92295 and M92296.
Docket Nos.
50-352 50-353 Attachments: 1. Safety Evaluation
- 2.
SALP Input CONTACT: Stephen Klementowicz, NRR/PERB 415-1084
C'LP'R R EG&4 UNITED STATES gH NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-00 EVALUATION BY THE EMERGENCY PREPAREDNESS AND RADIATION PROTECTION BRANCH OFFICE OF NUCLEAR REACTOR REGULATION PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS I AND 2 ONSITE DISPOSAL OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR 20.2002 DOCKET NOS. 50-352 AND 50-353 Introduction By letter dated April 6, 1995, and as supplemented on November 15, 1995, F'ECO Energy Company (the licensee), requested approval pursuant to 10 CFR 20.2002 for the disposal of contaminated material in a manner not specifically described in 10 CFR Part 20, Subpart K. The licensee has proposed to dispose of a maximum of 70,000 cubic feet of contaminated material (i.e., soil, sediment, and sludges) per year from the Limerick Generating Station (LGS) site settling basin, emergency spray pond, and cooling tower basins to a specific area within the LGS site restricted area.
The licensee has anticipated the need for future disposals of this type of material and has performed an evaluation to support the disposal of a maximum of 1j120,000 cubic feet over a 16 year period.
The licensee's request contains: (1) A detailed description of the licensed material to be disposed, including the physical and chemical properties important to risk evaluation, and the proposed manner and conditions of waste dispo xl, (2) An1 aGallysis ind VvdlUdl iH u1f pet-i rHell Iinfurormtilon on the nature of the environment; (3) The nature and location of potentially affected facilities; and (4) Analyses and procedures to ensure that doses are maintained ALARA.
Descri~Dtion of waste The material to be disposed of is composed of soil, sediment, and sludges (i.e., flowable solids). The material originates from the LGS settling basin, emergency spray pond, and cooling tower basins. The materials are suspended solids, which have settled to the bottom of these systems.
In order to assess the magnitude of the disposal, the material from the settling basin was sampled and analyzed using a lower limit of detection (ILD) consistent with the LLDs used in the licensee's radiological environmental monitoring program (REMP).
In addition to the naturally occurring
2 radionuclides (i.e., Be-7, K-40, Ra-226, and Th-228), statistically positive activities for Mn-54, Co-60, and Cs-137 were also detected.
The activity for Mn-54 averaged 1.8 E-08 pCi/gram (dry), and ranged from 5.0 E-09 to 4.0 E-08 pCi/gram (dry).
The activity for Co-60 averaged 1.14 E-07 pCi/gram (dry), and ranged from 4.0 E-08 to 2.2 E-08 pCi/gram (dry). The activity for Cs-137 averaged 3.7 E-08 pCi/gram (dry), and ranged from 3.8 E-09 to 6.0 E-08 pCi/gram (dry).
The Cs-137 activity was consistent with background levels observed in the Limerick area as a result of fallout from atomic weapons testing.
To evaluate the radiological dose consequences of the multiple disposals, the licensee performed a conservative bounding analysis using radionuclide concentrations equal to 10 times the values of the LLD for monitoring effluents, as defined in the LGS Radiological Process Control Program. The concentrations used in the bounding calculation are higher than the actual concentrations observed in the settling basin discussed above.
Disposal method and location The material will be transported to the designated on-site area, near the on-site radwaste storage pad, west-northwest of the emergency spray pond.
The material will be placed in the 1.5 acre area, graded, and seeded with grass to prevent wind erosion and to blend in with the surrounding area.
While in this designated restricted area, the contaminated material is expected to decay to non-detectable levels by the time the plant is expected to be decommissioned.
-The.designated disposal -area is part of -the site restricted area and will be patrolled and monitored by LGS plant security personnel.
Evaluation In it; application, the licensee used the computer code GASPAR to calculate doses to the general public, non-occupationally exposed workers, and to the inadvertent intruder.
The lUcon~see-haas-_
itted t i q. theM LUldted xposure to the maximumally exposed member of the public will not exceed 1.82 E-4 mrem per year, total effective dose equivalent; 0.101 mrem per year to the critical organ (infant's liver, via the goat milk pathway); the calculated maximum exposure to a plant worker will not exceed 3.1 mrem per year; and the calculated dose to an inadvertent intruder will not exceed 0.75 mrem per year.
The calculated doses are well within the limits of 10 CFR Part 20 and 40 CFR Part 1.90.
Actual doses are expected to be less than the calculated doses.
The licensee has committed to establish a program to provide for periodic verification of expected radionuclide concentrations, activity levels, and radionuclide distribution. The licensee will perform an analysis for every future quantity of material removed from the specified locations prior to placing the material in the designated disposal area. The performance of this method and analysis will be controlled by the LGS Radiological Process Control
I
Program.
Further, the licensee has a program to provide for maintenance of appropriate records of radionuclide concentrations and total activity. The licensee has stated that these records will be maintained in accordance with 10 CFR 50.75(g).
The licensee has committed to revise the LGS Updated Final Safety Analysis Report to include a description of the designated disposal area, and the bounding analysis used for this application.
The licensee's radiological environmental monitoring program (REMP) will be used to monitor any offsite release of radioactive material from the disposed material. The results of the REMP analyses will be reviewed by the licensee to confirm that the material is within the bounds of its original analysis.
The licensee has acknowledged that the material is also subject to the requirements of the Pennsylvania Department of Environmental Resources residual waste requirements.
The ;taff has reviewed the proposed disposal site layout and topography and has Verified that the general topography of the disposal site is compatible with the proposed disposal mechanisms and that it is unlikely that the disposed material would be recycled.
Conclusion The Staff has reviewed the licensee's application and has concluded that the doses calculated by the licensee appear reasonable, are a small percentage of 10 C1R Part 20 public dose limits, and conforms to the requirements set forth in 10 CFR 20.2002 and is therefore acceptable.
The staff requires the licensee to incorporate the analysis used to support this application into its Radiological Process Control Program. Any changes, by the licensee, to the analysis of this approved application must be submitted to the NRC for approval prior to implementation.
This is to ensure that all disposals conducted under this approved application remain within the analyzed bounding conditions.
"m.
SALP INPUT Facility Name:
LIMERICK GENERATING STATION, UNITS 1 AND 2
Subject:
REVIEW OF ONSITE DISPOSAL OF CONTAMINATED MATERIAL PURSUANT TO 10 CFR 20.2002 Reviews Area:
November 15, application, contaminated By letter dated April 6, 1995, and as supplemented on 1995, PECO Energy Company (the licensee), submitted an pursuant to 10 CFR 20.2002 for the on-site disposal of material (i.e., soil, sediment, and sludges).
Licensee's Performance -
Engineering/Technical Support The licensee's submittal was well written and contained above average technical background and related information to support its request. When requested, the licensee provided additional information to clarify its original application.
The overall quality of the licensee's TS package was good.
Principal Contributor:
Stephen Klementowicz Date: May 30, 1996