ML20134K662
| ML20134K662 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/11/1996 |
| From: | Yundt C PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20134K574 | List: |
| References | |
| NUDOCS 9611190266 | |
| Download: ML20134K662 (5) | |
Text
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Portland General Electric Coir,;eniy CPY-083-96 TO:
Distributio FROM:
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DATE:
November 11,1996
SUBJECT:
Iransmittal of Revision 1 to PGE-1061. " Trojan _ Nuclear Plant Decommissioning Plan" Enclosed are replacement pages for your Controlled Copy of Revision 1 to PGE-1061, " Trojan Nuclear Plant Decommissioning Plan." The pages are to be inserted in accordance with the accompanying instruction sheet.
Please acknowledge receipt of your copy by completing the lower portion of this transmittal and returning it to the location given below.
CPY/CKC i
i Enclosure 11/11/96 i
ACKNOWLEDGMENT PGE-1061, " Trojan Nuclear Plant Decommissioning Plan," Revision 1 I hereby acknowledge receipt of Controlled Copy number the subject document. All changes have been made in accordance with the instructions, and superseded pages have been destroyed.
Signature of Copy Holder Date Return to:
Pat Schaffran/TCB-3 Trojan Nuclear Plant 71760 Columbia River Highway Rainier, Oregon 97048 9611190266 961111 PDR ADOCK 05000344 P
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i TROJAN NUCLEAR PLANT PGE-1061, " Trojan Nuclear Plant Decommissioning Plan, Revision 1" The following is provided as a guide for inserting revised pages:
2 REMOVE EXISTING PAGE INSERT REVISED PAGE Xiii a:
3-40 3-40 3-44 3-44
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1 i
4 4
4 b
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TROJANDECOAS11SSIONING PIAN 1
LIST OF EFFECTIVE PAGES Section/Page Revised _Date Pages i through xii June 1996 i
Page xiii November 1996 a
Section 1 June 1996 Section 2 June 1996 Section 3 Pages 3-1 through 3-39 June 1996 Page 3-40 November 1996 Pages 3-41 through 3-43 June 1996 Page 3-44 November 1996 i
Pages 3-45 through 3-79 June 1996 Tables 3.1-1 through 3.1-9 June 1996 i
Figures 3-1 through 3-39 June 1996 Section 4 June 1996 Section 5 June 1996 Section 6 June 1996 Section 7 June 1996 i
Section 8 June 1996 i
Section 9 June 1996 4
Appendix A June 1996 Appendix B.
June 1996 l
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xiii Resision 1 J
TROJANDECOADflSSIOh7NG PLAN procedures and equipment employed for measuring and minimizing personnel exposure, is procided in the DSAR.
3.2.6.1.1 laboratory Radiation Pmtection Instmmentation The laboratory-type radiation instmmentation includes the following:
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High-resolution solid-state detector (s) provided with lead shielding and a multichannel analyzer; 2.
A beta counting system using Geiger-Mueller detectors; 3.
A liquid scintillation counter; 4.
A low-background thin-window gas flow proponional counter; and 5.
An alpha counting system (solid-state detector).
Counting efficiencies of laboratory radiation detectors have been detennined with certified radionuclide standards. A periodic calibration check is performed to check the efficiency of "in use" laboratory radiation detectors. Additional detail regarding calibration, testing, and f.~
i maintenance of laboratory mdiation protection instmmentation is provided in the DSAR and in radiation protection implementing procedures.
3.2.6.1.2 Ponable Radiation Detection Instmmentation The ponable radiation detection instmmentation available for use within the plant includes l
the following:
1.
Alpha detectors having count rate output; 2.
Ionization chamber instmments equipped with a beta window and correction factor for beta measurement; and l
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Wide-range Geiger-Mueller instmments having dose rate and count rate output.
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3-40 Revi,ien t
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TROJANDECOMAHSSIONING PL4N
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contaminatio'.i levels is fmther controlled and defined in accordance with 10 CFR 20 and radiation protection implementing procedures. Plant procedures also describe the requirements for radiological postings advising workers of potential radiological hazards at the entrance and boundaries of radiologically controlled areas.
3.2.6.3.3 Facility Contamination Control Plant and radiation protection implementing procedures direct the use of various practices and equipment to ensure general plant area contamination is controlled at the source to the greatest extent possible. Additional contamination controls are specified forjobs involving high levels of contamination (e.g., r. double step-off pad, additional surveys, etc.).
Appropriate contamination controls are used when carrying contaminated tools and equipment between areas. Geiger-Meller count rate meters (friskers) are located within the plant so that personnel can determine if they have been contaminated prior to entering another area of the plant. The final checkpoint for personnel leaving controlled areas of the plant is the access control point. Temporary exit points may be established at remote l
control areas as needed.
l Airborne contamination is minimized by minimizing loose contamination levels and their i
sources. The use of installed and temporary ventilation systems prevents the build-up of air contamination concentrations. These systems are described further in Sections 2.2.4.8, j
O 2 2.5.20, and 2.2.5.22.
Additional details on the policy and methods for controlling general area and airborne contamination are contained in radiation protection implementing procedures.
3.2.6.3.4 Personnel Contamination Control Contamination of personnel is controlled by the use of several types of protective clothing when entering contaminated areas. In the event that levels of airborne contamination approach or exceed applicable limits, provision is made for personnel to use respiratory protective equipment. Allowances are made for the use of respiratory protective equipment, as specifically authorized by the NRC, in determining whether individuals in restricted arcas are exposed to concentrations in excess of the values specified in 10 CFR 20. The use of respimtory protection equipment is consistent with the goal of maintaining the total effective dose to personnel ALARA.
Additional details on the policy and methods for controlling personnel contamination are contained in radiation protection implementing procedures.
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V 3-44 Revision 1