ML070290345

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Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases
ML070290345
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 12/04/2006
From:
Entergy Corp
To:
Office of Nuclear Reactor Regulation
References
IP-SMN-AD-103, Rev 0
Download: ML070290345 (19)
v • d • e


Text

December4, 2006 DISTRIBUTION CONTROL LIST Document Name: IP3 ITS /BASES Cc# NAME DEPARTMENT LOCATION 1 OPS PROC GP SUPERVISOR OPS PROCEDURE GROUP IP2 5 CONTROL ROOM ý OPERATIONS IP3 11 RES DEPARTMENT MGR RES 45-4-A 19 STEWARTANN LICENSING GSB-2D 20 CHEMISTRY SUPERVISOR CHEMISTRY DEPARTMENT 45-4-A 21 TSC (IP3) 53' ELEVATION IP2 22 SHIFT MANAGER OPERATIONS IP3 23 LIS LICENSING & INFO SERVICE OFFSITE 25 SIMULATOR, TRAINING 48-2-A 28 RESIDENT INSPETOR US NRC 88' ELEVATION 1P2 32 EOF E-PLAN EOF 47 CHAPMAN, N BECHTWL OFFSITE 50 HAAS, CHERYL A WESTINGHOUSE ELECTRIC OFFSITE 61 SIMULATOR TRAINING 48-2-A 69 CONROY,'PAT LICENSING / ROOM 205 GSB/2D 99 BARANSKI J ST. EMERGENCY MGMT. OFFICE OFFSITE 106 SIM INSTRUCT AREA TRAINING #48 164 CONTROL ROOM OPERATIONS IP3 273 FAISON, CHARLENE NUCLEAR LICENSING WPO-12 319 GRANT, LEAH LRQ TRAINING #48 354 GRANT, LEAH LRQ TRAINING #48 357 GRANT, LEAH ILO TRAINING 48-2-A 424 GRANT, LEAH TRAINING #48 474 OUELLETTE P ENG, PLAN & MGMT INC OFFSITE 489 CLOUGHNESSY, PAT PLANT SUPPORT TEAM GSB/3B 492 WORK CONTROL OPERATION 72' ELEVATION IP2 493 OPERATJONS FIN TEAM 33 TURBIN DECK 45-1-A 494 AOEF / A. GROSSJEAN E-PLAN WPO/12-D 496 GRANT,' LEAH LRQ TRAINING #48 497 GRANT, LEAH LRQ TRAINING #48 500 GRANT, LEAH LRQ TRAINING #48 501 GRANT, LEAH LRQ TRAINING #48 512 GRANT, LEAH LRQ TRAINING #48 513 GRANT, LEAH LRQ TRAINING #48 518 DOC CONTROL DESK i NRC OFFSITE 4oo(

IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0

- tenergy MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Page 1 of 1 S- Entergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 12121/06 PHONE NUMBER: 271-7057 FROM: IPEC DOCUMENT CONTROL The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-103, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.

AFFECTED DOCUMENT: IP3 ITS/BASESJTRM DOC# REV# TITLE F INSTRUCTIONS

                                • FOLLOW THE ATTACHED INSTRUCTIONS****************************
                      • PLEASE NOTE EFFECTIVE DATE***********

RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).

NAME (PRINT) SIGNATURE DATE CC#

I- -

l

Distribution of IP3 Technical Specification Amendment 232 (Approved by NRC December 13 2006)

Pages are to be inserted into your controlled copy of the IP3 Improved Technical Specifications following the instructions listed below. The TAB notation indicates which section the pages are located.

REMOVEAG A NSERT-PAGe, TAB - Facility Operating License FOL Page 3, Amd 231 ý FOL Page 3, Amd 232 TAB - List of Effective Pages Pages 1 through 3, (Amd 231) 1 Pages 1 through 3, (Amd 232)

TAB - List of Amendments TPage 14 TAB 5.0 - Administrative Controls 5.0-3, Amd 205 5.0-3, Amd 232 5.0-4, Amd 205 5.0-4, Amd 232 5.0-5, Amd 205 5.0-5, Amd 232 5.0-10, Amd 205 5.0-10, Amd 232 5.0-11, Amd 221 5.0-11, Amd 232 5.0-26, Amd 205 5.0-26, Amd 232 5.0-37, Amd 205 5.0-37, Amd 232 5.0-38, Amd 205 5.0-38, Amd 232

_....___ ___ .___ .., 5.0-39, Am d 232

____________,__.. ___,_,. 7,,5.0-40,

__ Amd 232 5.0-41, Amd 232 Page 1 of 1

(4) ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Amdt. 203 to receive, possess, and use in amounts as required any 11/27/00 byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 203 possess, but not separate, such byproduct and special 11/27/00 nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 3216 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 232 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.

(3) (DELETED) Amdt. 205 2-27-01 (4) (DELETED) Amdt. 205 2-27-01 D. (DELETED) Amdt.46 2-16-83 E. (DELETED) Amdt.37 5-14-81 F. This amended license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter of May 2, 1975, to Consolidated Edison Company of New York, Inc., granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.

Amendment No. 232

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page IAmend 2 205 8 225 3 205 9 213 Table of Contents Section 3.2.3 10 205 1 227 1 205 11 225 ii 228 2 205 12 205 T

iii 227 3 205 13 205 iv 227 4 205 Section 3.3.3 Section 1.1 Section 3.2.4 1 226 1 205 205 2 211 2 205 2 205 3 205 3 224 3___ 205 4 228 4 205 4 205 5 228 5 225 Section 3.3.1 Section 3.3.4 6 205 1 205 1 226 7 205 2 205 2 [ 205 8 205 3 205 Section 3.3.5 Section 1.2 4 205 1 [205 1 205 5 205 2 [231 2 205 6 205 Section 3.3.6 3 205 7 205 1 205 Section 1.3 8 205 2 205 1 205 9 205 3 205 2 205 10 205 4 205 3 205 11 205 5 205 4 205 12 205 Section 3.3.7 5 205 13 225 1 224 6 205 14 205 2 205 7 205 15 225 3 205 8 205 16 205 Section 3.3.8 9 205 17 205 1 215 10 205 18 205 2 205 11 205 19 225 Section 3.4.1 12 205 20 225 1 J225 13 205 Section 3.3.2 2 225 Section 1.4 1 205 Section 3.4.2 1 205 2 205 1 205 2 205 3 205 Section 3.4.3 3 205 4 205 1 205 4 205 5 205 2 205 Section 2.0 6 205 3 220 1I 1 225 720 4 220 The latest amendment reflected in this list is: Amendment 232

INDIAN POINT 3

-TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 5 220 Section 3.4.13 4 20 5 Section 3.4.4 1 1 205 5 205 1 205 2 J205 Section 3.6.3 Section 3.4.5 Section 3.4.14 1 205 1 205 1 205 2 205 2 205 2 205 3 205 3 205 3 205 4 205 Section 3.4.6 4 205 5 205 1 205 5 256 205 2 205 Section 3.4.15 Section 3.6.4 3 205 1 2261 120 Section 3.4.7 2 205 Section 3.6.5 1 205 3 205 1 205 2 205 4 205 Section 3.6.6 3 205 Section 3.4.16 1 205 Section 3.4.8 1 226 2 205 1 205 2 205 3 205 2 205 3 205 4 205 Section 3.4.9 4 205 Section 3.6.7 1 225 Section 3.5.1 1 205 2 225 1 222 2 205 Section 3.4.10 2 205 Section 3.6.8 1 205 3 205 1 228 2 205 Section 3.5.2 Section 3.6.9 Section 3.4.11 1 205120 1 226 2 205220 2 205 3 230 Section 3.6. 10 3 205 4 205 1 205 Section 3.4.12 Section 3.5.3 2 205 1 205 1 226 3 205 2 226 2 [205 4 205 3 205 Section 3.5.4 Section 3.7.1 4 205 1 205 1 205 5 205 2 [205 2 205 6 205 Section 3.6.1 3 225 7 205 1 205 4 205 8 205 2 205 9 220 Section 3.6.2 Section 3.7.2 10 220 1 205 1 205 11 220 2 205 2 205 12 220 3205 3 205 The latest amendment reflected in this list is: Amendment 232

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 7 205 8 205 9 210 10 232 11 232 12 205 13 205 14 205 15 205 16 205 17 205 18 205 19 205 20 205 21 224 22 224 23 224 24 224 25 224 26 232 27 205 28 205 29 205 30 206 31 225 32 227 33 227 34 225 35 225 36 205 37 232 38 232 39 232 40 232 41 232 The latest amendment reflected in this list is: Amendment 232

Entergy Nuclear Operations, Inc Indian Point 3 Nuclear Power Plant License Amendments Page 14 AMENDMENT SUBJECT LETTER DATE 232 Adoption of TSTF-258, TSTF-308, and Related 12/13/2006 Administrative Control Changes Based on NUREG-1431

Organization 5.2 5.2: Organization 5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.
b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
c. A radiation protection technician shall be on site when fuel is in I the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
d. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g., licensed Senior Reactor Operators (SROs), licensed Reactor Operators (ROs), health physicists, auxiliary operators, and key maintenance personnel).

(continued)

INDIAN POINT 3 5.0- 3 Amendment 232

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the above guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation.

Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

e. The operations manager or assistant operations manager shall hold an SRO license.
f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

This position must be manned in Mode 1, 2, 3 or 4 only.

INDIAN POINT 3 5.0 - 4 Amendment 232

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the following:

a. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975; and
b. The operations manager shall meet or exceed the minimum qualifications of ANSI N18.1-1971 except for the SRO license requirement which shall be in accordance with Technical Specification 5.2.2.e.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

INDIAN POINT 3 5.0 - 5 Amendment 232

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;
e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;
f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;
g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
a. For noble gases: Less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
b. For iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to dose rate of 1500 mrem/yr to any organ.
h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; (continued)

INDIAN POINT 3 5.0 - 10 Amendment 232

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluents Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section 4.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel is surface and volumetrically inspected at 20-year intervals.

(continued)

INDIAN POINT 3 5.0 - 11 Amendment 232

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Holdup System, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure." The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures."

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Waste Gas Holdup System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);
b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank shall be limited to less than the amount that would result in a whole body exposure of > 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and
c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

(continued)

INDIAN POINT 3 5.0 - 26 Amendment 232

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
d. Each individual or group entering such an area shall possess:
1. A radiation monitoring device that continuously displays radiation dose rates in the area; or
2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

INDIAN POINT 3 5.0 - 37 Amendment 232

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

(continued)

INDIAN POINT 3 5.0 - 38 Amendment 232

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any SurfacePenetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.
2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
d. Each individual or group entering such an area shall possess:
1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)

INDIAN POINT 3 5.0 - 39, Amendment 232

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.
4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

(continued)

INDIAN POINT 3 5.0 - 40 Amendment 232

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

INDIAN POINT 3 5.0 - 41 Amendment 232

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