ML063190553

Tech Spec Pages for Amendment Nos. 207 and 199 Regarding Revision of Administrative Controls

ML063190553
Person / Time
Site:	San Onofre
Issue date:	11/15/2006
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Kalynanam N, NRR/DORL/LP4, 415-1480
Shared Package
ML062900329	List: ML062900332 ML063190553
References
TAC MD2581, TAC MD2582
Download: ML063190553 (18)

Text

(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) SCE, pursuant to the Act' and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical fom, for sample analysis or instrument calibration or.

associated with radioactive apparatus or components; and (6) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess but not separate, such byproduct and special nuclear materiais as may be produced by the operation of San Onofre Nuclear Generating Station, Units I and 2 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth In 10 CFR Chapter I 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) Haxi*um Power Level Southern California Edison Company (SCE). is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protectjn Plan contained in Appendix B, as revised

'through Amendment No. .07 , are hereby incorporated An the license.

Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment Ho. 2 0 7

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2, departure from nucleate boiling ratio (DNBR) shall be maintained at > 1.31.

2.1.1.2 In MODES 1 and 2, peak fuel centerline temperature shall be maintained at < 5080°F, decreasing by 58°F per 10,000 MWD/MTU and adjusted for burnable poison per CENPD-382-P-A.

2.1.2 Reactor Coolant Svstem (RCS) Pressure SL In MODES 1, 2, 3, 4, and 5., the RCS pressure shall be maintained at _ 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1' 1 or SL 2.1.1.2 is violated, restore compliance and be in MODE 3 within I hour.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

SAN ONOFRE--UNIT 2 .2.0-1 Amendment No. 207

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The corporate officer with direct responsibility for the plant shall be responsible for overall unit operation and maintenance of Units 2 and 3 at San Onofre Nuclear Generating Station, and all site support functions. He shall delegate in writing the succession to this responsibility during his absence.

5.1.2 The Shift Manager shall be responsible for the ultimate command decision authority for all unit activities and operations which affect the safety of the plant, site personnel, and/or the general public. A management directive to this effect, signed *by the corporate officer with direct responsibility for the plant shall be reissued to all site/station personnel on an annual basis.

5.1.3 The Control Room Supervisor (CRS) shall be responsible for the Control Room command function. A management directive to this effect, signed by the corporate officer with direct responsibility for the plant, shall be issued annually to all site/station personnel. The confines of the Control Room Area shall be defined as depicted in the Licensee Controlled Specification (LCS). During any absence of the CRS from the Control. Room Area while the Unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator's (SRO) license shall be designated to assume the Control Room command function. During any absence of the CRS from the Control Room Area while the Unit is in MODE 5 or 6, an individual with an'active SRO license or Reactor Operator.'s license shall be designated to assume the Control Room command function.

SAN ONOFRE--UNIT 2 5.0-1 Amendment No.207

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for-unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These relationships, including the plant-specific titles of those personnel fulfilling the responsibilities for the positions delineated in these Technical Specifications, are documented in the UFSAR.

b. The corporate officer with direct responsibility for the plant shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the-plant.

c. A specified corporate officer (or officers) shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the 'operating staff and those who carry out health-physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

(continued)

SAN ONOFRE-UNIT 2 5.0-2 Amendment No. 207

Organization 5.2 5.2 Organization (continued) 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 unit when a reactor is operating in MODES 1, 2, 3, or 4.

With both units shutdown or defueled, a total of three non-Licensed operators are required for thetwo units.

b. At least one licensed Reactor Operator (RO) shall be in the Control Room when fuel is-in the-reactor. In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator (SRO) shall be in the Control Room Area.

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5..2.2.a 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.

d. A radiation protection technician shall be on site when fuel is

.in 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.

e. Administrative controls shall be developed and implemented 'to limit the working hours of personnel who perform safety-related functions (e.g.,.senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.

Any deviation from the working hour guidelines s-hall be authorized in advance by the cognizant corporate officer, or designees, in accordance with approved administrative procedures, or by higher 'levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

(continued)

SAN ONOFRE-UNIT 2 5.0-3 Amendment No. 207

Organi zat ion 5.2 5.2 Organization (continued) 5.2.2 UNIT STAFF (continued)

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the cognizant corporate officer, or designees, to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines shall not be authorized.

f. The Manager, Plant Operations (at time of appointment), Shift I Managers, and Control Room Supervisors shall hold a Senior Reactor Operator's license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the Unit. The STA shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in-plant design and in the response and analysis of the plant for transients and accidents.

(continued)

SAN ONOFRE-UNIT 2 5.0-4 Amendment No. 207

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 a) the radiation protection manager who shall meet or exceed the I qualifications of Regulatory Guide 1.8, September 1975, and b) multi-discipline supervisors who shall meet or exceed the qualifications listed below.

In addition, the Shift Technical Advisor shall meet the qualifications specified by the Commission- Policy Statement on Engineering Expertise on Shift.-

Multi-discipline supervisors shall meet or exceed the following qualifications:

a. Education: Minimum of a high school diploma or equivalent.

b. Experience: Minimum of four years of related technical experience which shall include three years power plant experience of which one year is at a nuclear plant.

c. Training: Complete the multi-discipline supervisor training program.

SAN ONOFRE-UNIT 2' 5.0-5 Amendment No. 207

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2 Programs and Manuals The following programs and manuals Shall be established, implemented, and maintained.

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program;

b. The ODCM shall also contain the Radioactive Effluent Controls required by Specification 5.5.2.3 and the Radiological Environmental Monitoring programs required by the LCS, and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 5.7.1.2 and Specification 5.7.1.3.

5.5.2.1.1 Licensee-initiated changes to the ODCM:

a. Shall -be documented and records of reviews performed shall be retained. This documentation shall contain:

1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I,.and not, adversely impacd the accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed and found acceptable.

b. Shall become effective upon review and approval by the corporate officer with direct responsibility for the plant or designee.

(continued)

SAN ONOFRE--UNIT 2 5.0-8 Amendment No. 207

High Radiation Area 5.8 5.8. High Radiation Area (continued) 5.8.2 in addition, areas that are accessible to personnel and that have radiation levels greater than 1.0 rem (but less than 500 rads at 1 meter) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source, or from any, surface penetrated by the radiation, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift manager on duty or radiation protection supervisor. Doors shall remain locked except during periods of access by personnel under an approved REP that. specifies the dose rates in theimmediate work areas and the maximum allowable stay time for individuals in that area. In lieu of a stay time specification on the REP, direct or remote continuous surveillance. (such as closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could result in radiation doses greater than 1.0 rem in 1hour, and that are within large areas where no enclosure exists to enable locking and where no enclosure can be reasonably constructed around the individual area shall be barricaded and conspicuously posted. A flashing light shall be activated as a warning device whenever the dose rate in such an area exceeds or is expected to exceed 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from. the radiation source or from any surface penetrated by the radiation.

SAN ONOFRE--UNIT 2 5.0-31 Amendment No. 207

(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and -use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysts Report, as supplemented and amended; (4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to.

receive, possess, and use at any time any byproduct, source and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any 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; and (6) SCE. pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 3 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 Southern California Edison Company (SCE) is authorized to o erate the facility at reactor core power levels not in excess of Mull power (3438 megawatts thermal).-

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 199. are hereby Incorporated In the license.

Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 199

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs . .....

2.1,1.1 In MODES 1 and 2. departure from nucleate boiling ratio (DNBR) shall be maintained at z,1.31.

2.1.1.2 In MODES 1 and 2, peak fuel centerline temperature shall be maintained at < 5080'F, decreasing by 58°F per 10,000 MWD/MTU and adjusted for burnable poison per CENPD-382-P-A.

2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1., 2, 3, 4, and 5, the RCS pressure shall be maintained.

at

• 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2.i's violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

SAN ONOFRE--UNIT 3 2.0-1 Amendment No.1.99

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The corporate officer with direct responsibility for the plant shall be responsible for overall unit operation and maintenance of Units 2 and 3 at San Onofre Nuclear Generating Station, and all site support functions.. He shall delegate in writing the succession to this responsibility during his. absence.

5.1.2 The Shift Manager shall be responsible for the ultimate command decision authority for all unit activities and operations which affect the safety of the plant, site personnel, and/or the general public. A management directive to this effect, signed by the corporate officer with direct responsibility for the plant shall be reissued to all site/station personnel on an annual basis.

5.1.3 The Control Room Supervisor (CRS) shall be responsible for the Control Room command function. A management directive to this effect, signed by the corporate officer with direct responsibility.

for the plant, shall be issued annually to all site/station personnel. The confines of the Control Room Area shall be defined as depicted in the Licensee Controlled Specification (LCS). During any absence of the CRS from the Control Room Area while the Unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator's (SRO) license shall be designated, to assume the Control Room command function. During any absence of the CRS from the Control Room Area while the Unit is in MODE 5 or 6, an individual with an' active SRO license or Reactor Operator's license shall be designated to assume the Control Room command function.

SAN ONOFRE--UNIT 3 5.0-1 Amendment No. 19 9 -

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite-Organizations-...... ....

Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting-the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These relationships, including the plant-specific titles of those personnel fulfilling the responsibilities for the positions delineated in these Technical Specifications, are documented in the UFSAR.

b. The corporate officer with direct responsibility for the plant shall be responsible for overall unit safe operation .and shall have control over those onsite activities necessary for safe operation and maintenance of the-plant.

c. A specified corpo.rate officer (or officers) shall havi corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure'nuclear.

safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom toensure their independence from operating pressures.

(continued)

SAN ONOFRE--UNIT 3.. 5.0-2 Amendment No. 199

Organi zation 5.2 5.2 Organization (continued) 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 unit when a reactor is operating in.MODES 1, 2, 3, or 4.

With both units shutdown or defueled, a total of three non-Licensed operators are required for the two units.

b. At least one licensed Reactor Operator (RO) shall be in the Control Room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2,. 3 or 4, at least one licensed Senior Reacto.r Operator (SRO) shall be in the Control Room Area.

c. Shift crew composition may be less. than the minimumrequirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a 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.

d. A radiation protection technician shall be on site when fuel is in 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.

e. Administrative controls shall be developed and implemented to limit-the working hours of personnel who perform safety-related functions (e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines-on working hours that ensure-that adequate shift coverage is maintained without routine heavy use of overtime for individuals.

Any deviation from the working hour guidelines shall be authorized in advance by the cognizant corporate officer, or designees, in accordance with.approved administrative procedures, or by higher levels of management, in accordance with. established procedures and with documentation of the basis for granting the deviation.

(continued)

SAN ONOFRE-UNIT 3 5.0-3 Amendment No.199

Organi zati on 5.2 5.2 Organization (continued) 5.2.2 UNIT STAFF (conti nued)

_Cootrols shall be included in the procedures such that individual overtime shall be reviewed monthly by the- c6ghniznt corporate-officer, or designees, to ensure that excessive hours have not been I - -

assigned. Routine deviation from the above guidelines shall not be authorized.

f. The Manager, Plant Operations (at time of appointment), Shift I Managers, and Control Room Supervisors shall hold a Senior Reactor I Operator's license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plantanalysis with regard to the safe operation of the unit. The STA shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline *with specific training in plant design and in the response and analysis of the plant for transients and accidents.

(continued)

SAN ONOFRE--UNIT 3 5.0-4 Amendment No. 199

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 a) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8. September 1975, and b) multi-discipline, supervisors who shall meet or exceed the qualifi-cations listed below.

In addition, the Shift Technical Advisor shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Multi-discipline supervisors shall meet or exceed the following requirements:

a. Education: Minimum of a high school diploma or equivalent.

b. Experience: Minimum of.four years of related technical experience which shall include three years power plant experience of which one year is at a nuclear plant.

c. Training: Complete the multi-discipline supervisor training program.

SAN ONOFRE--UNIT 3 5.0-5 'Amendment No. 19.9

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2 Programs and Manuals The followi.ng programs and manuials shall be established, implemented, and maintained.

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental. Monitoring Program;

b. The ODCM shall also contain the Radioactive Effluent Controls required by Specification 5.5.2.3 and the Radiological Environmental Monitoring programs 'required by the LCS, and descriptions of the information that should be -included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 5.7.1.2 and Specification 5.7.1.3.

5.5.2.1.1 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentationshall contain:

1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

2. A determination that the change(s) maintain the levels of radioactive effluent controlCFRrequire'd by 1I0 CFR 20.106, 40 CFR 190. 10 50.36a, and 10 CFR 50, Appendix I, and not adversely- impact the accuracy or re liability of effluent, dose, Or setpoint calculations.

'3. Documentation of the fact that the change has been reviewed and found acceptable.

b. Shall become effective upon review and approval by the co*-porate officer with direct responsibility for the plant or designee.

(continued)

SAN ONOFRE-UNIT 3 5.0-8 Amendment No. 199

High Radiation Area 5.8 5.8. High Radiation Area (continued) 5.8.2 In addition, areas that are accessible to personnel and that have

...- - radiation lev.]ls-greater than 1.* rem (but less than 500 rads at I meterý)_

in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source, or from any surface penetrated by the radiation, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift manager on duty or radiation protection supervisor. Doors shall remain locked except during periods of access by personnel under an approved REP that specifies the dose rates in the immediate work areas and the maximum allowable stay'time for individuals in that area. In-lieu of a stay time specification on the REP, direct or remote continuous surveillance (such as closed circuit TV cameras) may be made by personnel qualified. in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could result in radiation doses greater than 1.0 rem in I hour, and that are within large areas, where no enclosure exists to enable locking and where no enclosure can be reasonably constructed around the individual area shall be barricaded and conspicuously posted. A flashing light shall be activated as a warning device whenever the dose rate in such an area exceeds or is expected to exceed 1.0 rem in 1. hour at 30 cm from the radiation source or from any surface penetrated by the radiation.

SAN ONOFRE--UNIT 3 5.0-31 Amendment No. 199