ML20203K279

Proposed Tech Specs,Allowing Relocation of Fire Protection Requirements to FSAR & Revising License Conditions Re Fire Protection

ML20203K279
Person / Time
Site:	Hatch
Issue date:	07/23/1986
From:	GEORGIA POWER CO.
To:
Shared Package
ML20203K278	List: ML20203K276 ML20203K279
References
TAC-62123, TAC-62124, NUDOCS 8608070147
Download: ML20203K279 (20)

Text

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GeorgiaPower d ENCLOSURE 3 NRC DOCKETS 50-321 AND 366 OPERATING LICENSES DPR-57 AND NPF-5 EDWIN I. HATCH NUCLEAR PLANT-UNITS 1 AND 2 CHANGES TO FIRE PROTECTION TECHNICAL SPECIFICATIONS AND LICENSE CONDITIONS TECHNICAL SPECIFICATIONS CHANGES The proposed changes to Technical Specifications (Appendix A to Operating Licenses DPR-57 and NPF-5) would be incorporated as follows:

Remove Page Insert Page UNIT 1:

Y Y 1.0-7 1.0-7 3.13-1 thru 3.13-12 3.13-1 thru 3.13-12 6-la 6-la 6-8 6-8 6-18 6-18 UNIT 2:

Y Y VIII VIII XI XI XIII XIII 3/4 3-59 3/4 3-59 3/4 3-60 3/4 3-60 3/4 7-21 thru 3/4 7-30 3/4 7-21 thru 3/4 7-30 B 3/4 3-4 8 3/4 3-4 B 3/4 7-3 B 3/4 7-3 B 3/4 7-4 8 3/4 7-4 6-1 a 6-1 a 6-7 6-7 6-17 6-17 2832N 7/23/86 8600070147 860725 PDR ADOCK 05000321 roons P PDR

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

.3.9. AUXILIARY ELECTRICAL SYSTEMS (CONT'0) 4.9. AUXILIARY ELECTRICAL SYSTEMS (CONT'0) i

8. Requirements for Continued 8. Requirements for Continued 3.9-4  !

Operation With Inoperable Components Operation Without Inoperable i Components C. Diesel Generator Requirements 3.9-6 (Reactor in the Shutdown or Refuel Mode) 3.10. REFUELING 4.10. REFUELING 3.10-1 A. Refueling Interlocks A. Refueling Interlocks 3.10-1

8. Fuel Loading 3.10-1 C. Core Monitoring During Core C. Core Monitoring During Core 3.10-2 Alternations Alternations D. Spent Fuel Pool Water Level D. Spent Fuel Pool Water Level 3.10-2 E. Control Rod Drive Maintenance E. Control Rod Drive Maintenance 3.10-2 F. Reactor Building Cranes F. Reactor Building Cranes 3.10-4 G. Spent Fuel Cask Lifting G. Spent Fuel Cask Lifting 3.10-5 Trunnions and Yoke Trunnions and Yoke H. Time Limitation 3.10-5 3.11. FUEL R005 4.11. FUEL RODS 3.11-1 A. Average Planar Linear Heat A. Average Planar Linear Heat 3.11-1 Generation Rate (APLHGR) Generation Rate (APLHGR)

8. Linear Heat Generation Rate B. Linear Heat Generation Rate 3.11-1 (LHGR) (LHGR)

C. Minimum Critical Power C. Minimum Critical Power 3.11-1 Ratio (MCPR) Ratio (MCPR) 3.12. MAIN CONTROL ROOM ENVIRONMENTAL 4.12. MAIN CONTROL ROOM ENVIRONMENTAL 3.12-1 SYSTEM SYSTEM A. Ventilation System Operability A. Ventilation System Tests 3.12-1

8. Isolation Valve Operability B. Isolation Valve 3.12-2 and Closing Time Testing C. Radiation Monitors C. Radiation Monitors 3.12-3

0. Shutdown Requirements 3.12-3 E. Chlorine Monitors E. Chlorine Monitors 3.12-3 HATCH - UNIT 1 v Proposed TS/0038q/175

r MM. Minimum Critical Power Ratio (MCPR) - Minimum Critical Power Ratio (MCPR) is the value of the critical power ratio associated with the most limiting assembly in the reactor core. Critical Power Ratio (CPR) is the ratio of that power in a fuel assembly, which is calculated to cause some point in the assembly to experience boiling transition, to the actual assembly operation power.

NN. Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate action to accomplish a protective function. A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action. Initiation of protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.

00. (Deleted)

PP. (Deleted)

QQ. Channel Calibration - A Channel Calibration is the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Functional Test. The Channel Calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

RR. Channel Functional Test - A Channel Functional Test shall be:

l a. Analog channels - the injection of a simulated signal into the

( channel as close to the primary sensor as practicable to verify

operability including alarm and/or trip functions.

b. Bistable Channels - the injection of a simulated signal into the channel sensor to verify operability including alarm and/or trip functions.

l SS. Fraction of Limiting Power Density (FLPD) - the ratio of the linear heat I

generation rate (LH6R) existing at a given location to the design LHGR for the bundle type. Design LHGRs are 18.5 KW/ft for 7x7 bundles and 13.4 KW/ft for 8x8 bundles.

TT. Core Maximum Fraction of Limiting Power Density (CMFLPD) - the CMFLPD is the highest value existing in the core of the FLPD.

HATCH - UNIT 1 1.0-7 Proposed TS/0030g/174

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HATCH - UNIT 1 3.13-1 through 3.13-12 Proposed TS/00374/175

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6.0 ADMINISTRATIVE CONTROLS

f. (Deleted)

g. Administrative procedures shall be developed and implemented to limit the working hours of Unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used or during extended periods of shutdown for refueling, major maintenance, or major plant modifications, the following guidelines shall De followed on a temporary basis:

(1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

(2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.

(3) A break of at least eight hours should be allowed between work 1 periods, incluriing shif t turnover time.

(4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the l entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the General Manager-Plant Hatch or his deputy of higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls i shall be included in the procedures such that individual overtime shall be reviewed monthly by the General Manager-Plant Hatch or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

i HATCH - UNIT 1 6-la Proposed TS/0031g/174

f ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

1. Review of the Security Plan and implementing procedures and shall submit recommended changes to the SRB.

j. Review of the Emergenc.y Plan and implementing procedures and shall submit recommended changes to the SR8.

k. Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous effluents. Also included is the preparing and forwarding to the General Manager-Plant Hatch and the SR8 reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence.

1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL (00CM).

m. Review of proposed change (s) to plant systems and equipment to detemine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the i Manager-Nuclear Engineering and Chief Nuclear Engineer.

n. Review cf the Fire Protection Program and implementing procedures and shall submit recommended changes to the SRB.

AUTHORITY 6.5.1.7. The PRB shall:

1

a. Recommend in writing to the General Manager-Plant Hatch approval or l

disapproval of 1tems considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and the Safety Review Board of disagreement between the PR8 and the General Manager-Plant Hatch; however, the General Manager-Plant Hatch shall have responsibility for resolution of such disagreements pursuant to 6.1.1. above.

RECORDS ,

6.5.1.8. The Plant Review Board shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Manager of Nuclear Generation or Vice President and General Manager Nuclear Operations and the Safety Review Board.

HATCH - UNIT 1 6-8 Proposed TS/0031g/174

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l ADMINISTRATIVE CONTROLS

d. Abnormal degradation of systems other than those specified in 6.9.1.8.c. above designed to contain radioactive material resulting f rom the fission process.

SPECIAL REPORTS 6.9.2. Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified and for each activity shown in Table 6.9.2-1. Special reports for fire protection equipment operating and surveillance requirements shall be submitted, as required, by the Fire Hazards Analysis and its Appendix B requirements.

6.10. RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1. The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. ALL REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications,

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source r.atcria? of record.

6.10.2. The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

HATCH - UNIT 1 6-18 Proposed TS/0044q/192

r INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitoring Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incore Probe System 3/4 3-57 Chlorine Detectors 3/4 3-58 Radioactive Liquid Effluent Instrumentation i 3/4 3-60a Radioactive Gaseous Effluent Instrumentation 3/4 3-60f 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM 3/4 3-61 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 HATCH-UNIT 2 V Proposed TS/0032q/174

r INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System. . . . . . . . . . . . . . . 3/4 7-1 S e rv i c e Wa t e r Sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-3 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM. . . . . . . . . . . 3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . . . . 3/4 7-9 3/4.7.4 SNUBBERS................................................. 3/4 7-11 3/4.7.5 SEALED SOURCE CONTAMINATION.............................. 3/4 7-19 3/4.7.6 (Deleted) 3/4.7.7 (Deleted) 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-31 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources-Operating................................... 3/4 8-1 A.C. Sources-Shutdown.................................... 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating............................ 3/4 8-10 A.C. Di stributi on - Shutdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-12 D.C. Di stri buti on - Ope rati ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-13 D.C. Distribution - Shutdown............................. 3/4 8-16 A.C. Ci rcui ts Inside Prima ry Containment. . . . . . . . . . . . . . . . . 3/4 8-17 Primary Containment Penetration Conductor Overcurrent Protective Devices........................... 3/4 8-18 HATCH-UNIT 2 VIII Proposed TS/0032q/174

T INDEX BASES SECTION '

PAGE INSTRUMENTATION (Continued)

Remote Shutdown Monitoring B 3/4 3-3 Instrumentation Post-Accident Monitoring 8 3/4 3-4 Instrumentation Source Range Monitors B 3/4 3-4 Traversing Incore Probe System B 3/4 3-4 Cnlorine Detectors B 3/4 3-4 Radioactive Liquid Effluent i Instrumentation B 3/4 3-5 Radioactive Gaseous Effluent Instrumentation B 3/4 3-5 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM B 3/4 3-5 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION B 3/4 3-Sa 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems B 3/4 4-2 Operational Leakage B 3/4 4-2 3/4.4.4 CHEMISTRY B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY B 3/4 4-3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES B 3/4 4-6 HATCH-UNIT 2 XI Proposed TS/0032q/174

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INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS B 3/4 7-1 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM B 3/4 7-1 3/4.7.4 SNUBBERS B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION B 3/4 7-3 3/4.7.6 (Deleted) 3/4.7.7 (Deleted) 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH B 3/4 9-1 3/4.9.2 INSTRUMENTATION 8 3/4 9-1 3/4.9.3 CONTROL R0D POSITION B 3/4 9-1 l 3/4.9.4 DECAY TIME B 3/4 9-1 3/4.9.5 SECONDARY CONTAINMENT B 3/4 9-1 3/4.9.6 COMMUNICATIONS B 3/4 9-2 3/4.9.7 CRANE AND HOIST OPERABILITY B 3/4 9-2 3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE POOL B 3/4 9-2 3/4.9.9 WATER LEVEL - REACTOR VESSEL AND and WATER LEVEL - SPENT FUEL STORAGE 3/4.9.10 POOL B 3/4 9-2 3/4.9.11 CONTROL R00 REMOVAL B 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCULATION 8 3/4 9-3 HATCH-UNIT 2 XIII Proposed TS/0032q/174

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HATCH - UNIT 2 3/4 3-59 Proposed TS/0033q/175

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HATCH - UNIT 2 3/4 3-60 Proposed TS/0033q/175 I

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l HATCH - UNIT 2 3/4 7-21 through 3/4 7-30 Proposed TS/0034q/175 i

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r INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.6.4 POST-ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant param-eters to monitor and assess important variable following an accident.

3/4.3.6.5 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during startup. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.

3/4.3.6.6 TRAVERSING INCORE PROBE SYSTEM The OPERABILITY of the traversing incore probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector to be used and normalizing their respective outputs.

3/4.3.6.7 CHLORINE DETECTORS The OPERABILITY of the chlorine detectors ensures that an accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for control room personnel. Upon detection of a high concentration of chlorine the control room emergency ventilation system will automatically be placed in the isolation mode of operation to provide the required protection.

3/4.3.6.8 (Deleted)

HATCH - UNIT 2 B 3/4 3-4 Proposed TS/0035q/175

r PLANT SYSTEMS BASES 3/4.7.4 SNUB 8ERS (Continued)

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area,etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material. The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

Quantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage from sources excluded from the requirements of this specification is not likely to represent more than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.

3/4.7.6 (Deleted)

HATCH - UNIT 2 8 3/4 7-3 Proposed TS/0035q/175

PLANT SYSTEMS BASES 3/4.7.7 (Deleted) 3/4.7.8 SETTLEMENT OF CLASS 1 STRUCTURES In order to assure that settlement does not exceed predicted and allowable settlement values, a program has been established to conduct a survey at the site.

The allowable total and differential settlement values are based on original settlement predictions. In establishing these tabulated values, an assumption is made that pipe and conduit connections have been designed to safely withstand the stresses which would develop due to total and differential settlement.

i HATCH - UNIT 2 8 3/4 7-4 Proposed TS/0035q/175 l

r ADMINISTRATIVE CONTROLS

f. (Deleted)

g. Administrative procedures shall be developed and implemented to limit the working hours of Unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used or during extended periods of shutdown for-refueling, major maintenance, or major plant modifications, the following guidelines shall be followed on a temporary basis:

(1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

(2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.

(3) A break of at least eight hours should be allowed between work periods, including shift turnover time.

(4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the General Manager-Plant Hatch or his deputy of higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the General Manager-Plant Hatch or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

HATCH - UNIT 2 6-la Proposed TS/0036q/175

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, ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)  !

i. Review of the Security Plan and implementing procedures and shall submit recommended changes to the SRB.

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the SRB.

k. Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of I C1, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 C1 of noble gases or 0.02 Ci of radioiodines for gaseous effluents. Also included is the preparing and forwarding to the General Manager-Plant Hatch and the SRB reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence.

1. Review of changes to the PROCESS CONTROL PROGRAM and the 0FFSITE DOSE CALCULATION MANUAL (0DCM).

m.

Review of proposed change (s) to plant systems and equipment to determine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the Manager-Nuclear Engineering and Chief Nuclear Engineer.

n. Review of the Fire Protection Program and implementing procedures and shall submit recommended changes to the SRB.

AUTHORITY 6.5.1.7 The PRB shall:

a. Recommend in writing to the General Manager-Plant Hatch approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and the Safety Review Board of disagreement between the PRB and the General Manager-Plant Hatch; however, the General Manager-Plant Hatch shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The Plant Review Board shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsibility and authority provisions of these Technical Specifications. Copies shall be provided to the Manager of Nuclear Generation or the Vice President and General Manager Nuclear Operations and the Safety Review Board.

HATCH - UNIT 2 6-7 Proposed TS/0036q/175

. 0 ADMINISTRATIVE CONTROLS

d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.

SpECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. Special reports for fire protection equipment operating and surveillance requirements shall be submitted, as required, by the Fire Hazards Analysis and its Appendix B requirements.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related ,

to nuclear safety.

c. ALL REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1.

f. Records of radioactive shipments. .

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the unit Operating License:

a. Records and drawing changes reflecting unit design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

HATCH - UNIT 2 6-17 Proposed TS/0045q/195