ML18011A634

Retyped Proposed Radiological Effluent TSs

ML18011A634
Person / Time
Site:	Harris
Issue date:	11/03/1994
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A633	List: ML18011A632 ML18011A634
References
NUDOCS 9411150004
Download: ML18011A634 (41)

Text

ENCLOSURE SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RADIOLOGICALEFFLUENT TECHNICAL SPECIFICATIONS RETYPED TECHNICAL SPECIFICATION PAGES P...,

941115OOO4 ADOCK 05000400 94110'DR PDR

INDEX DEFINITIONS SECTION PAGE 1.32 SITE BOUNDARY . 1-5 1.33 SLAVE RELAY TEST 1-6 1.34 (DELETED) 1-6 I 1.35 SOURCE CHECK 1-6 1.36 STAGGERED TEST BASIS 1-6 1.37 THERMAL POWER . 1-6 1.38 TRIP ACTUATING DEVICE OPERATIONAL TEST 1-6 1.39 UNIDENTIFIED LEAKAGE 1-6 1.40 UNRESTRICTED AREA . 1-6 1.41 VENTILATION EXHAUST TREATMENT SYSTEM 1-7 1.42 VENTING . 1-7 TABLE 1.1 FRE(UENCY NOTATION 1-8 TABLE 1.2 'PERATIONAL MODES . 1-9 SHEARON HARRIS - UNIT 1 Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE TABLE 3.3-6 RADIATION MONITORING INSTRUHENTATION FOR PLANT OPERATIONS . 3/4 3-51 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS . 3/4 3-54 Movable Incore Detectors . . . . . . . . . . . . 3/4 3-56 Seismic Instrumentation 3/4 3-57 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION . 3/4 3-58 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-59 Meteorological Instrumentation . . . . . . . . . . . 3/4 3-60 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION 3/4 3-61 TABLE 4.3-5 METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-62 Remote Shutdown System . 3/4 3-63 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . 3/4 3-64 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-65 .

Accident Monitoring Instrumentation 3/4 3-66 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-68 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . 3/4 3-70 TABLE 3.3-11 (DELETED) 3/4 3-73 Hetal Impact Monitoring System . . 3/4 3-74 (DELETED) 3/4 3-75 Explosive Gas Monitoring Instrumentation . 3/4 3-82 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3/4 3-83 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-86 TABLE 3/4.3.4 TURBINE OVERSPEED PROTECTION . 3/4 3-89 SHEARON HARRIS - UNIT 1 vi Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION PAGE 3 4.11 RADIOACTIVE EFFLUENT 3/4.11.1 LIQUID EFFLUENTS (DELETED) 3/4 11-1 Liquid Holdup Tanks . 3/4 11-7 3/4.11.2 GASEOUS EFFLUENTS (DELETED) ~ ~ ~ ~ ~ ~ 3/4 11-8 Explosive Gas Mixture 3/4 11-15 Gas Storage Tanks . . 3/4 11-16 3/4.11.3 (DELETED) 3/4 11-17 3/4.11.4 (DELETED) 3/4 11-19 3 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (DELETED) 3/4 12-1 3/4.12.2 (DELETED) 3/4 12-1 3/4.12.3 (DELETED) 3/4 12-1 SHEARON HARRIS - UNIT 1 X11 Amendment No.

INDEX BASES SECTION PAGE 3 4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS 8 3/4 10-1 3/4.10.3 PHYSICS TESTS . B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS . B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN . B 3/4 10-1 3 4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS . B 3/4 11-2 3/4.11.3 (DELETED) B 3/4 11-2 3/4.11.4 (DELETED) B 3/4 11-2 3 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (DELETED) B 3/4 12-1 3/4.12.2 (DELETED) B 3/4 12-1 3/4.12.3 (DELETED) 8 3/4 12-1 SHEARON HARRIS - UNIT 1 XV1 Amendment No.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.3 CORPORATE NUCLEAR SAFETY SECTION 0

F unct 1 on i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ 6-11 0 rgan1zat1on...............................................

~

+ ~

6-11 R eview... ................................................. 6-12 R ecords.................................................... 6-13 6.5.4 CORPORATE EQUALITY ASSURANCE AUDIT PROGRAM

'4 Auul t d ts A

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ it ~ ~ ~ ~ ~ ~ ~ 6-14 R ecords.................................................... 6-15 Authority.................................................. 6-15 6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM................ 6-15 6.6 REPORTABLE EVENT ACTION...................................... 6-15

6. 7 SAFETY L IHIT VIOLATION....................................... 6-16 6.8 PROCEDURES AND PROGRAMS...................................... 6-16

6. 9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS................................ 6-20 S tartup Report......................;...................... 6-20 Annual Reports............................................. 6-20 Annual Radiological Environmental Operating Report......... 6-21 Annual Radioactive Effluent Release Report................. 6-22 Monthly Operating Reports.................................. 6-23 Core Operating Limits Report............................... 6-24 6.9.2 SPECIAL REPORTS.....................-.................. 6-24 6.10 RECORD RETENTION............................................ 6-24 6.11 RADIATION PROTECTION PROGRAM................................ 6-26 6.12 HIGH RADIATION AREA........ 6-26.

6. 13 PROCESS CONTROL PROGRAM PCP ..........................-.... 6-27 SHEARON HARRIS - UNIT 1 X1X Amendment No.

j INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.14 OFFSITE DOSE CALCULATION MANUAL ODCM . . . . . . . . . . . 6-27

~EE DELETE ......................... E EE SHEARON HARRIS - UNIT 1 XX Amendment No.

DEFI ITIONS 0

MASTER RELAY TEST

1. 18 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER S OF THE PUBLIC 1.19 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from I radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCH shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9. 1.3 and 6.9. 1.4.

OPERABLE - OPERABILITY 1.21 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE l.'22 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

SHEARON HARRIS - UNIT 1 Amendment No.

DEFI ITIONS PROCESS CONTROL PROGRAM 1.25 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. I PURGE - PURGING 1.26 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

UADRANT POWER TILT RATIO 1.27 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.28 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2775 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.29 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter'xceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.30 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.32 For these Specifications, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SHEARON HARRIS - UNIT 1 1-5 Amendment No.

DEFI ITIONS SLAVE RELAY TEST 1.33 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION 1.34 Deleted from Technical Specifications and relocated to the PCP.

SOURCE CHECK 1.35 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.36 A STAGGERED TEST BASIS shall consist of:

a~ A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval; THERMAL*POWER 1.37 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.40 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

SHEARON HARRIS - UNIT 1 1-6 Amendment No.

INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION Specification 3/4.3.3.10 has been deleted from Technical Specifications and has been relocated to the ODCM.

Pages 3/4 3-76 through 3/4 3-81 have been deleted.

SHEARON HARRIS - UNIT 1 3/4 3-75 Amendment No.

l INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table )

3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3. 11.2.5 are not exceeded. I I

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

'a ~ With an explosive gas effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b. With the number of OPERABLE explosive gas monitoring I instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days, and if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3. 11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

'ote: The radioactive gaseous effluent monitoring portions of Specification 3/4.3.3. 11 have been deleted from Technical Specifications and have been relocated to the 00CM.

SHEARON HARRIS - UNIT 1 3/4 3-82 Amendment No.

TABLE 3.3-13 EXPLOSIYE GAS MONITORING INSTRUMENTATION H IN IHUH CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. GASEOUS WASTE PROCESSING SYSTEM--HYDROGEN

'ND OXYGEN ANALYZERS

a. Recombiner Outlet Hydrogen Honitor 1/recombiner 50

b. Recombiner Outlet Oxygen Honitor 1/recombiner 48

c. Compressor Discharge Oxygen Monitor 1 48

TABLE 3.3-13 Continued TABLE NOTATIONS

• . During GASEOUS WASTE PROCESSING SYSTEM operation ACTION STATEMENTS ACTION 45 (NOT USED)

ACTION 46 (NOT USED)

ACTION 47- (NOT USED)

ACTION 48 With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.

ACTION 49 (NOT USED)

ACTION 50 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner.

ACTION 51 (NOT USED)

ACTION 52 (NOT USED)

SHEARON HARRIS - UNIT 1 3/4 3-85 Amendment No.

TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS ANALOG I KI CHANNEL MODES FOR WHICH CA CHANNEL CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST E tRED

1. GASEOUS WASTE PROCESSING SYSTEM--

HYDROGEN AND OXYGEN ANALYZERS Q

CCD CD

a. Recombiner Outlet Hydrogen Q(4)

Monitor

b. Recombiner Outlet Oxygen Q(5)

CA I

Monitor CO

'4 c. Compressor Discharge Oxygen Q(5)

CD Monitor Vl CO CD CD

TABLE 4.3-9 Continued TABLE NOTATIONS

• During GASEOUS WASTE PROCESSING SYSTEM operation.

(I) (NOT USED)

(2) .(NOT USED)

(3) (NOT USED)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing hydrogen and nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing oxygen and nitrogen.

SHEARON HARRIS - UNIT I 3/4 3-88 Amendment No.

3 4.11 RADIOACTIVE EFFLUENTS 3 4.11.1 LI UID EFFLUENTS Specifications 3/4. 11.1.1, 3/4. 11. 1.2 and 3/4.11. 1.3 have been deleted from Technical Specifications and relocated to the ODCM.

Pages 3/4 11-2 through 3/4 11-6 have been deleted.

SHEARON HARRIS - UNIT 1 3/4 11-1 Amendment No.

RADIOACTIVE EFFLUENTS 0

LI UID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11. 1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases:

a. Outside temporary tank, excluding demineralizer vessels and liners used to solidify or to dewater radioactive wastes.

APPLICABILITY: At all times.

ACTION:

'a ~ With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9. 1.4.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 11.1.4 The'uantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents within 7 days following any addition of radioactive material to the tank.

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

SHEARON HARRIS - UNIT 1 3/4 11-7 Amendment No.

RADIOACTIVE EFFLUENTS 3 4. 11.2 GASEOUS EFFLUENTS Specifications 3/4.11.2.1, 3/4.11.2.2, 3/4.11.2.3 and 3/4.11.2.4 have been deleted from Technical Specifications and relocated to the ODCH.

Pages 3/4 11-9 through 3/4 11-14 have been deleted.

SHEARON HARRIS - UNIT 1 3/4 11-8 Amendment No.

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 1.05 x 10'uries of noble gases (considered as Xe-133 equivalent).

APPLICABILITY: At al l times.

ACTION:

a ~ Mith the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release )

Report, pursuant to Specification 6.9. 1.4.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.

SHEARON HARRIS - UNIT 1 3/4 11-16 Amendment No.

RADIOACTIVE EFFLUENTS 3 4.11.3 SOLID RADIOACTIVE WASTES Specification 3/4.11.3 has been deleted from Technical Specifications and relocated to the PCP.

Page 3/4 11-18 has been deleted.

SHEARON HARRIS - UNIT 1 3/4 11-17 Amendment No.

RADIOACTIVE EFFLUENTS 3 4.11.4 TOTAL DOSE Specification 3/4. 11.4 has been deleted from Technical Specifications and relocated to the ODCH.

SHEARON HARRIS - UNIT 1 3/4 11-19 Amendment No.

3 4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING Specifications 3/4.12. 1, 3/4.12.2 and 3/4. 12.3 have been deleted from Technical Specifications and relocated to the ODCM.

Pages 3/4 12-2 throUgh 3/4 12-14 have been deleted.

SHEARON HARRIS - UNIT 1 3/4 12-1 Amendment No.

INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM Continued This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

3 4.3.3.'6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that suffi-cient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," Hay 1983 and NUREG-0737, "Clarification of THI Action Plan Requirements," November 1980.

3 4.3.3.7 DELETED 3 4.3.3.8 DELETED 3 4.3.3.9 METAL IMPACT MONITORING SYSTEM The OPERABILITY of the Metal Impact Monitoring System ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components. The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1. 133, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," Hay 1981.

3 4.3.3. 10 DELETED SHEARON HARRIS - UNIT 1 B 3/4 3-5 Amendment No.

INSTRUMENTATION BASES 3 4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation provides for monitoring and controlling the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE TREATMENT SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3 4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

SHEARON HARRIS - UNIT 1 B 3/4 3-6 Amendment No.

3 4.11 RADIOACTIVE EFFLUENTS BASES 3 4.11.1 LI UID EFFLUENTS 3 4.11.1.1 DELETED 3 4.11.1.2 DELETED 3 4.11.1.3 DELETED 3 4.11.1.4 LI UID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls'capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3 4.11.2 GASEOUS EFFLUENTS 3 4.11.2.1 DELETED 3 4. 11.2.2 DELETED 3 4. 11.2.3 DELETED 3 4. 11.2.4 DELETED 3 4.11.2.5 EXPLOSIVE GAS HIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the GASEOUS RADWASTE TREATHENT SYSTEH downstream of the hydrogen recombiners is maintained below the flammability limits of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of oxygen to reduce the concentration below the flammability limits. Haintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the. requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

SHEARON HARRIS - UNIT 1 B 3/4 11-1 Amendment No.

RADIOACTIVE EFFLUENTS BASES 3 4.11.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification. Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, "Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

3 4.11.3 DELETED 3 4.11.4 DELETED Pages B 3/4 11-3 through B 3/4 11-6 have been deleted.

SHEARON HARRIS - UNIT 1 B 3/4 11-2 .Amendment No.

3 4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3 4.12.1 DELETED 3 4.12.2 DELETED 3 4. 12.3 DELETED Page B 3/4 12-2 has been deleted.

SHEARON HARRIS - UNIT 1 8 3/4 12-1 Amendment No.

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued

h. Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCH, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCH)

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20. 1001 - 20.2402,

3) Honitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODCH,

4) 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 Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCH at least every 31 days,

6) Limitations on the operability and use of the'iquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5. 1-1) shall be limited to the following:

a. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and

b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to a dose rate of 1500 mrem/yr to any organ.

SHEARON HARRIS - UNIT 1 6-19a Amendment No.

C ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS Continued

h. Radioactive Effluent Controls Pro ram Cont.

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

i. Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accor'dance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that

'modifications to the monitoring program are made if required by the results of this census, and

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample

'atrices are performed as part of the quality assurance program for environmental monitoring.

SHEARON HARRIS - UNIT 1 6-19b Amendment No.

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ADMINISTRATIVE CONTROLS ANNUAL REPORTS Continued film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions;

b. The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) cleanup flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) graph of the I-131 concentration (yCi/gm) and one other radio-iodine isotope concentration (yCi/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) the time duration when the specific activity of the reactor coolant exceeded the radioiodine limit.

c. Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) and safety valves.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.3 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before Hay 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCH and (2) Sections IV.B.2, IY.B.3, and IV.C of Appendix I to 10 CFR Part 50.

SHEARON HARRIS - UNIT 1 6-21 Amendment No.

ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9. 1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section-IV.B. 1 of Appendix I to 10 CFR Part 50.

SHEARON HARRIS - UNIT 1 6-22 Amendment No.

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ADMENISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9. 1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Hanagement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

SHEARON HARRIS - UNIT 1 6-23 Amendment No.

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ADMINISTRATIVE CONTROLS RECORD RETENTION Continued effective at specified times and gA records showing that these procedures were followed; I

o. Records of facility radiation and contamination surveys; and I

p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11. 1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12. 1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area; or

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such'areas with this monitoring device may be made after the dose rate levels in the area have been estab-lished and personnel have been made knowledgeable of them; or

c. An individual qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the, area and who shall perform periodic radiation surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6. 12.2 In addition to the requirements of Specification 6. 12. 1, accessible areas with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates, shall be rovided with locked doors to prevent unauthorized entry, and the keys shall e maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1 6-26 Amendment No.

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.s) q (y 4P ADMINISTRATIVE CONTROLS HIGH RADIATION AREA Continued and/or health physics supervision. Doors shall remain locked except during.

periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous sur-veillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. During emergency situations that involve personal injury or actions taken to prevent major equipment damage, continuous surveillance and radiation monitoring of the work area by a qualified individual may be substituted for the routine RWP procedure.

For accessible individual high radiation areas, with radiation levels of greater than 1000 mR/h, that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

6. 13 PROCESS CONTROL PROGRAM PCP Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.3p. This documentation shall contain:

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

2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the PNSC and the approval. of the Plant General Manager.

6. 14 OFFSITE DOSE CALCULATION MANUAL ODCM Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6. 10.3p. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and SHEARON HARRIS - UNIT 1 i 6-27 Amendment No.

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ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL Continued

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PNSC and the approval of the Plant General Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCH as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCH was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

6. 15 Specification 6.15 has been deleted from Technical Specifications and has been relocated to the ODCH and PCP, as appropriate.

Page 6-29 has been deleted.

SHEARON HARRIS - UNIT 1 6-28 Amendment No.