ML20086F020
| ML20086F020 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/06/1995 |
| From: | Mark Miller NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086F022 | List: |
| References | |
| NUDOCS 9507120381 | |
| Download: ML20086F020 (19) | |
Text
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NUCLEAR REGULATORY COMMISSION 5
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company
{
(the licensee) dated February 16, 1994, as supplemented by letter 4
dated April 25, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized
)
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:
l l
9507120381 950706 PDR ADOCK 05000275 P
PDR l
i ;
i (2)
Technical Soecifications The Technical. Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 106, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of its date of issuance to be i
implemented within 90 days of issuance..
FOR THE NUCLEAR REGULATORY COMMISSION Melanie A. Miller, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 6, 1995 i
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a cto UNITED STATES y-L g
. j NUCLEAR REGULATORY COMMISSION
' s WASHINGTON, D.C. 3066dKm01
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 l
DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 105 i
License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Pacific Gas & Electric Company j
(the licensee) dated February 16, 1994, as supplemented by letter l
dated April 25, 1995, complies with the standards and requirements i
of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to read as follows:
. (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 105, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of its date of issuance to be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Melanie A. Miller, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 6, 1995 L
.=.
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 106 TO FACILITY OPERATING LICENSE NO. DPR-80 i
AND AMENDMENT N0. 105 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 l
Revise Appendix A Technical Specifications by removing the pages identified i
below and inserting the enclosed pages. The revised pages are identified by j
the captioned amendment number and contain marginal lines indicating the area of change.
Overleaf pages are provided to maintain document completeness.
f REMOVE INSERT x
x t
xi xi 3/4 0-2 3/4 0-2 3/4 7-10 3/4 7-10 3/4 7-18 3/4 7-18 t
3/4 7-19 3/4 7-20 t
3/4 7-21 l
3/4 7-22 f
3/4 7-23 t
3/4 7-23a 3/4 7-23b 3/4 7-24 3/4 7-25 l
3/4 7-26 3/4 7-37 l
3/4 7-38 3/4 7-40 B 3/4 0-3 B 3/4 0-3 8 3/4 7-3 B 3/4 7-3 8 3/4 7-4 B 3/4 7-4 8 3/4 7-5 B 3/4 7-6 B 3/4 7-7 B 3/4 7-8 6-21 6-21 4
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4 ELU g
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
/
SECTION
{g{
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 A C CUMU LATO RS............................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - 7,,, GREATER THAN OR EQUAL 70 350*F... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350*F..................
3/4 5-7 avg 3/4.5.4 DELETED 3/4.5.5 REFUELING WATER STORAGE TANK............................
3/4 5-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT Co nta i nment I ntegri ty...................................
3/4 6-1 I
Containment Leakage.....................................
3/4 6-2 Containment Air Locks...................................
3/4 6 5 Internal Pressure.......................................
3/4 6-7 Air Temperature.........................................
3/4 6-8 Containment Structural Integrity........................
3/4 6-9 Containment Ventilation System..........................
3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment spray System................................
3/4 6-11 Spray Additive Systes...................................
3/4 6-12 Containment Cooling Systas..............................
3/4 6-13 3/4.6.3 CONTAI NMENT I SOLATION VALYES............................
3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTROL
%droge n Analyz e rs /Moni tors.............................
3/4 6-17 Electric % drogen Recombiners...........................
3/4 6-18 DIABLO CANYON - UNITS 1 & 2 1x Amendment Nos. 73 & r2
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PEiE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves...........................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES.......
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.......................
3/4 7-3 Auxil i ary Feedwater System.............................. 3/4 7-4 Auxiliary Feedwater Source..............................
3/4 7-6 Specific Activity.......................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.............................
3/4 7-8 Main Steam Line Isol ation Val ves........................
3/4 7-9 Steam Generator 10% Atmospheric Dump Valves.............
3/4 7-9a Main Feedwater Regulating Bypass and Isolation Valves...
3/4 7-9b 3/4.7.2 DELETED l
3/4.7.3 VITAL COMP 0NENT COOLING WATER SYSTEM....................
3/4 7-11 3/4.7.4 AUXILIARY SALTWATER SYSTEM..............................
3/4 7-12 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM.........................
3/4 7-13 3/4.7.6 AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM.....
3/4 7-16 3/4.7.7 DELETED l
3/4.7.8 DELETED DIABLO CANYON - UNITS I & 2 x
Unit 1 - Amendment 65,75,77,106 Unit 2 - Amendment 65,74,75,105
1 INDEX LIMITINGCONDITIONSFOROPERATIONANDSURVEILLANCERE0VIREMENTS SECTION 1%GE 3/4.7 PLANT SYSTEMS (continued) 3/4.7.11 DELETED l
3/4.7.12 ULTIMATE HEAT SINK......................................
3/4 7-39 3/4.7.13 DELETED g
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating...............................................
3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................
3/4 8-8 TABLE 4.8-2a LOAD SEQUENCING TIMERS - ESF TIMERS..................
3/4 8-9 TABLE 4.8-2b LOAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS........
3/4 8-10 Shutdown................................................
3/4 8-11 3/4.8.2 ONSITE POWER DISTRIBUTION 0perating...............................................
3/4 8-12 Shutdown................................................
3/4 8-14 3/4.8.3 D.C. SOURCES 0perating...............................................
3/4 8-15 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS....................
3/4 8-17 Shutdown................................................
3/4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Motor-0perated Valves Thermal Overload Protection and Bypass Devices......................................
3/4 8-19 Containment Penetration Conductor Overcurrent Protective Devices......................................
3/4 8-20 DIABLO CANYON - UNITS 1 & 2 xi Unit 1 - Amendment 55,75,70,106 Unit 2 - Amendment 55,74,78,105
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION c
3/4.9 REFUELING OPERATIONS 3/4 9-1 3/4.9.1 BORON CONCENTRATION.....................................
3/4 9-2 3/4.9.2 INSTRUMENTATION.........................................
3/4 9-3 3/4.9.3 DECAY TIME..............................................
3/4.9.4 CONTAINMENT PENETRATIONS................................
3/4 9-4 3/4 9-5 3/4.9.5 COMMUNICATIONS..........................................
3/4.9.6 MANIPULATOR CRANE.......................................
3/4 9-6 3/4.9.7 CRANE T RAVEL - FUEL HANDLING BUILDING...................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4 9-8 High Water Level........................................
3/49-9 Low Water Leve1.........................................
3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................
3/4 9-10 3/4.9.10 WAT ER LEVE L - RE ACTOR VESSEL............................
3/4 9-11 3/4 9-11 Fuel Assemblies.........................................
3/4 9-11a Control Rods............................................
3/4.9.11 WAT ER LEVE L - SPENT FUEL P00L...........................
3/4 9-12 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM...............
3/4 9-13 3/4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.......................
3/4 9-15 3/4.9.14 SPENT FUEL ASSEMBLY ST0 RAGE.............................
3/4 9-17 3/4.10 SPECIAL TEST EXCEPTIONS 3/4 10-1 3/4.10.1 SHUTDOWN MARGIN.........................................
3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS...
3/4 10-2 3/4.10.3 PHYSICS TESTS.........................................~..
3/4 10-3 3/4.10.4 POSITION INDICATION SYSTEM - SHVT00WN...................
3/4 10-4 DIABLO CANYON - UNITS 1 & 2 xii Amendment Nos. 39 & 38, 72 & 71
3/4 LIMXTING CONDITIONS FOR OPERATION Ahii SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION
- 3. 0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associat'ed ACTION requirements are not met within the specified time intervals.
If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
At least HDT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, a.
b.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
Where corrective measures are completed that permit operation under the ACTION,
requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to rieet the Limiting Condition for Operation.
Exceptions of these requirements are stated in the individual specifications.
This specification is not applicable in MODE 5 or 6.
i 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.
Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.
This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION statements.
Exceptions to these requirements sre stated in the individual specifications.
- 3. 0. 5 Limiting Conditions for Operation including the associated ACTION re-s quirements shall apply to each unit individually unless otherwise indicated as follows:
Whenever the Limiting Conditions for Operation refers to systems or a.
components which are shared by both units, the ACTION requirements will apply to both units simultaneously.
This will be indicated in the ACTION section; b.
Whenever the Limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and 4
Whenever certain portions of a specification contain operating param-c.
eters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.
DIABLO CANYON - UNITS 1 & 2 3/4 0-1 Amendment Nos. 55 and 54
APPLICABILITY SURVEILLANCE RE0VIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval defined by Specification 4.0.2 shall constitute non-compliance with the OPERABILITY-requirements for a Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps, valves, and snubbers shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i);
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA PERFORMING INSERVICE TERMIN0 LOGY FOR INSERVICE INSPECTION AND TESTING INSPECTION AND TESTING ACTIVITIES ACTIVITIES Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days I
Every 9 months At least once per 276 days Yearly or annually At least once per 366 days DIABLO CANYON - UNITS 1 & 2 3/4 0-2 Unit 1 - Amendment No. W,106 Unit 2 - Amendment No. H,105
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DIABLO CANYON - UNITS 1 & 2 3/4 7-10 Unit 1 - Amendment 'No.106' Unit 2 - Amendment No.105
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DIABLO CANYON - UNITS 1 & 2 3/4 7-18 Unit 1 - Amendment No. E,106 (Next page is 3/4 7-39)
Unit 2 - Amendment No. E,105 4
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PLANT SYSTEMS 3/4.7.12 ULTIMATE HEAT SINK
.IMITING CONDITION FOR OPERATION 3.7.12 The ultimate heat sink (UHS)* shall be OPERABLE with an inlet water temperature of less than or equal to 64'F.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
With the requirements of the above specification not satisfied, place a second vital component cooling water heat exchanger in service within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.12 The UHS shall be determined OPERABLE by verifying the inlet water tem-perture to be within its limit:
a.
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 the inlet water temperature is equal to or less than 60*F, or b.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the inlet water temperature is greater than 60'F but less than 62*F, or i
c.
At least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the inlet water temperature is equal to or greater than 62*F but less than or equal to 64'F.
i
- The UHS is common to both units.
l DIABLO CANYON - UNITS 1 & 2 3/4 7-39 l
Revised December 21, 1990 APPLICABILITY BASES surveillance interval was exceeded.
Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed.
The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance.
The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.
This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.
If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.
When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.
Surveillance Requirements do not have to be performed on inoperable equip-ment because the ACTION requirements define the remedial measures that apply.
However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status, i
DIABLO CANYON - UNITS 1 & 2 B 3/4 0-2a Amendment Nos. 55 and 54
APPLICABILITY BASES 4.0.4 This specification establishes the requirement that all applicable surve111ances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.
The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.
This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.
Under the provisions of this specification, the applicable Surveillance Requirem?nts must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.
When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.
4.0.5 This specification establishes the requirement that inservice inspection of ASME code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps, valves, and snubbers shall be performed in l
accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Commission.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
3 4.0.6 This specification delineates the applicability of the surveillance activities to Unit 1 and Unit 2 operations.
DIABLO CANYON - UNITS 1 & 2 B 3/4 0-3 Unit 1 - Amendment No. 55,106 Unit 2 - Amendment No. 64,105
r PLANT SYSTEMS BASES l
3 /4. 7. 3 VITAL COMPONENT COOLING WATER SYSTEM The OPERADILITY of the Vital Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.4 AUXILIARY SALTWATER SYSTEM The OPERABILITY of the Auxiliary Saltwater System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming & single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.5 CONTROL ROOM VENTILATION SYSTEM 1
The OPERABILITY of the Control Room Ventilation System ensures that:
(1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A,10 CFR Part 50.
Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
ANSI N510-1980 will be used as a procedural guide for surveillance testing.
DIABLO CANYON - UNITS 1 & 2 B 3/4 7-3 Unit 1 - Amendment No.106 Unit 2 - Amendment No.105
PLANT SYSTEMS BASES 3/4.7.6 AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM l
The OPERABILITY of the Auxiliary Building Safeguards Air Filtration System I
ensures that radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment. Operation of the system with the heaters operating to maintain low humidity for at least 10 continuous hours in a 31-day period is sufficient j
to reduce the buildup of moisture on the adsorbers and HEPA filters. The operation of this system and the resultant effect on offsite dosage I
l calculations were assumed in the safety analyses. ANSI N510-1980 will be used l
as a procedural guide for surveillance testing.
3/4.7.12 ULTIMATE HEAT SINK The OPERABILITY of the Component Cooling Water (CCW) System and the components that it cools is ensured if the CCW temperature remains equal to or less than 132'F during any condition assumed in the safety analysis. One CCW heat exchanger is required in service when the ocean temperature is 64*F or less.
Two CCW heat exchangers are required in service when the ocean temperature is greater than 64*F.
If the reactor coolant temperature is less than 350*F (MODE 4), one CCW heat exchanger in service is adequate even if the ocean temperature is greater than 64*F.
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l DIABLO CANYON - UNITS 1 & 2 B 3/4 7-4 Unit 1 - Amendment No. 66,106 Unit 2 - Amendment No. 65,105
ADMINISTRATIVE CONTROLS RE.C0RD RETENTION (Continued) 1.
Records of analyses required by the Radiological Environmental Monitoring Program; m.
Records of the service lives of all hydraulic and mechanical snubbers required by the Final Safety Analysis Report including the date at l
which the service life commences and associated installation and maintenance records; and n.
Records of secondary water sampling and water quality, o.
Records of reviews performed for changes made to the RADIOLOGICAL MONITORING AND CONTROLS PROGRAM, 0FFSITE DOSE CALCULATION PROCEDURE, ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE, and the PROCESS CONTROL PROGRAM.
6.11 RADIATION PROTECTION PROGRAM 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)(2) each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the l
radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance i
thereto shall be controlled by requiring issuance of work permits for radiation (WPR).
Individuals qualified in radiation platection procedures (e.g., Health Physics Technician) or personnel continuou:ly escorted by such individuals may be exempt from the WPR 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 which continuously indicates the radiation dose rate in the area; or b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated i
dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or DIABLO CANYON - UNITS 1 & 2 6-21 Unit 1 - Amendment No. 67,106 Unit 2 - Amendment No. 66,105
ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 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 shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the WPR.
6.12.2 In addition to the requirements of Specification 6.12.1, areas acces-sible to personnel 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 provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved WPR which shall specify the dose rate levels in the immediate work areas and the maximum allow-able stay time for individuals in that area.
In lieu of the stay time speci-fication of the WPR, direct or remote (such as closed circuit TV u meras) con-tinuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being per-formed within the area.
For individual high radiation areas accessible to personnel 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, conspicuously posted, and a flashing light shall be activiated as a warning device.
6.13 PROCESSCONTROLPROGRAM(PC3 l
6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
1)
Sufficient information to support the changt together with the j
appropriate analyses or evaluations justifying the change (s) and i
2)
A determination that the change will maintain the overall l
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 PSRC and the approval of the Plant Manager.
DIABLO CANYON - UNITS 1 & 2 6-22 Amendment Nos. 67 and 66 l
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