ML20044C330
| ML20044C330 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/16/1993 |
| From: | Cross J, Walt T PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303220220 | |
| Download: ML20044C330 (30) | |
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James E. Cross Vice President and Chief Nuclear Officer March 16,1993 Trojan Nuclear Plant Docket 50-344 License NPF-1 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sirs:
l Operational Requirements for the Permanently Defueled Condition at Troian Nuclear Plant The purpose of this correspondence is to transmit Portland General Electric's Operational Requirements for the Permanently Defueled Condition (attached). This report provides a listing of Trojan Technical Specifications and delineates their applicability to the defueled condition.
In addition, this report provides a brief discussion of additional administrative controls that have been established to suppen the permanently defueled condition.
l Portland General Electric will continue to comply with the Technical Specifications and administrative controls described in this report until such time as permanently defueled Technical Specifications are approved.
If you have any questions regarding the contents of this repon, please contact me, or Tom Walt of my staff.
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Sincerely, j
T. D. Walt l
for J. E. Cross Attachment 1
220078 l
9303220220 930316
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l PDR ADOCK 05000344
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PDR 121 SW Salmon Street, Portland, OR 97204 503/464-8897 J
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Dogument Control Desk i
March 16,1993 Page 2 c:
Mr. John B. Manin l
Regional Administrator, Region V
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U. S. Nuclear Regulatory Commission
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Mr. David Stewart-Smith State of Oregon Department ofEnergy t
Mr. Kenneth Johnston NRC Resident Inspector Trojan Nuclear Plant -
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a Trojan NuclearPlant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 1 of 28 OPERATIONAL REQUIREMENTS FOR TIIE DEFUELED CONDITION
- 1. ABSTRACT This report is a consolidated listing of Technical Specifications that remain applicable in the defueled condition, i. e., no fuel assemblies in the containment building. Additional administrative requirements are also delineated in this report.
II. INTRODUCTION The purpose of this document is to identify the operational requirements for the defueled conditicn. This document is also intended to provide a description of the philosophy used for establishing these operational requirements. It is intended that this document provide a l
consolidation of existing requirements only. It is not intended to supersede or modify any existing regulatory or management-directed requirements.
The requirements contained herein are applicable during the period while the plant is in the defueled condition and until Permanently Defueled Technical Specifications have been approved.
III. REFERENCES
- 1. NUMARC 92-02, " Regulatory Process for Decommissioning Prematurely Shutdown Plants"
- 2. Trojan Plant Procedure TPP 30-1, " Nuclear Division Defueled Requirements and Defueled Systems List"
- 3. Licensing Document Interpretation 92-07 IV. BACKGROUND Since Trojan is permanently shutdown, systems have been categorized as to whether they are required Operable, Available, Prudent, or Not Required to support the defueled condition. The purpose of this categorization was to assist affected departments in prioritizing corrective maintenance, preventative maintenance, or surveillance activities.
The four categories were defined as follows:
- 1. Operable - The term " operable" applies to systems that are required by the Trojan Technical Specifications to be operable. A system, subsystem, train, component or device shall be operable or have operability when 'it is capable or performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls,
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9 Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 2 of 28 normal and emergency electric power sources, cooling or seal water, lubrication or other i
auxiliary equipment that are required for the system, subsystem, train, component or device to perform its functions (s) are also capable of performing their rated support function (s).
Nonessential ponions of a system, subsystem, train component, or device need not be operational as long as its lack of operational capability does not in any way degrade the function (s) of the system, subsystem, train, component, or device.
- 2. Available - The term "available" applies to systems that are not required to be operable by Technical Specifications. These components fit into two general subcategories: (1)a component or system which supports the normal function of a Trojan Technical Specification System, or (2) a component or system essential to support the Emergency Plan, Fire Protection Plan, Security Plan, or other license conditions. A component or system is considered to be available when: (1) it has been appropriately tested or maintained by appropriate procedures, (2) its required auxiliaries are capable of performing their function, and (3) it has an available power source.
- 3. Prudent to Operate - The term " prudent to operate" applies to systems that are not in Trojan Technical Specifications and are not support systems to Trojan Technical Specification systems. A component or system in this category provides a plant support function that is not required for operable or available equipment but is desirable to operate to facilitate work being performed on site, or for personnel safety. A component or system in this category is afforded normal maintenance and administrative controls.
- 4. Not Required - A component in a system that is deemed not required to suppon the defueled condition. A component in this category shall have no work or testing requirements with the exception of that necessary for proper lay up or plant safety concerns.
l In conjunction with this effort, it was considered prudent to develop 1 consolidated listing of applicable Technical Specifications. Current Technical Specifications define Modes 1 through 6, but do not explicitly recognize the defueled condition. The development and utilization of this list will aid consistent application of Technical Specifications in the permanently defueled condition.
The table provided as an appendix to this document lists the Technical Specifications and their applicability in the defueled condition.
Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 3 of 28 V. GENERAL REQUIREMENTS Compliance with the Technical Specifications applicable in the defueled condition will be maintained. The table attached to this document identifies the Technical Specifications that are applicable in the defueled condition.
Surveillance Requirements associated with the applicable Technical Specifications will be implemented, except as described in Section C below. Surveillances will not be performed on inoperable equipment as permitted by Technical Specifications 4.0.1 and 4.0.3.
A. Determination of Applicability Trojan Technical Specifications that are applicable to the permanently defueled condition include:
1.
Technical Specifications contained in Section 1 -Definitions; Section 5 - Design Features; and Section 6 -Administrative Controls.
2.
Technical Specifications contained in Sections 3.0 -Limiting Conditions for Operation (with the exception of Technical Specifications 3.0.3 and 3.0.5) and Section 4.0 -
Surveillance Requirements, with:
a.
Limiting Conditions for Operation with an Applicability of"At all times" b.
Cenain Limiting Conditions for Operation with an Applicability of"All modes" or
" Modes 1 - 6" when it was determined that the intended applicability was "at all times".
c.
Limiting Conditions for Operation which are conditionally applicable. Examples in this category include those applicable "During releases via this pathway" or "When affected equipment is required to be operable".
B. Discussion of Non-applicability The table attached to this document contains the basis for the determination of non-applicability for the Technical Specifications that were determined non-applicable to the defueled condition.
An example of a Technical Specification in this category is Technical Specification 3.0.3. Existing-Technical Specification 3.0.3 states that "This Specification is not applicable in Modes 5 or 6".
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 4 of 28 The basis for Technical Specification 3.0.3 states that the purpose is to delineate the time limits for placing the unit in a safe shutdown Mode when plant operation cannot be maintained within the limits for safe operation. Because the plant will not resume operation, this specification is not needed. Similarly, the Safety Limits and Limiting Safety System Settings contained in Section 2 of the Technical Specifications are not applicable in the permanently defueled condition, as these requirements apply to operation of the reactor.
C. Additional Surveillance Requirement Information There are several Technical Specifications which are applicable at all times which contain Surveillance Requirements that are not necessary to support the permanently defueled condition.
These will be discussed separately:
1.
Technical Specification 3.4.7, Reactor Coolant System Chemistry, states that the Reactor Coolant System chemistry is to be maintained within specified limits for Dissolved Oxygen, Chloride, and Fluoride. The associated Surveillance Requirement requires analysis of Chloride and Fluoride at a minimum frequency of 3 times per 7 days with a maximum time between samples of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The basis for this requirement states that the limitations on Reactor Coolant System chemistry ensure that corrosion is minimized and reduce the potential for leakage or failure due to stress corrosion. The purpose of the surveillance requirement is to provide assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
Because the Reactor Coolant System will not be used again at elevated temperatures and pressures, failure due to stress corrosion is no longer a significant safety concern. Therefore, this Surveillance Requirement will not be performed and the Action, which requires, in part, determination that the Reactor Coolant System is acceptable for continued operations prior to increasing pressure above 500 psig or prior to proceeding to Mode 4 will be imposed.
2.
Technical Specification 3.7.2.1, Steam Generator Pressureffemperature Limitation, requires the temperatures of both the primary and secondary coolants in the steam generators to be >70 degrees Fahrenheit when the pressure of either coolant in the steam generators is >200 psig. The associated Surveillance Requirement requires that the pressure in each side of the steam generators be determined to be <200 psig at least once per hour when the temperature of either the primary or secondary coolant in the steam generator is <70 degrees Fahrenheit.-
This limitation ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 i
License NPF-1 Attachment Page 5 of 28 Currently, a pressurizer safety is removed, thus ensuring that the primary side of the steam generator will remain at atmospheric pressure. This Surveillance
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Requirement will not be performed and the Action, which requires, in part, a determination that the steam generator remains acceptable for continued operaticsn l
prior to increasing its temperatures above 200 degrees Fahrenheit, will be imposed.
3.
Technical Specification 3.4.9.1, Pressure / Temperature Limits - Reactor Coolant System, states that the Reactor Coolant System temperature and pressure shall be i
limited in accordance with the limit lines contained in the Technical Specifications j
during heatup, cooldown, criticality, and insenice leak and hydrostatic testing.
l The associated Sun eillance Requirements require, in part, that the Reactor l
Coolant System temperature and pressure be determined to be within the limits at least once per hour during system heatup and cooldown. In the defueled condition, fluctuations in Reactor Coolant System temperature are anticipated due to changes in ambient conditions. These minor fluctuations in temperature are not considered to be heatups or cooldowns and therefore the limit lines contained in Figure 3.4-2 are not applicable under these conditions. These minor fluctuations will not be recorded once per hour.
4.
Technical Specification 3.4.9.2, Pressurizer, specifies that the pressurizer temperature be limited to a maximum heatup of 100 degrees in any one hour l
period, a maximum cooldown of 200 degrees in any one hour, and a maximum spray water temperature differential of 320 degrees. The associated Surveillance Requirement requires, in part, that the pressurizer temperature be determined to be within the limits at least once per hour during system heatup or cooldown. In the defueled condition, temperature changes in the pressurizer are anticipated because of changes in ambient conditions. These minor fluctuations in temperature are not considered to be heatups or cooldowns and therefore will not be recorded once per hour.
VI. ADDITIONAL ADMINISTRATIVE CONTROLS 1
Compliance will be maintained with several Technical Specifications beyond those which are explicitly required. The table attached to this document specifies the source of the requirement for compliance with Technical Specifications in this category. These additional administrative controls include:
1.
The Seismic Category I Service Water System makeup water path to the Spent Fuel Pool will be maintained operable.
2.
One train of Senice Water will be maintained operable and capable of providing cooling l
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 6 of 28 to the operable Emergency Diesel Generator and capable of supplying makeup to the Spent Fuel Pool. It shall also be capable of being powered from the operable Emergency Diesel Generator.
3.
The Control Room Emergency Ventilation System will be maintained operable in accordance with Technical Specification 3.7.6.1, with the exception of one surveillance requirement. The associated Surveillance Requirements specify, in part, that the system be demonstrated operable by verifying that on a Safety Injection Signal, the control room -
normal air conditioning system stops and isolation dampers close to automatically isolate the control room, that the water sampling laboratory exhaust, toilet and lunch room exhaust, Control Building supply, mechanical room exhaust, and Control Building air conditioning supply systems stop, and that the control room emergency ventilation system automatically starts. This Surveillance will not be performed because the Safety Injection actuation circuitry will not be maintained as allowed by Technical Specification 3.3.2.
One train of the systems required to provide suppon functions such as power and cooling will be maintained operable. The related subsystems of chlorine detection and sulfur dioxide detection will also be maintained operable.
4.
Electrical Distribution Systems are to be maintained operable in support of the equipment required to be maintained operable. This includes one offsite transmission circuit and one Emergency Diesel Generator Circuit (as the necessary attendant power source) as dermed in Technical Specification 3.8.1.2. Technical Specification 3.8.1.2 contains a requirement to perform surveillance testing in accordance with Surveillance Requirement 4.8.1.1.2, which requires, in part, simulating a loss of offsite power with and without the presence of a safety injection signal, and verifying:
- 1. De-energization of the emergency busses and load shedding from the emergency busses
- 2. That the diesels start from ambient conditions on the auto stan signal and energize the emergency busses, and
- 3. That the non-emergency diesel generator trips are bypassed on an automatic start signal.
These surveillance requirements verify the availability of automatic start and load features of the emergency diesel generator units. The load shedders and sequencers are designed to sequence on key Engineered Safety Features loads in the event of a loss of offsite power with or without a concurrent Safety Injection Signal. This function is only needed in Modes 1 - 4. The availability of these automatic start features of the emergency diesel generator units is not considered necessary to support the defueled condition. Therefore, surveillances related to the automatic start and load features of the diesel generator units will not be performed.
Trojan Nuclear Plant Document Control Desk -
' Docket 50-344 March 16,1993 License NPF-1 Attachment Page 7 of 28 VII. ADDITIONAL INFORMATION 1.
Inservice inspection and testing for ASME Code Class 1,2, and 3 components will be govemed by the insenice inspection and testing program.
2.
Performance of snubber surveillances will be governed by the snubber surveillance program.
VIII.
SUMMARY
This document contains a summary of the operational requirements for the defueled condition, including Technical Specification requirements and self-imposed administrative requirements. For those Technical Specifications that are no longer considered applicable, a summary of the basis for non-applicability is included.
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Document Control Desk Trojan Nuclear Plant March 16,1993 Docket 50-344 Attachment License NPF-1 Page 8 of 28 TTS Applicability While Defueled Appendix Technical Specification Title LCO Applicability All definitions are applicable.
1.0 DEFINITIONS SAFETY LIMITS AND Not Applicable. The Safety Limits and 2.0 LIMITING SAFETY SETITNGS Limiting Safety System Settings are only applicable in Modes 1,2.3.4.5.
3.0.1 LIMITING CONDITIONS FOR Applicable.
OPERATION 3.0.2 LIMITING CONDITIONS FOR Applicable.
OPERATION 3.0.3 LIMITING CONDITIONS FOR Not Applicable.
OPERATION 3.0.4 LIMITING CONDITIONS FOR Applicable.
OPERATION 3.0.5 LIMITING CONDITIONS FOR Not Applicable. Applicable only in Modes 1 -
4.
OPERATION 3.1.1.1 REACTIVITY CONTROL Not Applicable. Applicable only in Modes SYSTEMS - BORATION 1,2.3.
CONTROL - SIRTfDOWN MARGIN n
3.1.1.2 REACTIVITY CONTROL Not Applicabic. Applicable only in Modes 4,5.
SYSTEMS - BORATION CONTROL - SHUTDOWN MARGIN - Tavg </= 350
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Trojar Nuclear Plant Document Control Desk i
Docket 50-344 March 16,1993 i
License NPF-1 Attachment Page 8 of 28
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TTS Applicability While Defueled i
Appendix
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Technical Specification Title LCO Applicability 1.0 DEFINITIONS All definitions are applicable.
2.0 SAFETY LIMITS AND Not Applicable. The Safety Limits and I IMmNG SAFETY SETTINGS Limiting Safety System Settings are only applicable in Modes 1,2,3,4,5.
3.0.1 LIMmNG CONDmONS FOR Applicable.
OPERATION 3.0.2 LIMmNG CONDmONS FOR Applicable.
OPERATION l
3.0.3 LIMmNG CONDmONS FOR Not Applicable.
OPERATION
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J.0.4 LIMmNG CONDITIONS FOR Applicable.
f OPERATION 3.0.5 LIMmNG CONDmONS FOR Not Applicable. Applicable only in Modes 1 -
OPERATION 4.
3.1.1.1 REACTIVITY CONTROL Not Applicable. Applicable only in Modes
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SYSTEMS - BORATION 1,2,3.
CONTROL-SHUTDOWN
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MARGIN 3.1.1.2 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 4.5.
SYSTEMS - BORATION i
CONTROL - SIRITDOWN
-l MARGIN - Tavg </= 350
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment l
Page 9 of 28 l
Appendix I
Technical Specification Title LCO Applicability
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3.1.1.3 REACTIVITY CONTROL Not Applicable. Applicable only in Modes i
SYSTEMS - BORATION 1,2,3,4,5,6. This Specification ensures l
CONTROL - BORON DILUTION adequate mixing. prevents stratification, and l
ensures gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. With no fuel assemblies in the vessel, it is not necessary to ensure the reactivity change rate associated with boron reductions are within the capability for operator l
recognition and control.
3.1.1.4 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1.2.
f SYSTEMS - BORATION CONTROL - MODERATOR l
TEMPERATURE COEFFICIENT j
3.1.1.5 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1,2.
j SYSTEMS - BORATION i
i CONTROL MINIMUM TEMPERATURE FOR i
CRITICALITY 3.1.2.1 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 5,6.
SYSTEMS - BORATION This Specification ensures that negative SYSTEMS - FLOW PATHS -
reactivity control is available. With no fuel.
l SHUTDOWN assemblics in the vessel, this is no longer a
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-l concern.
3.1.2.2 REACTIVITY CONTROL Not Applicable. Applicable only in Modes I
SYSTEMS - DORATION 1,2,3,4.
l SYSTEMS - FLOW PATHS -
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OPERATING j
1 3.1.2.3 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 5,6.
l SYSTEMS - BORATION This Specification ensures a flow path for -
SYSTEMS - CHARGING boron injection. With no fuel assemblies in l
PUMP - SHUTDOWN the vessel, a path for boron injection is no longer necessary.
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l Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment i
Page 10 of 28 l
Appendix Technical Specification Title LCO Applicability 3.1.2.4 REACTIVITY CONTROL Not Applicable. Applicable onlyin Modes l
SYSTEMS - BORATION 1,2,3,4.
SYSTEMS - CHARGING PUMPS - OPERATING 3.1.2.5 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 5,6.
SYSTEMS - BORATION This Specification ensures a flow path for SYSTEMS-BORIC ACID boron injection. With no fuel assemblies in the TRANSFER PUMPS -
vessel, a path for boron injection is no longer SHUTDOWN necessary.
3.1.2.6 REACTIVITY CONTROL Not Applicab!c. Applicable only in Modes SYSTEMS - BORATION 1,2,3,4.
SYSTEMS - BORIC ACID TRANSFER PUMPS -
OPERATING 3.1.2.7 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 5,6.
SYSTEMS - BORATION This Specification ensures the availability of SYSTEMS - BORATED WATER borated water for shutdown conditions in the SOURCES-SHUTDOWN Reactor Coolant System. With no fuel assemblies in the vessel, assurance of sufficient boron inventory is no longer needed.
3.1.2.8 REACTIVITY CONTROL Not Applicable. Applicable only in Modes SYSTEMS - BORATION 1,2,3,4.
SYSTEMS - BORATED WATER SOURCES - OPERATING 3.1.3.1 REACTIVTTY CONTROL Not Applicable. Applicable only in Modes 1,2.
SYSTEMS - MOVABLE CONTROL ASSEMBLIES -
GROUP HEIGHT
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 11 of 28 I
.i Appendix Technical Specification Title LCO Applicability 3.1.3.2 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1,2.
SYSTEMS - MOVABLE CONTROL ASSEMBLIES -
l POSITIONINDICATOR l
- CHANNELF, 3.1.3.3 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1,2.
SYSTEMS -MOVABLE i
ASSEMBLIES - ROD DROP TIME 3.1.3.4 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1,2.
SYSTEMS -MOVABLE ASSEMBLIES - SHUTDOWN ROD INSERTION LIMITS 3.I.3.5 REACTIVITY CONTROL Not Applicable. Applicable only in Modes 1.2.
l SYSTEMS - MOVABLE ASSEMBLIES - CONTROL i
ROD INSERTION LIMITS l
3.2.1 POWER DISTRIBUTION Not Applicable. Applicable only in Mode 1.
l LIMITS - AXIAL FLUX
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DIFFERENCE (AFD) j 3.2.2 POWER DISTRIBUTION Not Applicable. Applicable only in Mode 1.
LIMITS - HEAT FLUX HOT i
CHANNEL FACTOR -
FQ(X,Y.Z) j 3.2.3 POWER DISTRIBUTION Not Applicable. Applicab!c only in Mode 1.
LIMITS - NUCLEAR j
ENTHALPY RISE HOT CHANNEL FACTOR - FdH(X,Y) 3.2.4 POWER DISTRIBUTION Not Applicable. Applicable only in Mode 1.
LIMITS - QUADRANT POWER TILT RATIO
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i Trojan Nuclear Plant Document Control Desk l
Docket 50-344 March 16,1993 License NPF-1 Attachment Page 12 of 28 Appendix l
Technical Specification Title LCO Applicability 3.2.5 POWER DISTRIBUTION Not Applicable. Applicable only in Mode 1.
LIMITS - DNB PARAMETERS 3.3.3 INSTRUMENTATION -
Not Applicable. Applicable only in Modes REACTOR TRIP SYSTEM 1.2,3,4 and 5 as shown in Table 3.3-I.
INSTRUMENTf'lON 3.3.2 INSTRUMElfTATION -
Not Applicable. Applicable only in Modes l
ENGINEERED SAFETY 1,2,3 and 4 as shown in Table 3.3-3.
FEATURE ACTUATION SYSTEM INSTRUMENTATION 3.3.3.1 INSTRUMENTATION -
Applicable. Fuel Storage Pool Arca Radiation.
i RADIATION MONITORING Monitors are required with fuel in the storage j
INS'IRUMENTATION pool or building. Containment High Range i
Area Radiation Monitors are only required in Modes 1-4.
3.3.3.2 INSTRUMENTATION -
Not Applicable. Applicable only when the MOVABLE INCORE movable incore detection system is used for i
DETECTORS recalibration of the axial flux offset detection.
system, monitoring the quadrant power tilt ratio, measurement of Fdelta H and FQ..
i 3.3.3.3 INSTRUMENTATION.
Applicable.
SEISMIC INSTRUMENTATION I
l 3.3.3.4 INSTRUMENTATION -
Applicable.
METEOROLOGICAL l
l INSTRUMENTATION i
3.3.3.5 INSTRUMENTATION -
Not Applicable. Applicable only in Modes f
REMOTE SHUTDOWN 1,2,3.
INSTRUMENTATION i
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I Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 l
License NPF-1 Attachment l
Page 13 of 28 I
Appendix Technical Specification Title LCO Applicability f
i 3.3.3.6 INSTRUMENTATION -
Applicable. Although the applicability stated in f
CHLORINE DETECTION the Limiting Condition for Operation is all l
SYSTEMS Modes. this specification is being i
administrative!y applied to the defueled condition.
j 3.3.3.7 INSTRUMENTATION - FIRE Applicabic to protect systems and components 4
PROTECTION required to be OPERABLE when defueled.
INSTRUhENTATION 3.3.3.8 INSTRUMENTATION -
Applicable for the systems and components DECObi'LE SWTTCIIES required to be OPERABLE when defueled.
3.3.3.9 INSTRUhENTATION -
Not Appliuible. Applicable only in Modes i
ACCIDENT MONITORING 1,2,3.
l INSTRUMENTATION i
5 3.3.3.10 INSTRUMENTATION -
Applicable.
RAD 10 ACTIVE LIQUID j
EFFLUENT INSTRUMENTATION
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3.3.3.11 INSTRUMENTATION -
Applicable.
j RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION I
3.3.3.12 INSTRUMENATION - SO2 Applicable. Although the applicability stated j
DETECTION SYSTEMS in the Limiting Condition for Operation is l
Modes 1,2,3,4. this specification is being i
administratively applied to the defueled Condition.
i 3.4.1.1 REACTOR COOLANT Not Applicable. Applicable only in Modes 1 SYSTEM - REACTOR and 2.
COOLANT LOOPS - NORMAL OPERATION j
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4 Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 14 of 28 Appendix Technical Specification Title LCO Applicability 3.4.1.2 REACTOR COOLANT Not Applicable. Applicable only in Mode 3.
SYSTEM - REALTOR COOLANTLOOPS-HOT STANDBY 3.4.1.3 REACTOR COOLANT Not Applicable. Applicable only in Modes 4,5.
SYSTEM - REACTOR COOLANT LOOPS -
SHUTDOWN 3.4.1.4 REACTOR COOLANT Not Applicable. Applicable only in Modes 4,5.
SYSTEM - REACTOR COOLANT LOOPS - NORMAL OPERATION 3.4.2 REACTOR COOLANT Not Applicable. Applicable only in Modes 4,5.
SYSTEM - SAFETY VALVES -
SHUTDOWN 3.4.3.1 RE' '~h,. COOLANT Not Applicable. Applicable only in Modes SYSTEM-SAFETY AND 1,2,3.
RELIEF VALVES -
OPERATING - SAFETY 1
VALVES 3.4.3.2 REACTOR COOLANT Not Applicable. Applicable only in Modes SYSTEM - SAFETY AND 1,2,3.
RELIEF VALVES -
OPERATING - RELIEF VALVES 3.4.4 REACTOR COOLANT Not Applicable. Applicable only in Modes SYSTEM - PRESSURIZER 1,2,3.
3.4.5 REACTOR COOLANT Not Applicable. Applicable only in Modes SYSTEM - STEAM 1.2.3,4.
GENERATORS 1
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Trojan Nuc! car Plant Document Control Desk Docket 50-314 March 16,1993 License NPF-1 Attachment Page l5 0f 28 Appendix Technical Specification Title LCO Applicability 3.4.6.1 REACTOR COOLANT Not Applicabic. ApplicabiconlyinModes SYSTEM - REACTOR 1,2,3,4.
COOLANT SYSTEM LEAKAGE-LEAKAGE DETECTION SYSTEMS 3.4.6.2 REACTOR COOLANT Not Applicable. Applicable onlyinModes SYSTEM - REACTOR 1.2,3,4.
COOLANT SYSTEM LEAKAGE - OPERATIONAL LEAKAGE 3.4.7 REACTOR COOLANT Applicable. (See discussion in Section V.C.)
SYSTEM - CHEMISTRY 3.4.8 REACTOR COOLANT Not Applicable. Applicable only in Modes SYSTEM - SPECIFIC ACTIVITY 1,2,3,4,5.
3.4.9.1 REACTOR COOLANT Applicable. (See discussion in Section V.C.)
SYSTEM - PRESSURE /
TEMPERATURE LIMITS -
REACTOR COOLANT SYSTEM 3.4.9.2 REACTOR COOLANT Applicable. (See discussion in Section V.C.)
SYSTEM - PRESSURE /
TEMPERATURE LIMITS -
PRESSURIZER 3.4.9.3 REACTOR COOLANT Applicable. Although the applicability stated SYSTEM - PRESSURE /
in the Limiting Condition for Operation is TEMPERATURE LIMITS -
Modes 4,5,6. this specification is being OVERPRESSURE administratively applied to the defueled PROTECTION SYSTEMS condition.
- _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ = _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - -
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Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment j
Page 16 of 28 J
Appendix Technical Specification Title LCO Applicability f
3.4.10.1 REACTOR COOLANT Not Applicable. Applicable only in Modes j
SYSTEM - STRUCTURAL 1,2,3,4,5,6. (Inspection of Class 1,2, and 3 INTEGRITY - ASME CODE components is required by Specification 4.0.5.)
i CLASS 1,2, AND 3 l
COMPONENTS i
i 3.4.11 REACTOR COOLANT Not Applicable. Applicable only in Modes SYSTEM - REACTOR VESSEL 1,2,3.
[
HEAD VENT VALVES
[
3.5.1 EMERGENCY CORE COOLING Not Applicable. Applicable only in Modes SYSTEMS (ECCS)-
1,2,3.
ACCUMULATORS g
3.5.2 EMERGENCY CORE COOLING Not Applicabic. Applicable only in Modes l
l SUBSYSTEMS - Tavg >= 350F
{
3.5.3.1 EMERGENCY CORE COOLING Not Applicable. Applicable only in Mode 4 f
SUBSYSTEMS - Tavg <= 350F 3.5.3.2 EMERGENCY CORE COOLING Not Applicable. Applicable only in Mode 4 SYSTEMS (ECCS)- ECCS with the temperature of any cold leg </= 290; SUBSYSTEMS -Tavg < 350 Mode 5, or Mode 6 with the Reactor Vessel Head on. This Specification ensures a mass addition transient can be relieved by a single Power Operated Relief Valve. This is not a concern with a safety removed.
3.5.4 DELETED DELETED.
3.5.5 EMERGENCY CORE COOLING Not Applicable. Applicable only in Modes l
SYSTEMS (ECCS)-
1,2,3,4.
REFUELING WATER STORAGETANK l
l i
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License NPF-1 Attachrnent
- l Page 17 of 21t l
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Appendis Technical Specification Titic LCO Applicability 3.6.1.1 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes f'
PRIMARY CONTAINMENT-1,2,3,4.
CONTAINMENTINTEGRITY 3.6.1.2 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes PRIMARY CONTAINMENT -
1.2,3,4 i
CONTAINMENT LEAKAGE l
t 3.6.1.3 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes PRIMARY CONTAINMENT -
1,2,3,4.
t i
CONTAINMENT AIR LOCKS l
3.6.1.4 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes
{
1.2.3,4 i
l INTERNAL PRESSURE
{
1 3.6.1.5 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes j
1,2,3,4.
l AIR TEMPERATURE 3.6.1.6 CONTAINMENT SYSTEMS -
Not Applicable. Applicable onlyin Modes j
PRIMARY CONTAINMENT-1,2.3.4 j
CONTAINMENT l
STRUCTURAL INTEGRITY 3.6.2.1 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes l
DEPRESSURIZATION AND 1,2,3,4.
]
COOLING SYSTEMS -
SYSTEM j
3.6.2.2
' CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes DEPRESSURIZATION AND 1.2,3,4 l
COOLING SYSTEMS - SPRAY l
ADDITIVE SYSTEM 1
4
..-wm
i Trojan NuclearPlant Document Control De!,k Docket 50-344 March 16,1993 License NPF-1 Attachment Page IS of 28 i
Appendix i
i Technical Specification Title LCO Applicability i
3.6.2.3 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes DEPRESSURIZATION AND 1,2.and 3.
COOLING SYSTEMS -
CONTAINhENT COOLING SYSTEM i
1 1
3.6.3.1 CObrTAINMENT SYSTEMS -
Not Applicable. Applicab!c only in Modes l
CONTAINMENTISOLATION 1.2,3,4.
VALVES i
3.6.4.1 CONTAINMENT SYSTEMS -
Not Applicable. Applicabic only in Modes 1 COMBUSTIBLE GAS and 2.
CONTROL-HYDROGEN l'
ANALYZERS 5
3.6.4.2 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes 1 l
COMBUSTIBLE GAS and 2.
7 CONTROL - ELECTRIC 1'
HYDROGEN RECOMBINERS 3.6.4.3 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes land COMBUSTIBLE GAS 2.
l CONTROL-int)ROGEN.
-) -
VENT SYSTEM 3.6.4.4 CONTAINMENT SYSTEMS -
Not Applicable. Applicable only in Modes 1 l
COMBUSTIBLE GAS and 2.
CONTROL-HYDROGEN MLXING SYSTEM 3.7.1.1 PLANT SYSTEMS -TURBINE Not Applicable. Applicable only in Modes CYCLE - SAFETY VALVES 1,2,3.
J l
l 3.7.1.2 PLANT SYSTEMS - TURBINE Not Applicable. Applicable onlyinModes CYCLE-AUXILIARY 1,2,3-.
FEEDWATER SYSTEM 9
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Appendix Technical Specification Title LCO Applicability 3.7.1.4 PLANT SYSTEMS - TURBINE Not Applicable Applicable only in Modes CYCLE - CONDENSATE 1,2,3.
STORAGE TAhX i
3.7.1.5 PLANT SYSlEMS -TURBINE Not Applicable. Applicable only in Modes l
CYCLE-ACTIVITY 1.2,3,4.
3.7.1.6 PLANT SYSTEMS - TURBINE Not Applicable. Applicable only in Modes CYCLE - MAIN STEAM LINE 1,2,3.
ISOLATION VALVES 3.7.2.1 PLANT SYSTEMS - STEAM Applicable. (See discussion in Section V.C.)
GENERATOR l
PRESSURE / TEMPERATURE LIMITATION 3.7.3.1 PLANT SYSTEMS -
Not Applicable. Applicable onlyin Modes COMPONENT COOLING 1.2,3,4 WATER SYSTEM 3.7.3.2 PLANT SYSTEMS -
Not Applicable. Applicable only in Modes 5,6.
j COMPONENT COOLING j
WATER SYSTEM 3.7.4.1 PLANT SYSTEMS - SERVICE Not Applicable. Applicable only in Modes j
WATER SYSTEM 1,2,3,4.
i 3.7.4.2 PLANT SYSTEMS - SERVICE Applicable. Although the applicability stated WATER SYSTEM in the Limiting Condition for Operation is Modes 5 and 6, this specification is being l
administratively applied to the defueled l
condition.
~!
3.7.5.1 PLANT SYSTEMS -
Not Applicable. Applicable only in Modes j
f ULTIMATE HEAT SINK 1,2,3.4.
1 J
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License NPF-1 Attachment Page 20 of 28 l
l Appendit TechaicalSpecification Title LCO Applicability I
3.7.6.1 PLANT SYSTEMS - CONTROL Applicable, Although the applicability stated ROOM EMERGENCY in the Limiting Condition for Operation is in VENTILATION SYSTEM all Modes, this specification is being administratively applied to the defueled condition.
t 3.7.7.1 PLANT SYSTEMS - SEALED Applicable.
l SOURCE CONTAMINATION
.i 3.7.8.1 PLANT SYSTEMS - FIRE Applicable, j
SUPPRESSION SYSTEMS -
FIRE SUPPRESSION WATER f
SYSTEM s
3.7.8.2 PLANT SYSTEMS - FIRE Applicable whenever equipment in the spray, SUPPRESSION SYSTEMS -
sprinkler, and/or deluge protected areas is SPRAY, SPRINKLER, AND/OR required to be operable.
DELUGE SYSTEMS j
i 3.7.S.3 PLANT SYSTEMS - FIRE Applicable whenever equipment in the areas SUPPRESSION SYSTEMS -
protected by the fire hose stations is required to l
FIRE HOSE STATIONS be operable.
3.7.9 PLANT SYSTEMS -
Applicable.
PENETRATION FIRE BARRIERS 3.7.10 PLANT SYSTEMS - SNUBBERS Applicable. The Limiting Condition for Operation states that this specification is i
applicable in Modes 1,2,3, and 4, and Modes 5 and 6 for snubbers located on systems -
required operable in those modes. Snubber l
surveillances are govemed by a separate document.
3.7.11 PLANT SYSTEMS - CONTROL Applicable.
j BUILDING MODIFICATION CONNECTION BOLTS.
i 1
i r
_i_,_
= _..,
ar.
-c.-y
Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 21 of 28 Appendix
)
L Technical Specification Title LCO Applicability 3.8.1.1 ELECTRICAL POWER Not Applicable. Applicable only in Modes SYSTEMS - A.C. SOURCES -
1,2,3,4.
OPERATING 3.8.1.2 ELECTRICAL POWER Applicable. Although the applicability stated SYSTEMS - A.C. SOURCES -
in the Limiting Condition for Operation is SHUTDOWN Modes 5 and 6, this specification is being administratively applied to the defueled condition.
1 3.8.2.1 ELECTRICAL POWER Not Applicable. Applicable only in Modes SYSTEMS - ONSITE 1,2,3,4.
l DISTRIBUTION SYSTEMS -
A.C. DISTRIBUTION -
OPERATING 3.8.2.2 ELECTRICAL POWER Applicable. Although the applicability stated SYSTEMS - ONSITE POWER in the Limiting Condition for Operation is DISTRIBUTION - A. C.
Modes 5 and 6, this specification is being i
DISTRIBUTION - SHUTDOWN administratively applied to the defueled condition.
3.8.2.3 ELECTRICAL POWER Not Applicable. Applicable only in Modes l
SYSTEMS - ONSITE POWER 1,2,3,4,
?
DISTRIBUTION - D.C.
i DISTRIBUTION - OPERATING 3.8.2.4 ELECTRICAL POWER Applicable. Although the applicability stated SYSTEMS - ONSITE in the Limiting Condition for Operation is DISTRIBUTION SYSTEMS -
Modes 5 and 6, this specification is being i
D.C. DISTRIBUTION -
administratively applied to the defueled SHUTDOWN condition.
.I 1
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License NPF-1 Attachment i
Page 22 of 28 l
Appendit -
Technical Specification Title LCO Applicability f
I i
3.8.3.1 ELECTRICAL POWER Not Applicable. Applicable only in Modes l
SYSTEMS - UNDERVOLTAGE 1.2,3.
l FROTECTION-4.16 kV l'
ENERGENCY BUS UNDERVOLTAGE PROTECTION i
3.9.1 REFUELING OPERATIONS -
Not Applicabic. Applicable only in Mode 6.
i BORON CONCENTRATION The limitation on minimum boron i
l concentration ensures that the reactor will
{
remain suberitical during core alterations and that a uniform boron concentration is i
maintained for reactivity control in the water l
volume having direct access to the reactor l
vessel. Because there are no fuel assemblies in the reactor vessel, this specification is not r.ecessary.
{
'i 3.9.2 REFUELING OPERATIONS.
Not Applicable. Applicabic only in Mode 6.
INSTRUhENTATION Because there are no fuel assemblies in the reactor vessel, there is no need for source range
}
neutron flux monitors.
I 3.9.3 REFUELING OPERATIONS -
.Not Applicable. Applicable during movement DECAY TIhE ofirradiated fuel in the seactor vessel. There i
are no fuel assemblies in the reactor vessel.
i 3.9.4 REFUELING OPERATIONS -
Not Applicable. Applicable during core CONTAINMENT BUILDING alterations or movement ofirradiated fuel PENETRATIONS within the containment. There will be no irradiated fuel assemblies in containment.
.l
[
3.9.5 REFUELING OPERATIONS -
Not Applicable. Applicable dunng core i
COMMUNICATIONS alteratiers.
4 3.9.6 IEFUELING OPERATIONS -
Not Applicable. Applicable during movement f
MANIPULATOR CRANE of drive shans or fuel assemblics within the l
OPERABILITY reactor vessel.
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Docket 50-344 March 16,1993 License NPF-1 Attachment Page 23 of 28 Appendix Technical Specification Title LCO Applicability 3.9.7 REFUELING OPERATIONS -
Applicable with fuel assemblies and water in CRANE TRAVEL - FUEL the storage pool.
t BUILDING 3.9.8.1 REFUELING OPERATIONS -
Not Applicable. Applicable only in Mode 6.
COOLANT CIRCULATION This specification ensures that suflicient cooling capacity is available to remove decay heat and maintain the water in the reactor t'
vessel less than 140 degrees and that suflicient coolant circulation is maintained to minimize the effect of a boron dilution incident and prevent stratification. Since there are no fuel assemblies in the reactor vessel, there is no decay heat to be removed. Boron dilution incidents are not of concern.
3.9.8.2 REFUELING OPERATIONS -
Not Applicable. Applicable in Mode 6 when LOW WATER LEVEL the water level above the top of the reactor pressure reswl flange is kss than 23 feet.
Because there are no fuel assemblics and hence no decay heat in the reactor vessel, there is no need to maintain two residual heat removal loops operable to ensure decay heat removal capability.
3.9.9 REFUELING OPERATIONS -
Not Applicable. Applicableduringcore CONTAINMENT alterations or movement ofirradiated fuel VENTILATION ISOLATION within the Containment. There are no fuel 1
SYSTEM assemblics in the containment.
3.9.10 REFUELING OPERATIONS -
Not Applicable. Applicable during movement WATER LEVEL - REACTOR of fuel assemblies or control rods within the VESSEL reactor pressure vessel while in Mode 6. There will be no control rods or fuel assemblies in the reactor vessel.
r
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l Appendis l
Technical Specification Title LCO Applicability 3.9.11 REFUELING OPERATIONS.
Applicable whenever irradiated fuel assemblies STORAGE POOL WATER are in the storage pool.
LEVEL 3.9.12 REFUELING OPERATIONS.
Applicable.
[
SPENTFUEL POOLEX11AUST SYSTEM i
i 3.9.13 REFUELING OPERATIONS.
Not Applicable. Applicable only in Mode 6.
}
CONTAINMEbTT PURGE EXIIAUST SYSTEM l
OPERATION 3.10.1 SPECI AL TEST EXCElrrlONS - Not Applicable. Applicable only in Mode 2.
SHUTDOWN MARGIN 3.10.2 SPECIAL TEST EXCEPTIONS Not Applicabic. Applicable only in Mode 1.
l GROUP IIElGilT, INSERTION l
AND POWER DISTRIBUTION li LIMITS 3.10.3 SPECIAL TEST EXCEPTIONS Not Applicable. Applicable only in Mode 2.
PRESSURF) TEMPERATURE l
LIMITAllON - REACTOR CRinCAUTY
[
3.10.4 SPECIAL TEST EXCEPTIONS. Not Applicable. Applicable only in Mode 2.
f PIIYSICS TESTS 3.10.5 SPECIAL TEST EXCEPTIONS - Not Applicabic. Applicable during l
NATURAL CIRCULATION perfortmmec of physics testing and operation i
TESTS below the P-7 Interlock Setpoint.
l l
3.11.1.1 RADIOACTIVE EFFLUENTS. Applicabic At AllTimes.
LIQUID EFFLUENTS CONCENTRATION
.j k
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Page 25 of 28 Appendix i
Technical Specification Title LCO Applicability i
3.11.1.2 RADIOACFIVE EFi'LUENTS - Applicable At AllTimes.
LIQUID EFFLUENTS - DOSE 3.11.1.3 RADIOACFIVE EFFLUENTS - Applicable At AllTimes.
LIQUID EFFLUENTS-LIQUID i
WASTE TREATMENT i
i 3.11.1.4 RADIOACTIVE EFFLUENTS - Applicable At AllTimes.
LlQUID EFFLUENTS -
TEMPORARY RADWASTE STORAGE TANKS l
3.11.2.1 RADIOACTIVE EFFLUENTS - Applicable At AllTimes.
GASEOUS EFFLUENTS -DOSE RATE f
3.11.2.2 RADIOACFIVE EFFLUENTS - Applicab!c At AllTimes.
GASEOUS EFFLUENTS -
1 DOSE. NOBLE GASES l
3.11.2.3 RADIOACTIVE EFFLUENTS - Applicable At AllTimes.
f DOSE -IODINE-131, TRITIUM
[
I AND RADIONUCLIDES IN PARTICULATE FORM 3.11.2.4 RADIOACTIVE EFFLUENTS - Applicable At AllTimes
[
GASEOUS EFFLUENTS -
GASEOUS RADWASTE
[
TREATMEhT
+
3.11.2.5 RADIOACTIVE EFFLUENTS - Applicable At All Times.
GASEOUS EFFLUENTS -
TOTAL DOSE l
3.11.2.6 RADIOACTIVE EFFLUENTS - Applicable At AllTimes.
GASEOUS EFFLUENTS -
l EXPLOSIVE GAS MIXTURE j
^
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License NPF-1 Attachment Page 26 of 28 I
i Appendix
}
j Technical Specification Title LCO Applicability f
3.11.3.1 RADIOACTIVE EFFLUENTS - Applicable At AllTimes.
i SOLID RADIOACTIVE WASTE I
3.12.1 RADIOLOGICAL Applicable At AllTimes.
ENVIRONMENTAL MONITORING PROGRAM -
MONITORING PROGRAM f
3.12.2
. RADIOLOGICAL Applicable At AllTimes.
I ENVIRONMENTAL MONITORING - LAND USE f
CENSUS i
i 3.12.3 RADIOLOGICAL Applicable At AllTimes.
l ENVIRONMENTAL I
MONITORING -
1 INTERLABORATORY i
COMPARISON PROGRAM f
i 4.0.1 SURVEILLANCE Applicable.
REQUIREMENTS 4
4.0.2 SURVEILLANCE Applicabic.
REQUIREhENTS 4.0.3 SURVEILLANCE Applicable.
REQUIREMENTS
(
4.0.4 SURVEILLANCE Applicable.
REQUIREMENTS 4.0.5 SURVEILLANCE Applicable.
)
REQUIREMENTS l
4 f
5.0 DESIGN FEATURES Applicable.
f f
6.1 RESPONSIBILITY Applicable.
f h
f l
i
l
\\
Trojan Nuclear Plant Document Control Desk Docket 50-344 March 16,1993 License NPF-1 Attachment Page 27 of 28
')
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Appendix l
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Technical Specification Title LCO Applicability 6.2 ORGANIZATIONAL Applicable.
REQUIREMENTS 6.3 FACILITY STAFF Applicable.
QUALIFICATIONS t
6.4 TRAINING Applicable.
6.5 REVIEW AND AUDIT Applicable.
i 6.6 REPORTABLE EVENT ACTION Applicable.
j 3
l 6.7 SAFETY LIMIT VIOLATION Not Applicable. There are no fuel assemblies l
in Containment, therefore Safety Limits on l
reactor power, pressurizer pressure, RCS pressure, and loop coolant temperature are not applicable.
6.8 PROCEDURES AND Applicable.
PROGRAMS 6.9 REPORTING REQUIREMENTS Applicable. Reports per specifications 6.9.1.1, i
6.9.12,6.9.1.3. and 6.9.1.7, are not anticipated.
6.10 RECORD RETENTION Applicable.
l
'I 6.11 RADIATION PROTECTION Applicable.
PROGRAM I
6.12 HIGli RADI ATION AREA Applicable.
6.13 ENVIRONMENTAL Applicable.
QUALIFICATION
[
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e
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Appendit l
?
Technical Specification Title LCO Applicability.
6.14 PROCESS CONTROL Applicable.
l PROGRAM t
6.15 OFFSITE DOSE Applicable.
j CALCULATION MANUAL l
(ODCM) i 6.16 MAJOR CIIANGES TO Applicable.
RADIOACTIVE WASTE TIEATMENT SYSTEMS l
(Liquid, Gaseous, and Solid)
L
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. -.