ML19336A655

Proposed Changes to Tech Specs 3/4.4 Through 3/4.9.13, Incorporating Revisions Re Refueling Operations & Redundancy in Residual Heat Removal Capabilities

ML19336A655
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/24/1980
From:	PORTLAND GENERAL ELECTRIC CO.
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Shared Package
ML19336A650	List: ML19336A649 ML19336A654 ML19336A655
References
NUDOCS 8010300425
Download: ML19336A655 (16)

Text

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Dif ference................. 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor............. 3/4 2-5 3/4.2.3 RCS Flowrate and F 3/42-8 R

3/4.2.4 Quadrant Power Til t Ratio............... 3/4 2-10 3/4.2.5 DNB Parameters...

3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUfENTATION................... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......... 3/4 3-33 Movable Incore Dett: tors............... 3/4 3-37 Seismic Instrumentation................ 3/4 3-38 Meteorological Instrumentation............ 3/4 3-41 Remote Shutdown Instrumentation............ 3/4 3-44 Chlorine Detection Systems.............. 3/4 3-47 Fire Detection Instrumentation............. 3/4 3-48 Decouple Switches 3/4 3-50 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS Power Operation 'nd Startup 3/4 4-1 Hot Standby 3/4 4-2b S hu t do w n....................... 3/4 4-2c TROJAN-UNIT 1 IV 80103006f5

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.9 REFUELING OPERATIONS 1/4.9.1 BORON CONCENTRATION.................. 3/4 9-1 3/4.9.2 INSTRUMENTATION.................... 3/4 9 2 3/4.9.3 DECAY TIME...................... 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........... 3/4 9-4 3/4.9.5 COMMUNICATIONS.................... 3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY............. 3/4 9-6 3/4.9.,

CRANE TRAVEL - FUEL BUILDING............. 3/4 9-7 3/4.9.6 COOLANT CIRCULATION AND LOW WATER LEVEL 3/4 9-8 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM....... 3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR VESSEL.............. 3/4 9-10 3/4.9.11 STORAGE POOL WATER LEVEL............... 3/4 9-11 3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM............ 3/4 9-12 3/4 9.13 CONTAINMENT PURGE EXHAUST SYSTEM OPERATION...... 3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS. 3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION-REACTOR CRITICALITY.. 3/4 10-3 3/4.10.4 PHYSICS TESTS..................... 3/4 10-5 3/4.10.5 NATURAL CIRCULATION TESTS............... 3/4 10-6 TROJAN-UNIT 1 VIII

f 3/4.4 REACTOR COOLANT SYSTEM

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3/4.4.1 REACTOR COOLANT LOOPS NORMAL OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 All reactor coolant I sops shall be in operation.

APPLICABILITY: As noted below, for MODES 1 and 2.*

ACTION:

Above P-7, comply with either of the following ACTIONS:

a.

With one reactor coolant loop and associated pump not in operation, STARTUP and/or continued POWER OPERATION may proceed provided THERMAL POWER is restricted to <31% of RATED THERMAL POWER and the following ESFAS instrumentation channels associated with the loop not in operation, are placed in their tripped condition within 1 hour:

1)

Tav$uit with Steam Flow - High for Safety Injection.

- Low-Low channel used in the coincidence ci r

2) Steam Line Pressure - Low channel used in the coincidence circuit with Steam Flow - High for Safety Injection.

3) Steam Flow-High channel used for Safety Injection.

4) Differential Pressure Between Steam Lines - High Channel used for Safety Injection (trip all bistables which indicate low active loop steam pressure with respect to the idle loop steam pressure).

b.

With one reactor coolant loop and ass,ciated pump not in operation, subsequent STARTUP and POWER OPERATION above 31% of RATED THERMAL POWER may proceed provided:

1.

The following actions have been completed with the reactor subcritical:

a) Reduce the overtemperature AT trip setpoint to the value specified in Specification 2.2.1 for 3 loop operation.

• See Special Test Exception 3.10.5.

TROJAN-UNIT 1 3/4 4-1

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3/4.4 REACT 0k COOLANT SYSTEM BASES 3/4.4.2 and 3/4.4.3 SAFETY VALVES (Continued) the valve's setpoint. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating RHR loop. connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

During operation, all pressurizer code safety valves mu" oe OPERABLE to prevent the RCS from being pressurized above its cafety limit of 2735 psig. The combined relief capacity of all of these 4 Ives is greater than the maximum surge rate resulting from a complet: loss of load assuming no reactor trip until the first Reactor Protte.tive System trip set point is reached (i.e., no credit is taken for a di'*ect reactor trip on the loss of load) and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code,1974 Edition.

TROJ AN-UNIT 1 3/4 4-la H

f REACTOR COOLANT SYSTEM ACTION (Continued) b) Place the following reactor trip system and ESFAS instrumentation channels, associated with the loop not in operation, in their tripped conditions:

1) Overpower aT channel.

2) Overtemperature aT channel.

3). Tavg it with steam Flow - High for Safety Injection.

- Low-Low channel used in the coincidence circu

4) Steam Line Pressure - Low channel used in the coincidence circuit with Steam Flow - High for Safety Injection.

5) Steam Flow-High channel used for Safety Injection.

6) Differential Pressure Between Steam Lines - High Channel used for Safety Injection (trip all bistables which indicate low active loop steam pressure with respect to the idle loop steam pressure).

c) Change the P-8 interlock setpoint from the value specified in Table 3.3-1 to <75% of RATED THERMAL POWER.

2.

THERMAL POWER is restricted to <70% of RATED THERMAL POWER.

Below P-7:

a.

With Keff >1.0, operation below P-7 may proceed provided at least two reactor coolant loops and associated pumps are in operation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

TROJAN-UNIT 1 3/4 4-2

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.1.1 With one reactor coolant loop and associated pump not in operation, at least once per 7 days determine that:

a.

The applicable reactor trip system and/or ESFAS instrumentation channel specified in the ACTION statements above have been placed in their tripped conditions, and b.

The P-8 interlock setpoint has been changed to <75% of RATED THERMAL POWER.

r 1 TROJAN-UNIT 1 3/4 4-2a

REACTOR COOLANT SYSTEM HOT STANDBY, LIMITING CONDITION FOR OPERATION 3.4.1.2 a.

At least two reactor coolant loops shall be OPERABLE.

b.

At least one reactor coolant loop shall be in operation.*

APPLICABILITY: MODE 3 ACTION:

a.

With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation

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and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of ihe reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

TROJAN-UNIT 1 3/4 4-2b

1 REACTOR COOLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPEPATION 3.4.1.3 a.

At least two of the cooling loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop (A) and its associated steam generator and reactor caolant pump,*

2.

Reactor Coolant Loop (B) and its associated steam generator and reactor coolant pump,*

3.

Reactor Coolant Loop (C) and its associated steam generator and reactor coolant pump,*

4.

Reactor Coolant Loop (D) and its associated steam generator and reacter coolant pump,*

5.

Residual Heat Removal Loop (A),**

6.

Residual Heat Removal Loop (B).**

b.

At least one of the above coolant loops shall be in operation.***

APPLICABILITY: MODES 4 and 5 ACTION:

With less than the above required loops OPERABLE, immediately a.

initiate corrective action to return the required loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b.

With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

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• A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 290*F unless 1) the pressurizer steam volume is greater than 200 cubic feet, or 2) the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperatures.

• • The normal or energency power source may be inoperable in MODE 5.

• • • All reactor coolant pumps and residual heat removal pumps may be de-energized for up to I hour provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.

TROJAN-UNIT 1 3/4 4-2c

REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS 4.4.1.3.1 The required residual heat removal loops (s) shall be determined OPERABLE per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side level to be greater than or equal to 0% narrow range indication at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

TROJAN-UNIT 1 3/4 4-2d

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REFUELING OPERATIONS 1

j COOLANT CIRCULATION

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LIMITING CONDITION FOR OPERATION

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3.9.8.1 At least one residual heat removal loop shall be in operation.

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APPLICABILITY: MODE 6.

I ACTION:

1 a.

With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations involving i

an increase in the reactor decay heat load or a reduction in J

boron concentration of the Reactor Coolant System.

Close all j

containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I b.

The residual heat removal loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

The provisions of Specification 3.0.'3 are not applicable.

c.

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I SURVEILLANCE REQUIREMENTS I

4.9.8.1 A residual heat removal loop shall be determined to be in opera-tion and circulating reactor coolant at a ficw rate of >3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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TROJAN-UNIT 1 3/4 9-8

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l REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.*

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

4

)

a.

With less than the required RHR loops OPERABLE, immediately l

initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.

)

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 The required Residual Heat Removal loops shall be determined OPERABLE per Specification 4.0.5.

• The normal or emergency power source may be inoperable for each RHR loop.

TROJAN-UNIT.1 3/4 9-8a

REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.

APPLICABILITY: During movement of fuel assemblies or control rods within the reactor pressure vessel while in MODE 6.

ACTION:

a.

With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel.

b. The provisions of Specification 3.0.3 are not applicable.

J SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be detenmined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per i

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods within the reactor pressure vessel.

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l TROJAN-UNIT 1 3/4 9-10

REFUELING OPERATIONS CONTAINMENT PURGE EXHAUST SYSTEM OPERATION LIMITING CONDITION FOR OPERATION 3.9.13 The Containment purge exhaust fans shall not be operated when irradiated fuel is being moved inside Containment during the first 285 hours0.0033 days <br />0.0792 hours <br />4.712302e-4 weeks <br />1.084425e-4 months <br /> following reactor shutdown.

APPLICABILITY: MODE 6.

ACTION:

a.

With the requirements of the above specification not satisfied, suspend movement of fuel in the Containment Building.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.9.13 It shall be determined prior to fuel movement incide Containment that either the Containment purge exhaust fans are not in operation or that more than 285 hours0.0033 days <br />0.0792 hours <br />4.712302e-4 weeks <br />1.084425e-4 months <br /> have elapsed since reactor sh*;tdown.

TROJAN-UNIT 1 3/4 9-15

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3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and to maintain DNBR above 1.73 during all normal operttions and J

anticipated transients. With one reactor coolant loop not in operation, THERMAL POWER is restricted to < 38 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset.

Either action ensures that the DNBR will be maintained above 1.73.

A loss of flow in two loops will cause a reactor trip if operating above P-7 (10 percent of RATED THERMAL POWER) while a loss of flow in one loop will cause a reactor trip if operating above P-8 (38 percent of RATED THERMAL POWER).

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODES 4 and 5, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE.

Thus, if the reactor coolant loops are not OPERABLE, this specification requires two RHR loops to br DPERABLE.

The operation of one Reactor Coolant Pump or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during baron concentration reductions in the Reactor Coolant System. The reacti /ity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump with one or more RCS cold legs less than or equel to 290 F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50.

The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either I') restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into, or (2) by restricting starting of the RCPs tn when the secondary water temperature of each steam generator is less than 50*F above each of the RCS cold leg temperatures.

3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at 110% of TROJAN-UNIT 1.

B 3/4 4-1

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REFUELING OPERATIONS BASES

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3/4.9.6 MANIPULATOR CRANE OPERABILITY The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of control rods and fuel assemblies 2) each crane has sufficient load capacity to lift a control rod or fuel assembly and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7. CRANE TRAVEL - FUEL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly over other fuel assemblies ensures that no more than the contents of one fuel asembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below la0*F as required during the REFUELING MODE, and (2) suffi-cient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water a'oove the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is aVailable for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

3/9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment venti-lation penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material fran the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

TROJAN-UNIT 1 B 3/4 9-2

e' REFUELING OPERATIONS BASES 3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM The limitaticas on the spent fuel pool exhaust system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

3/4.9.13 CONTAINMENT PURGE / EXHAUST SYSTEM The restriction on the use of Containment purge exhaust system for the first 285 hours0.0033 days <br />0.0792 hours <br />4.712302e-4 weeks <br />1.084425e-4 months <br /> following reactor shutdown during actual fuel movement ensures that the resultant offsite doses from a fuel handling accident inside Containment are within the guidelines of 10 CFR 100. The evalua-tion used to determine that doses would be within 10 CFR 100 assumes assembly activities consistent with Regulatory Guide 1.25 and that all the activity from a single fuel assembly is released directly to the atmosphere.

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i TROJAN-UNIT 1 B 3/4 9-3 i