ML19350A856

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Proposed App a Tech Specs Re Decay Heat Removal Capability
ML19350A856
Person / Time
Site: Beaver Valley
Issue date: 03/13/1981
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML19350A855 List:
References
NUDOCS 8103170151
Download: ML19350A856 (17)
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Text

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3/4.4 REACTOR COOLANT SYSTEM l

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

APPLICABILITY: MODES 1 and 2

  • ACTION:

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

a. With one reactor coclant loop and associated pump not in operation, subsequent STARTUP and POWER OPERATION above 26%

of RATED THERMAL POWER may procee'd 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 2 loop operation.

  • See Special Test Exception 3.10.5

'- BEAVER. VALLEY - UNIT.1 3/4 4-1 DESIRED WORDING:

'O108170$\

REACTOR COOLANT SYSTEM _

ACTION (Con'tinued)

Below P-7:

a. With K 1 least Twb >reac.0, operation tor coolant loops below P-7 maypumps and associated proceedareprovided in at operation.
b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. ,

4 SURVEILLANCE REQUIREMENTS 4.4.1.1.1 With one recctor coolant loop and associated pump not in ,

operation, at least once per 7 days determine that:

a. The applicable reactor trip system channels specified in the ACTION statements above have been placed in their tripped conditions and,
b. The P-8 interlock setpoint is within the following limits if

'the P-8 interlock was reset for 2 loop operation:

1. < 71% of RATED THERMAL POWER when the reactor coolant i' top valves in' the nonoperating . loop are closed, or
2. < 66% of RATED THERMAL POWER when the reactor coolant i' top valves in the nonoperating loop are open.

4.4.1.1.2 The power to each of the reactor coolant system loop stop valves shall be verified to be removed at least once per 31 days during operation in MODES 1 or 2.

a BEAVER VALLEY - UNIT 1 3/4 4-2a DESIRED WORDING

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REACTOR COOLANT SYSTEM HOT STANDBY

, LIMITING CONDITION FOR OPERATION 3.4.1.2 a. At least two of the reactor coolant loops listed below shall be OPERABLE:

1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant 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.
b. At least one of the above coolant loops 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 one of 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 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 the reactor coolant system boron concentration and (2) core outlet temperature is main-tained at least 10 F below saturation temperature.

BEAVER VALLEY - UNIT 1 3/4 4-2b DESIRED WORDING

REACTOR COOLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE:

1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant 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. Residual Heal Removal Pump (A) and a heat exchanger,**
5. Residual Heat Removal Pump (B) and a second heat exchanger.**
b. At least one of the above coolant loops shall be in operation.***

APPLICABILITY: MODES 4 and 5 ACTION:

a. With less than the above required loops OPERABLE, immediately 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.
  • A reactor coolant pump shall not be started with one or more of the RCS cold leg temperatures less than or equal to 275 F unless: 1) the pressurizer water volume is less than 1120 cubic feet or 2) the secondary water tempera-ture of each steam generator is less than 50 F above each of the RCS cold leg temperatures.
    • The normal or emergency power source may be inoperable in MODE 5.
      • All reactor coolant pumps and Residual Heat Removal pumps may be de-energized for up to l hour provided: 1) no operations are permitted that would cause dilution of the Octor coolant system boron concentration and 2) core outlet temperature is i.Mntained at least 10 F below saturation temperature.

BEAVER VALLEY - UNIT 1 3/4 4-2c DESIRED WORDING

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required residual heat removal loop (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 c verifying secondary side level equivalent to 12% narrow range 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 />.

BEAVER VALLEY - UNIT 1 3/4 4-2d DESIRED WORDING

REACTOR COOLANT SYSTEM ISOLATED LOOP LIMITING CONDITION FOR OPERATION 3.4.1.4 The boron concentration of an isolated loop shall be maintained greater than or equal to the boron concentration of the operating loops, except when the loop is drained for maintenance.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 o ACTION:

With the requirements of the above specification not satisfied, do not open the isolated loop's stop valves; either increase the boron concen-tration of the isolated loop to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-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 /> with the unisolated portion of the RCS borated to a SHUTDOWN MARGIN equivalent to at least 1% ak/k at 200 F.

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SURVEILLANCE REQUIREMENTS 4.4.1.2 The boron concentration of an isolated loop shall be determined to be greater than or equal to the baron concentration of the operating loops at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and within 30 minutes prior to opening either the hot leg or cold leg stop valves of an isolated loop.

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l BEAVER VALLEY - UNIT 1 3/4 4-3 DESIRED WORDING

REACTOR CCOLANT SYSTEM ISOLATED LOOP STAnTUP LIMITING CONDITION FOR OPERATION 3.4.1. 5 A reactor coolant loop shall remain isolated until: l

a. The isolated loop has been operating on a recirculation flow of

> 125 gpm for at least 90 minutes and the temperature at the cold leg of the isolated loop is within 20*F of the highest cold leg temperature of the operating loops.

b. The reactor is subcritical by at least 1 percent ak/k.

APPLICABILITY: ALL MODES. . I ACTION:

With the requirements of the above specification not satisfied, suspend -

startup of the isolated loop.

SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The isolated loop cold leg temperature shall be determined to be within 20*F of the highest cold leg temperature of the operating loops within 30 minutes prior to opening the ec16 leg stop valve.

4.4.1.3.2 The reactor shall be determined to be subcritical by at least 1 percent ak/k within 30 minutes prior to opening the cold leg stop valve.

BEAVER VALLEY - UNIT 1 3/44-4 DESIRED WORDING e

I PLANT SYSTEMS 3/4.7.10 RESIDUAL HEAT REMOVAL SYSTEM -Tavg 1 350 F i-l 4

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This spcification deleted.

h BEAVER VALLEY --UNIT 1 3/4. 7-24:.

DESIRED WORDING

PLANT SYSTEMS 3/4.7.11 RESIDUAL. HEAT REMOVAL SYSTEM - T avg < 350*F 4

t This specification deleted.

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I BEAVER-VALLEY - UNIT 1 3/4 7-25 DESIRED WORDING

REFUELING OPERATION 3/4 9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.

APPLICABILITY: MODE 6 ACTION: ,

a. With less than one residual heat removal loop in operation, except as provided in b below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all 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 />.
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) i legs.

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c. The residual heat removal loop may be removed from operation l

for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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

. Ultrasonic In-service Inspection inside the reactor vessel l nozzles provided there is at least 23 feet of water above the top of the reactor vessel flange.
d. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at a flow rate of > 3000 gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when making boron dilution changes and > 1000 gpm for decay heat removal when the Reactor Coolant System is in the drained down condition within the loops.

BEAVER VALLEY - UNIT 1 3/4 9-8 DESIRED WORDING

t REFUELING CONDITION FOR OPERATION LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two 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:

a. With less than the required RHR loops OPERABLE, immediately 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 by verifying flow > 1000 gpm.

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

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i l BEAVER VALLEY - UNIT 1 3/4 9-Sa l DESIRED WORDING l

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REFUELING OPERATIONS 3/4 9.10 WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION'c 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:

With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SUPVEILLANCE REQUIREMENTS 4.9.10 The r avel shall be determined to be at 'least its minimum required depth withit ...s prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter duruig movement of fuel assemblies or control rods.

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1 BEAVER VALLEY - UNIT 1 3/4 9-10 DESIRED WORDING

3/4.4 REACTOR COOLANT SYSTEM BASES i

3/4.4.1 REACTOR COOLANT LOOPS The plant is designed to operate with all reactor coolant loops in operation and maintain DNBR above 1.30 during all normal operations and anticipated transients. In Modes 1 and 2, with one reactor coolant loop not in operation, THERMAL POWER is restricted to < 31 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset. Either action ensures that the DNBR will be maintained above 1.30. A loss of flow in two loops will cause a reactor trip if operating above P-7 (11 percent of RATED THERMAL POWER) while a loss of flow in one loop will cause a reactor trip if operating above P-8 (31 percent of RATED THERMAL POWER).

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

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

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

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 boron concentration reductions in the Reactor Coolant System. The reactivity 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 equal tc 276'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 BEAVER VALLEY - UNIT 1 B 3/4 4-1 DESIRED WORDING

3/4.4 REACTOR COOLANT SYSTEM BASES 1

3/4.4.1 REACTOR COOLANT LOOPS (continued) of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restrie. ting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50 *F above each of the RCS cold leg temperatures.

The requirement to maintain the baron concentration of an isolated .

loop greater than or equal to the boron concentration of the operating i

loops ensures that no reactivity addition to the core could occur during startup of an isolated loop. Verification of the boron concentration in an idle loop imediately prior to opening the stop valves provides a re-

, assurance of the adequacy of the boron concentration in the isolated loop.

Operating the isolated loop on recirculating flow for at least 90 minutes prior to opening its stop valves ensures adequate mixing of the coolant in this loop and prevents any reactivity effects due to boron concentra-tion stratifications.

Startup of an idle loop will inject cool water from the loop into the core. The reactivity transient resulting from this cool water injection is minimized by delays isolated loop startup until its temperature is within 20*F of the operating loops. Making the reactor subcritical prior to loop startup prevents any power spike which could result from this cool water induced reactivity transient.

3/4.4.2 a'nd 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 l is designed to relieve 345,000 lbs. per hour of saturated steam at the valve set point. The relief capacity of a single safety valve is adequate to l

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BEAVER VALLEY - UNIT 1 B 3/4-la DESIRED WORDING

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM 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 sl1 credible accident conditions. The OPERABILITY of this system in conjunction with control room design pro-visions 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 consisten with the requirements of General Design Criteria 10 of Appendix "A",10 CFR 50.

3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS)

The OPERABILITY of the SLCRS ensures that radioactive materials leaking from equipment following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.

The limitations on removable contamination for sources requiring leak testing, Oncluding alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakage of sour'ces excluded from the requirements of this specification represent less than one maximum permissible body burden for total bcdy irradiation if the source material is inhaled or ingested.

3/4.7.10 and 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM (RHR)

Deleted BEAVER VALLEY - UNIT 1 B 3/4 7-5 DESIRED WORDING 4.

i REFUELING OPERATIONS i

BASES 3/4.9.5 COPNUNICATIONS l 2

The requirements for comunications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility i status or core reactivity conditions during CORE ALTERATIONS.

l 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 j engaged during lifting operations.

l 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING 1

The restriction on movement of loads in excess of the normal weight of a fuel assembly over other fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity i release assumed in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION  !

i The requirement that at least one residual heat removal (RHR) loop be in I operation ensures that 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained throughout the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

i The requirement to have two RHR loops OPERABLE when there is less than 23

', feet of water above the reactor pressure vessel flange ensures that a single l 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 l 23 feet of water above the reactor pressure vessel flange, a large heat sink L 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.

I 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge

< penetrations will be automatically isolated upon detection of high radiation levels within the containment. The integrity of the containment penetrations of this system is required to restrict the release of radioactive material from the containment atmosphere to acceptable levels which are less than '

. those listed in 10 CFR 100. Applicability in MODE 5, although not an NRC safety requirement, will provide additional protection against small releases of radioactive material from the containment during maintenance activities.

i BEAVER VALLEY - UNIT 1 B 3/4 9-2 -

DESIRED WORDING  !

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