ML19347F674

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Amend 43 to License DPR-66,revising Tech Specs to Provide Redundancy in Decay Heat Removal Capability & Providing for 23 Feet of Water Over Reactor Pressure Vessel Flange While in Mode 6
ML19347F674
Person / Time
Site: Beaver Valley
Issue date: 05/15/1981
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19347F675 List:
References
NUDOCS 8105260003
Download: ML19347F674 (19)
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Text

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OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-66 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The request and application for amendment by Duquesne Light Company (the licensees) dated March 13. 1981, supplemented March 24,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and 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 C.is 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.

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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-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contiined in Appendices A.and B, as revised through Amendment No. 43, are hereby incorporated in the. license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendcent was effective March 14. 1981.

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Attachment:

Changes to the Technical

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Speci fications Date of Issuance: May 15,1981 O

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-ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.~ 43 TO FACILITY OPERATING LICENSE NO. OPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

Remove Pages Insert Pages l

3/4 4-1 3/4 4-1 3/4 4-2a 3/4 4-2a I

3/4 4-2b 3/4 4-2c 3/4 4-2d 3/4 4-3 3/4 4-3 3/4 4-4 3/4 4-4 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 9-8 3/4 9-8 3/4 9-8a 3/4 9-10 3/4 9-10 B3/4 4-1 B3/4 4-1 B3/4 4-la B3/4 7-5 B3/4 7-5 i

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3/4.4 REACTOR COOLANT' SYSTEM 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 coolant loop and associated pump not in operation, subsequent STARTUP and POWER OPERATION above 26%

of RATED THEiCML POWER raf 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.

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  • See Special Test Exception 3.10.5 BEAVER VALLEY - UNIT 1 3/4 4 ~

Amendment No. 43 e

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ACTION (Continued)

Below P-7:

least I $ >reac.0, operation below P-7 may proceed provided at With X 1

a.

tor coolant loops and associated pumps are in operation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not

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applicable.

SURVEILLANCE RECUIREMENTS 4.4.1.1.1 With one reactor coolant loop and associated pump not in,

operation, at least once per 7 days determine that:

a.

The applic ble 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.

E 71% of RATED THERMAL POWER when the reactor coolant stop val res in the nonoperating loop are closed, or 2.

< 66% of RATED THERMAL POWEP. when the reactor coolant itop valves in the nonoperating loop are open.

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4.4.1.1.2 The power to each of the reactor coolant system loop stop i

valves shall be verified to be removed at least once per 31 days during operation in MODES 1 or 2.

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BEAVER VALLEY - UNIT 1 3/4 4-2a Amendment No. 43 l

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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 4

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 coolent 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 conlant 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 I

(1) no operations are permitted that would cause dilution of the reactor l

coolant system boron concentration and (2) core outlet temperature is main-tained at least 10*F below saturation temperature.

BEAVER V LLEY - UNIT 1 3/4 4-2b Amendment No. 43

P.EACTOR 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 sh'all be in operation.***

APPLICABILITY: MODES 4 and 5 ACTION:

a.

With less thar. the above required icops 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 baron concentration of the Reactor Coolant system aru 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 2CS 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 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 maintained at least 10*F below saturation temperature.

BEAVER VALLEY - UNIT 1 3/4 4-2c Amendment No. 43 e

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4. 4.1. 3. 2 The required reactor coolant pump (s), if not in operation, shall i 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 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 />.

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i BEAVER VALLEY - UNIT 1 3/4 4-2d Amendment No. 43 l

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REACTOR COOLANT SYSTEM ISOLATED LOOP LIMITING CONDITION FOR OPERATION 3.4.1.4 The baron 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 ACTION:

With the requirements of the above specification not satisfied, do not open the isolated loop's stop valves; either increase the baron 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 barated to a SHUTDOWN MARGIN equivalent to at least 1% ak/k at 200*F.

l-SURVEILLANCE REQUIREMENTS

4. 4.1. 4 The boron concentration of an isolated loop shall be determined l

l 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 ta opening e;ther the hot leg or cold leg stop valves of an isolated loop.

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BEAVER VALLEY - UNIT 1 3/4 4-3 Amendment No. 43 m~r-__,,..

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REACTOR COOLANT SYSTEM ISOLATED LOOP STARTUP l.IMITING CON 0! TION FOR OPERATIOl4-3.4.1.5 A reactor coolant loop shall remain isolated until:

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 suberitical 'by at least 1 percent ak/k.

APPLICA8ILITf: ALL MODES.

ACTION:

With the requirements of the above specification not satisfied, suspend startup of the isolated loop.

SURVEILLANCE REGUIREMENTS 4.4.1. 5.1_ The isolated loop cold leg tamparature shall be determined to -

l be within 20*F of the highest cold leg temperature of the operating l

l loops within 30 minutes prior to opening the cold leg stop valve.

4.4.1. 5.2 The reactor shall be determined to be suberitical by at least l

I percent ak/k within 30 minutes prior to opening the cold les stop valve.

l BEAVEA VALLEY - UNIT 1 3/44-4 Amendment No. 43

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PLANT SYSTEMS 3/4.7.10 RESIDUAL HEAT REMOYAL SYSTEM -Tavn > 350*F l'

b This specification deleted.

BEAVER VALLEY - UNIT 1 3/4 7-24 Amendment No. 43 6

PLANT SYSTEMS 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM - T

< 350*F ava-This specification deleted.

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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 remova'l 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 contairaent 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 CORE ALTERATIONS in the vicinity of the reactor pressure sessel (hot) legs.

c.

The residual heat removal loop may be removed from operation 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 nozzles provided there is at least 23 feet of water above the

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top of the reactor vessel flange.

d.

The provisions of Specification. 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

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4.9.8.1 At least one residual heat removal loop shc11 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 baron dilution changes and > 1000 gpm for decay heat removal when the Reactor Coolant System is in the drained down condition within the loops.

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BEAVER VALLEY - UNIT 1 3/4 9-8 Amendment No. 43 r_

I REFUELING CONDITION FOR OPERATION LOW WATER LEVEL LIMITING CONDITION FOR OPERATION

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3 3.9.8.2 Two Residual Heat Removal (RHR) loops shall be OPERABLE.*

l 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 Hbat Removal loops shall be determined OPERABLE ber soecification 4.0.5.

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

BEAVER VALLEY - UNIT 1 3/4 9-8a Amendment No. 43

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REFUELING OPERATIONS 3/4 9.10 ' DATER 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:

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.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall ;e determined 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

thereefter during movement of fuel assemblies or control rods.

I BEAVER VALLEY - UNIT 1 3/4 9-10.

Amendment No. 43

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3/4.4 REACTOR COOLANT SYSTEM BASES 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 removal capability for removing decay heat; however, single failure con-siderations require that two loops be OPERABLE.

I In MODES 4 and 5, a single re&ctor coolant loop or RHR subsystem 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.be OPERABLE.

The operation of one Reactor Coclant 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 j

Coolant System.

The reactivity change rate associated with boron reduction will, therefore, be witnin the capability of operator recognition and control.

The restrictionr, on starting a Reactor Coolant Pump with one or more RCS cold legs less 'han or equal to 275'F are provided to prevent RCS c

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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

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l BEAVER VALLEY - UNIT 1 B 3/4 4-1 Amendment No. 43

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l 3/4.4 REACTOR COOLANT SYSTEM BASES a

3/4.4.1 REACTOR COOLANT LOOPS (continued) l i

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 restricting 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.

l The requirement to maintain the boron concentration of an isolated loop greater ij.

or equal to the boron concentration of the operating 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-l assurance of the adequacy of the boroa concentration in the isolated loop.

Operating the isolated loop on recirculating flow for at least 90 minutes prior to opening its step valves ensures adequate mixing of the coolant in this loop and prevents any reactivity affects 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 and 3/4.4.3 SAFETY VALVES l

The pressurizer code safety valves operate to prevent the RCS from l

being pressurized above its Safety Limit of 2735 psig. Each safety valva l

is designed to relieve 345,000 lbs. per hour of saturated steam at the l

valve set point. The relief capacity of a single safety valve is adequate to t

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BEAVER VALLEY - UNIT 1 B 3/4-la Amendment No. 43

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM The OPERA 8ILITY of the control room ventilation system ensures that

1) the ambient air temperature does not excaed 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 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 requiiements 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 en sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable ifmits in the event of ingestion or inhalation of the source material.

The limitations on removable contamination for sources requiring leak testing, including 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 body irradiation if the source material is inhaled or ingested.

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

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REFUELING OPERATIONS PASES 3/4.9.5 COINUNICATIONS The requirements for cour.unications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditiens during COPE ALTERATIONS.

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 H AVEL - SPENT FUEL STORAGE BUILDING l

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 l

contents of one fuel assembly will be ruptured in the event of a fuel handling. accident. This assumption is consistent with the activity release assumed in the accident analyses.

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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 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 baron dilution incident and prevent boron stratification.

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

feet of water above 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.

3/4.9.9 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.

BEAVER VALLEY - UNIT 1 B 3/4 9-2 Amendment No. 43

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