ML19332D558

Amends 173,176 & 144 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Revising Reactor Pressure Requirements at Which HPCI Sys & RCIC Sys Must Be Operable

ML19332D558
Person / Time
Site:	Browns Ferry
Issue date:	11/24/1989
From:	Black S Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332D559	List: ML19332D558 ML19332D565
References
NUDOCS 8912040146
Download: ML19332D558 (27)

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 173 License No. DPR-33 l

-1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee)-datedAugust9,1989,complieswiththestandardsand p

requirements of the Atomic Energy Act of 1954, as amended (the Act),

p and the Commission's rules and regulations set forth in.10 CFR L

Chapter I; L

B..

The facility will operate in confomity with the application, the L

provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by I

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Commission's regulations;-

D.

The issuance of this amendment will not be inimical to the comon 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 Conenssion's regulations and all applicable requirements have been satisfied.

8912040146 891124

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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. OPR-33 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as-revised through Amendment No.173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.-

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1-e#A(

ne Black, Msta Director for Projects L

TVA Projects Division Office of Nuclear Reactor Regulatien-

Attachment:

Changes to the Technical Specifications Cate of Issuance:

tiovember 24, 1989 l

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1 ATTACHMENT TO LICENSE AMENDMENT NO. 173 FACILITY OPERATING LICENSE NO. DPR-33 DOCKETNO.50d59 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

4.

REMOVE-INSERT 3.5/4.5-12 3.5/4.5-12*

3.5/4.5-13 3.5/4.5-13 l'

3.5/4.5-14 3.5/4.5-14 3.5/4.5-15 3.5/4.5-15 3.5/4.5-30 3.5/4.5-30 3.5/4.5-31 3.5/4.5-31 l

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3.5/4.5 CORE AND CONTAINMENT'C00 LING SYSTEMS l

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I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.0 RHR Service Water and Emeraency 4.5.C RHR Service Water and Emeraency Eauinment Coolina Water Systema

.Eautoment Coolina Water Systems (EECWS) (Continuedl (EECWS) (Continued) 4.

One of the D1 or D2 RHRSW

4. No additional surveillance pumps assigned to the RHR is required, heat exchanger supplying the standby coolant supply connection may be inoperable for a period not to exceed 30 days provided the OPERABLE pump is aligned to supply the RHR heat exchanger header and the associated diesel generator and essential control valves are OPERABLE.

l S.

The standby coolant supply capability may be inoperable for a period not to exceed 10 days.

6.

If Specifications 3.5.C.2 through 3.5.C.5 are not s

met, an orderly shutdown shall-be initiated and the unit placed in the COLD SHUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7.

There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.

BFN 3.5/4.5-12 Amendment Nos. 153, 169 Unit 1

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[A 3'. 5 /4. 5' CORE AND CONTAINMENT' COOLING SYSTEMS' LIMITING CONDITIONS FOR OPEkATION SURVEILLANCE REQUIREMENTS ~

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-3.5.C nut Service Water and Emernenev 4.5.C RRR Service Water and Emeraency Eauinment Coolina Water Systems

' Eauinment Coolina Water Systems' (EECWS) (Continued)

(EECWS) (Continued) 4.

One of the D1 or D2 RHRSW

4. No additional surveillance pumps. assigned to the RHR is required, heat exchanger supplying the standby-coolant supply connection may be inoperable for a period not to exceed 30 days provided the OPERABLE pump is aligned to supply the RHR heat exchanger header and the associated diesel

. generator and essential control valves are OPERABLE.

5.

The standby coolant supply capability may be inoperable for a period not to exceed 10 days.

.r 6.

If Specifications 3.5.C.2 l-through 3.5.C.5 are not met, an' orderly shutdown shall be initiated and the unit placed in the COLD L

SHUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7.

There shall'be at least 2 RERSW pumps,. associated

'with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing-irradiated fuel.

BFN 3.5/4.5-12 Amendment Nos. 153, 169 Unit 1

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~ CORE AND CONTAINMENT COOLING SYSTEMS 325/4.5 4

_ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.D.

.Eauinment Area LJolers 4.5.D Eauiement Area Coolers.

1.

The equipment area cooler

1. Each' equipment area cooler associated with each RHR is operated in conjunction pump and the equipment with the equipment served area _ cooler associated.

by that particular cooler; with each set-of core therefore, the equipment shu.

spray pumps (A and C area coolers are tested at or B and D) must be the same frequency as the

.0PERABLE at all times pumps which they serve, when the pump or pumps served by that specific.

cooler is considered to be OPERABLE.

2.-

When an equipment area cooler is not OPERABLE, the pump (s) served by that cooler must be considered inoperable for Technical Specification purposes.

gc E.

High Pressure Coolant Iniection E. Hinh Pressure Coolant System (HPCIS)

Iniection System (NPCIS) l; l

1.

The HPCI system.shall be 1.

HPCI Subsystem testing OPERABLE whenever there is shall be performed as irradiated fuel in the follows:

reactor vessel and the

?

reactor vessel pressure a.

Simulated Once/18 is greater than 150 psig, Automatic months r

except as.specified in Actuation Specification 3.5.E.2.

Test L

OPERABILITY shall be

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determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b.

Pump Per after reactor steam pressure OPERA-Specification reaches 150 psig from a COLD BILITY 1.0.MM CONDITION, or; alternatively PRIOR TO STARTUP by using an c.

Motor Oper-Per auxiliary steam supply.

ated Valve Specification OPERABILITY 1.0.MM d.

Flow Rate at once/3 normal months reactor vessel operating pressure BFN 3.5/4.5-13 Amendment No. 159, 173 Unit 1

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3.$/4.5 CORE AND CONTAINMENT COOLING SYSTEMS

' LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.E Hlah Pressure Coolant In_iection 4.5.E High Pressure Coolant Iniection System (HPCIS)

System (HPCIS) h 4.5.E.1 (Cont'd) e.

Flow Rate at once/18 150 pois months The HPCI pump shall deliver at least C

5000 gpm during each flow rate test.

f.. Verify that Once/ Month each valve-(manual, power-o operated, or automatic) in the injection flow-path that is not locked,. sealed, or otherwise secured in position, is in its correct

• position.-

2.

If the HPCI system is

2. No additional surveillances inoperable, the reactor may are required.

= remain in operation Tor a period not to exceed 7 days, provided the ADS, CSS, RHRS (LPCI), and RCICS are OPERABLE.

Except that an automatic 3.

If Specifications 3.5.E.1 or'3.5.E.2 are not met, valve capable of automatic an orderly shutdown shall return to its ECCS position be initiated and the when an ECCS signal is reactor vessel pressure present may be in a l

shall be reduced to 150 position for another mode pois or less within 24' of operation.

hours.

F.

Reactor Core Isolation Coolina F.

Reactor Core Isolation Coolina System (RCICS)

System (RCICSS 1.

The RCICS shall be OPERABLE

1. RCIC Subsystem testing shall whenever'there is irradiated be performed as follows:

fuel in the reactor vessel and the reactor vessel

a. Simulated Auto-Once/18 pressure is above 150 psig, matic Actuation months except ao specified in Test 3.5.F.2.

OPERABILITY shall BFN 3.5/4.5-14 Amendment No. 159, 169, 173 Unit 1

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CORE AND CONTAIRMENT COOLING SYSTEMS 4

LIMITING CONDITIONS FOR OPERATION SURVIILLANCE REQUIREMENTS 3.5.F.

Reactor Core Isolation Coolina 4.5.F Reactor Core Isolation Coolina System (RCICS)

System (RCICS) 3.5.F.1 (Cont'd) 4.5.F.1 (Cont'd) be determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

b. Pump Per after reactor steam pressure OPERABILITY Specifi-reaches 150 pais from a COLD cation CONDITION or alternatively 1.0.MM PRIOR TO STARTUP by using an auxiliary steam supply,

c. Motor-Operated Per Valve Specifi-OPERABILITY cation 1.0.MM d.

Flow Rate at Once/3 normal reactor months vessel operating pressure e.

Flow Rate at once/18 150 psig months The RCIC pump shall deliver at least 600 gpm during each flow test.

2.

If the,RCICS is inoperable, f.

Verify that once/ Month-the reactor may remain in each valve operation for a period not (manual, power-to. exceed 7 days if the operated, or HPCIS is OPERABLE during automatic) in the such time.

injection flovpath that is not locked,

.3.

If Specifications 3.5.F.1 sealed, or other-or 3.5.F.2 are not met, an wise secured-in orderly shutdown shall be position, is in its initiated and the reactor correct

• position.

shall be depressurized to less than 150 psig within

2. No additional surveillances 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

are required.

• Except that an automatic valve capable of automatic return to its normal position when a signal is present may be in a position for another mode of operation.

BFN 3.5/4.5-15 Amendment No. 169, 173 Unit 1

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[3,5-ggggg'(Cont'd)

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3.5.E.

Himh Pressure Coolant Iniection Svotem (NPCIS)

The NPCIS is provided to assure that the reactor core'is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss of coolant which does not result in rapid reactortobeshutdownwhilemaintaining-sufficientreactorvesselwaterl fdepressurization of the. reactor vessel. The HPCI system permits the

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' level' inventory until the vessel is depressurized. The HPCIS continues to operate until reactor vessel pressure is below the pressure at which.

h LPCI operation or Core Spray system operation maintains core cooling.

The capacity of the system is selected to provide the required core l

cooling. The HPCI pump is designed to pump 5000 spm at-reactor pressures a

between 1120 and 150 pais. The HPCIS is not required to be operable below 150 psig since this is well within the range of the low pressure cooling-systems and below the pressure of any events for which HPCI is required to provide core cooling.

a The HPCIS is not designed to operate at full capacity until reactor pressure exceeds 150 pais and-the steam supply to the HPCI turbine is automatically-isolated before reactor pressure decreases below 100 psig.

The ADS, CSS, and'RHRS (LPCI) must be OPERABLE when starting up from a

' Cold Condition. Steam pressure is sufficient at 150 psig to run the HPCI turbine for operability testing yet, still below the shutoff head of the CSS and RHRS pumps so they will inject water into the vessel if required. -The ADS provides additional backup to reduce pressure to the range where the CSS and RHRS will inject into the vessel if necessary.

Considering the low reactor pressure, the redundancy and availability of CSS, RHRS, and ADS during startup from a Cold Condition, twelve hours is allowed as s reasonable time to demonstrate HPCI operability once sufficient steam pressure becomes available. The alternative to demonstrate HPCI operability prior to startup using auxiliary steam is provided-for plant operating flexibility.

With the HPCIS inoperable, a seven-day period to return the system to service is justified based on the availability of the ADS, CSS, RHRS (LPCI) and the RCICS. The availability of these redundant and diversified systems provides adequate assurance of core cooling while HPCIS is out of service.

The surveillance requirements, which are based on industry codes and standards, provide adequate assurance that the HPCIS will be OPERABLE when' required.

BFN 3.5/4.5-30 Amendment No. 169, 173 Unit 1

3.5 BASES'(Cont'd)'

Reactor Core Isolation Coolina System (RCICS) 3.5.F The RCICS functions to provide core cooling and makeup water to the reactor vessel during shutdown and isolation from the main heat sink and l

for certain pipe break accidents. The RCICS provides its design flow between 150 pais and 1120 pais reactor pressure.

Below 150 pais, RCICS is not required to be operable since this pressure is substantially E

.below:that for any events in which RCICS is required to provide core cooling..RCICS will continue to operate below 150 psig at reduced flow until it: automatically isolates at greater than or equal to 50 psig reactor steam pressure.

150 psis is also below the shutoff head of the CSS and RHRS,1thus, considerable overlap exists with the cooling systems that provide core cooling at low reactor pressure.

The ADS, CSS, and RHRS (LPCI) must be OPERABLE when starting up from a Cold Condition. Steam pressure is sufficient at 150 pais to run the RCIC turbine for operability testing, yet still below the shutoff head i

of the CSS and RHRS pumps so they will inject water into the vessel if required.

Considering the low reactor pressure and the availability of the low pressure coolant systems during startup from a Cold Condition, twelve hours is allowed as a reasonable time to demonstrate RCIC operability once sufficient steam pressure becomes available. The alternative to demonstrate RCIC operability prior to startup using auxiliary steam is provided for plant. operating flexibility.

With the RCICS inoperable, a seven-day period to return the system to service is justified based on the availability of the HPCIS to cool the core and upon consideration that the average risk associated with failure of the RCICS to cool the core when required is not increased.

The surveillance requirements, which are based on industry codes and standards, provide adequate assurance that the RCICS will be OPERABLE when required.

3.5.G-Automatic Deoressurization System (ADS)

This specification ensures the operability of the ADS under all conditions for which the depressurization of the nuclear system is an essential response to station abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low-pressure coolant injection (LPCI) and the core spray subsystems can operate to protect the fuel barrier. Note that this specification applies only to the automatic feature of the pressure relief system.

L Specification 3.6.D specifies the requirements for the pressure relief function of the valves.

It is possible for any number of the valves i.

assigned to the ADS to be incapable of performing their' ADS functions because of instrumentation failures, yet be fully capable of performing their pressure relief function.

t BFN 3.5/4.5-31 Amendment No. 173 Unit 1 mm-,

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NUCLEAR REGULATORY COMMISSION

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 License No. DPR-52 l

1.

The Nuclear Regulatory Consission (the Conunission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 9,1989, complies with the standards-and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Connission'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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l

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 o

of the Conunission's regulations and all applicable requirements have been satisfied.

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2..

Accordingly, the license is amended by changes to the Technical Specifications-as indicated in the attachinent to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby

' amended to read as follows:

-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as

revised through Amendment No.176, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with r

the Technical Specifications.

3.

ThislicenseamendmentiseffEctiveasofitsdateofissuanceandshall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0'

Su e Black, Assi nt Director 1

for Projects TVA Projects C' Hion Office of Nucle actor Regulatio'n' ~

Attachment:

Changes tolthe Technical Specifications Date of Issuance:

November 24, 1989 1

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. ATTACHMENT T0' LICENSE AMENDMENT NO j76 0'

FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260-I k

, Revise the Appendix-A Technical Specifications by removing the pages.

' identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE' INSERT 3.5/4.5-12 3.5/4.5-12*

i 3.5/4.5-13' 3.5/4.5-13 3.5/4.5-14 3.5/4.5-14 3.5/4.5-15 3.5/4.5-15

'3.5/4.5-28 3.5/4.5-28 3.5/4.5-29 3.5/4.5-29 f

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2.5/4.$

C0tt Aun CONTA1 g NT COOLING SYSTEMS LIMITING 00NDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.C art Service Water and Emermenev 4.5.C nun Sarrice Water and Emeraenev l

Eauia=amt Coolina Water Systems Eaulement Coolina Water Systems (EECWS) (Continued)

(EECWS) (Continued) 4.

Three of the D1, D2, B1, B2

4. No additional surveillance RNRSW pumps assigned to the is required.

RHR heat exchanger supplying the standby coolant supply connection may be inoperable for a period not to exceed 30 days o

provided the OPERABLE pump is aligned to supply the RRR heat exchanger header and the associated diesel generator and essential control valves are OPERABLF.

5.

The standby coolant supply capability may be inoperable for a period not to exceed l

10 days.

6.

If Specifications 3.5.C.2 through 3.5.C.5 are not met, an orderly shutdowti shall be initiated and the unit placed in the COLD 1

SKUTDOWN CONDITION within l

3 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7.

There shall be ft least 2 RHRSW pumps, associated-with the selected RHR pumps, aligned for RER heat exchanger service for each reactor vessel containing irradiated fuel.

- BrN 3.5/4.5-12 Amendment No. 149, 169 Unit 2

(

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS i

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.D raula= ant Area Coolers 4.5.D Eaulement Area Coolers 1.

The equipment area cooler

1. Each equipment area cooler associated with each RHR is operated in conjunction pump and the equipment with the equipment served

'3 area cooler associated by that particular cooler; with each set of core therefore, the equipment spray pumps (A and C area coolers are tested at or B and D) must be the same frequency as the OPERABLE at all times pumps which they serve, when the pump or pumps served by that specific cooler is considered to be OPERABLE.

2.

When an equipment area cooler is not OPERABLE, the pump (s) served by that cooler must be considered inoperable for Technical r

Specification purposes.

E.

Hlah Pressure Coolant Iniection E. Himh Pressure Coolant System (HPCIS1 Iniection System (KPCIS) 1.

The HPCI system shall be 1.

HPCI Subsystem testing OPERABLE whenever there is shall be performed as irradiated fuel in the follows:

reactor vessel and the reactor vessel pressure a.

Simulated once/18 is greater than 150 psig, Automatic months except as specified in Actuation Specification 3.5.E.2.

Test OPERABILITY shall be determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b.

Pump Per after reactor steam pressure OPERA-Specification reaches 150 psig from a COLD BILITY 1.0.MM CONDITION, or alternatively PRIOR TO STARTUP by using an c.

Motor Oper-Per auxiliary steam supply, ated Valve Specification OPERABILITY 1.0.MM d.

Flow Rate at Once/3 normal months reactor vessel operating pressure BFN 3.5/4.5-13 Amendment No. 155, 176 Unit 2

1

, 3.5/4.5.C0tt AND CONTifMMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.E Hiah Pressure Coolant Iniection 4.5.E Hiah Pressure. Coolant Iniection Svatan (RPCIS)

System (NPCIS) l 4.5.E.1 (Cont'd) e.

Flow Rate at Once/18 150 pais months 1

The HPCI pump shall I

deliver at least 5000 spm during each flow rate test.

f.

Verify that Once/ Month each valve

!l (manual, power-operated, or automatic) in the injection flow-path that is not i

locked, sealed, or otherwise secured in position, is in its correct

• position.

2.

If the HPCI system is

2. No additional surveillances inoperable, the reactor may are required.

remain.in operation for a l

period not to exceed 7 days, l

provided the ADS, CSS, RHRS i

(LPCI), and RCICS are OPERABLE.

3.

If Specifications 3.5.E.1 Except that an automatic or 3.5.E.2 are not met, valve capable of automatic an orderly shutdown shall return to its ECCS position be initiated and the when an ECCS signal is reactor vessel pressure present may be in a i

shall be reduced to 150 position for another mode l

psig or less within 24 of operation.

E hours.

F.

Reactor Core Isolation Coolina F.

Meactor Core Isolation Cotlina System (RCICS)

System (RCICS) l 1.

The,RCICS shall be OPERABLE

1. RCIC Subsystem testing shall whenever there is irradiated be performed as follows:

fuel in the reactor vessel and the reactor vessel

a. Simulated Auto-Once/18 pressure is above 150 psig, matic Actuation months except as specified in Test 3.5.F.2.

OPERABILITY shall BFN 3.5/4.5-14 Amendment No. 155. 169. 176 Unit 2 teer,-=

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3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS j.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F.

Raaeter core Isolation Coolina 4.5.F Reactor Core Isolation Coolina gygtpa (RCICS)

System (RCICS) 3.5.F.1 (Cont'd) 4.5.F.1 (Cont'd) be determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

b. Pump Per after reactor steam pressure OPERABILITY Specifi-reaches 150 psig from a COLD cation CONDITION or alterna**vely 1.0.MM

' PRIOR TO STARTUP by < ins an auxiliary steam serga,

c. Motor-Operated Per Valve Specifi-OPERABILITY cation 1.0.MM d.

riov Rate at Once/3 normal reactor months vessel operating pressure e.

Flow Rate at once/18 150 psig months The RCIC pump shall deliver at least 600 spm during each flow test.

2.

If the RCICS is inoperable, f.

Verify that once/ Month the reactor may remain in each valve operation for a period not (manual, power-to exceed 7 days if the operated, or HPCIS is OPERABLE during automatic) in the such time.

injection flowpath that is not locked, 3.

If Specifications 3.5.F.1 sealed, or other-or 3.5.F.2 are not met, an vise secured in orderly shutdown shall be position, is in its initiated and the reactor correct

• position, shall be depressurized to less than 150 paig within

2. No additional surveillances 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

are required.

• Except that an automatic valve capable of automatic return to its normal position when a signal is present may be in a position for another mode of operation.

BFN 3.5/4.5-15 Amendment No. 169, 176 Unit 2

i 1

• 3.5 BASES (Cont'd) 3.3.E. Hiah Pressure Coolant Iniection System (HPC[1]

The NPCIS is provided to assure that the ret' tor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss of coolant which 'oes not result in rapid depressurization of the reactor vessel. The HPCI system permits the l

reactor to be shut down while maintaining sufficient reactor vessel l

water level inventory until the vessel is depressurized. The HPCIS

)

continues to operate until reactor vessel pressure is below the pressure

-)

at which LPCI operation or Core Spray system operation maintains core cooling. The capacity of the system is selected to provide the required l

core cooling. The HPCI pump is designed to pump 5000 spa at reactor pressures between 1120 and 150 pais. The NPCIS is not required to be operable below 150 pais since this is well within the range of the low pressure cooling systems and below the pressure of any events for which HPCI is required to provide core cooling.

The NPCIS is not designed to operate at full capacity until reactor pressure exceeds 150 psig and the steam supply to the HPCI turbine is automatically isolated before reactor pressure decreases below 100 psig.

The ADS, CSS, and RHRS (LPCI) must be OPERABLE when starting up from a Cold Condition. Steam pressure is sufficient at 150 pais to run the HPCI turbine for operability testing yet still below the shutoff head of the CSS and RHRS pumps so they will inject water into the vessel if required. The ADS provides additional backup to reduce pressure to the range where the CSS and RHRS will inject into the vessel if necessary. Considering the low reactor pressure, the redundancy.and availability of CSS, RHRS, and ADS during startup from a Cold Condition, I

twelve hours is allowed as a reasonable time to demonstrate HPCI l.

operability once sufficient s:eam pressure becomes available. The alternative to demonstrate HPCI operability prior to startup using auxiliary steam is provided for plant operating flexibility.

With the HPCIS inoperable, a seven-day period to return the system to service is justified based on the availability of the ADS, CSS, RHRS (LPCI) and the RCICS. The availability of these redundant and diversified systems provides adequate assurance of core cooling while HPCIS is out of service.

The surveillance requirements, which are based on industry codes and standards, provide adequate assurance that the HPCIS will be OPERABLE i

when required.

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BEN 3.5/4.5-28 Amendment No. 169, 176 Unit 2

1 3.5 BASEF (Cont'd) 3.5.F Reactor Core Isolation Coolina System (RCICS)

The RCICS functions to provide core cooling and makeup water to the

)

reactor vessel-during shutdown and isolation from the main heat sink and for certain pipe break accidents. The RCICS provides its design flow between 150 pais and 1120 pais reactor pressure.

Below 150 pois, RCICS is not required to be operable since this pressure is substantially below that for any events in which RCICS is required to provide core cooling. RCICS will continue to operate below 150 pais at reduced flow until it automatically isolates at greater than or equal to 50 psig

-reactor ateam pressure.

150 psis is also below the shutoff head of the l'

CSS and RHRS, thus, considerable overlap exists with the cooling systems ll that provide core cooling at low reactor pressure.

l The ADS, CSS, and RHRS (LPCI) must be OPERABLE when starting up from a l

Cold Condition. Steam pressure is sufficient at 150 psig to run the RCIC turbine for operability testing, yet still below the shutoff head of the CSS and RERS pumps so they will inject water into the vessel if required.

Considering the low reactor pressure and the availability of the low pressure coolant systems during startup from a Cold Condition, twelve hours is allowed as a reasonable time to demonstrate RCIC operability once sufficient steam pressure becomes available.

The alternative to demonstrate RCIC operability prior to startup using auxiliary steam is provided for plant operating flexibility.

r With the RCICS inoperable, a seven-day period to return the system to j

service is justified based on the availability of the HPCIS to cool the core and upon consideration that the average risk associated with failure of the RCICS to cool the core when required is not increased.

The surveillance requirements, which are based on industry codes and standards, provide adequate assurance that the RCICS will be OPERABLE when required.

3.5.G Automatic Deeressurization Svatem (ADS)

This specification ensures the operability of the ADS under all conditions for which the depressurization of the nuclear system is an essential response to station abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low-pressure coolant injection (LPCI) and the core spray subsystems can operate to protect the fuel barrier. Note that this specification applies only to the automatic feature of the pressure relief system.

Specification 3.6.D specifies the requirements for the pressure relief function of the valves.

It is possible for any number of the valves assigned to the ADS to be incapable of performing their ADS functions i

because of instrumentation failures, yet be fully capable of performing their pressure relief function.

BFN 3.5/4.5-29 Amendment No. 176 Unit 2

.u b

-g" UNITED STATES

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NUCLEAR REGULATORY COMMISSION

• A WASHINGTON D. C. 20665 l

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TENNESSEE VALLEY AUTHORITY 1

DOCKET NO. 50-296 i

BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. DPR-68 I

1.

The Nuclear Regulatory Conunission (the Comunission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 9, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

i 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 Conunission; C.

.There is reasonable assurance (1) that the 4ctivities authorized by this amendment can be conducted without end6ngering 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 coninon defense and security or to the health and safety of the public; and E.

The issuana 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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,y 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as t

revised through Amendment No.144, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION W [--

Suza e Black, Assista 1 rector for Projects TVA Projects Division Office of Nuclear Reactor Regulation-

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 24, 1989

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,a.

ATTACHMENT TO LICENSE AMENDMENT NO. 144 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

i REMOVE INSERT 3.5/4.5-12 3.5/4.5-12*

3.5/4.5-13 3.5/4.5-13 3.5/4.5 14 3.5/4.5-14 3.5/4.5-15 3.5/4.5-15 3.5/4.5-31 3.5/4.5-31 3.5/4.5-32 3.5/4.S-32 i

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I 4

0

[3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE P{QUIREMENTS 3.5.C nNa service Water and Emeraency 4.5.C RNW Service Water and Emeraency Eauinment Coolina Water Systems Eauinment Coolina Water Systems (EECWS) (Continued)

(EECWS) (Continued) t 4.

One of the 81 or B2 RHRSW

4. No additional surveillance pumps assigned to the RHR is required.

heat exchanger supplying the standby coolant supply connection may be inoperable for a period l

not to axceed 30 days provided the OPEEABLE pump is aligned to supply the RHR heet exchanger header and the associated diesel generator and essential control valves are OPERABLE.

5.

The standby coolant supply capability may be inoperable l

for a period not to exceed l

10 days.

6.

If Specifications 3.5.C.2 through 3.5.C.5 are not

(

met, an orderly shutdown shall be initiated and the Junit placed in the COLD l

SHUTDOWN CONDITION within l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7.

There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.

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BFN 3.5/4.5-12 Amendment No. 124, 130, 140 Unit 3

i 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.$.D Eauinment Area Coolers 4.$.D Eaulement Area Coolers 1.

The equipment area cooler

1. Each equipment area cooler associated with each RHR is operated in conjunction pump and the equipment with the equipment served area cooler associated by that particular cooler; with each set of core therefore, the equipment spray pumps (A and C area coolers are tested at or B and D) must be the same frequency as the OPERABLE at all times pumps which they serve.

When the pump or pumps served by that specific L

cooler is considered to L

be OPERABLE.

2.

When an equipment area cooler is not OPERABLE, the pump (s) served by that cooler must be considered inoperable for Technical Specification purposes.

E.

Hiah Pressure Coolant Iniection E. Himh Pressure Coolant System (HPCIS)

Iniection System (HPCIS) 1.

The HPCI system shall be 1.

HPCI Subsystem testing OPERABLE whenever there is shall be performed as irradiated fuel in the follows:

reactor vessel and the reactor vessel pressure a.

Simulated Once/18 is greater than 150 pais, Automatic months L

except as specified in Actuation Specification 3.5.E.2.

Test OPERABILITY shall be determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b.

Pump Per L

after reactor steam pressure OPERA-Specification reaches 150 pais from a COLD BILITY 1.0.MM CONDITION, or alternatively PRIOR TO STARTUP by using an c.

Motor Oper-Per auxiliary steam supply, ated Valve Specification OPERABILITY 1.0.MH d.

Flow Rate at Once/3 normal months reactor vessel operating pressure BFN 3.5/4.5-13 Amendment No. 130, 144 Unit 3

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,'*5.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS

' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.E Himh Pressure Coolant Iniection 4.5.E Hiah Pre 3sure Coolant Iniection i

$vatan (NPCIS)

System (HPCIS) 4.5.E.1 (Cont'd) e.

Tiow Rate at once/18 l

150 psig months The KPCI pump shall deliver at least 5000 spa during each flow rate test.

f.

Verify that Once/ Month each valve (manual, power-operated, or automatic) in the t

injection flow-path that is not locked, sealed, or otherwise secured in position, is in its correct

• position.

2.

If the NPCI system is

2. No additional surveillances inoperable, the reactor may are required.

remain in operation for a period not to exceed 7 days, provided the ADS, CSS, RHRS (LPCI), and RCICS are OPERABLE.

l 3.

If Specifications 3.5.E.1 Except that an automatic or 3.5.E.2 are not met, valve capable of automatic an orderly shutdown shall return to its ECCS position be initiated and the when an ECCS signal is' reactor vessel pressure present may be in a l

shall be reduced to 150 position for another mode pois or less within 24 of operation.

hours.

F.

Reactor Core Isolation Coolina F.

Reactor Core Isolation Coolina L

System (RCICS)

System (RCICS) 1.

The RCICS shall be OPERABLE

1. RCIC Subsystem testing shall whenaver there is irradiated be performed as follows:

fuel in the reactor vessel and the reactor vessel

a. Simulated Auto-Once/18 pressure is above 150 psig, matic Actuation months except as specified in Test 3.5.F.2.

OPERABILITY shall BPN 3.5/4.5-14 Amendment No. 130, 140, 144 Unit 3

e a

3,5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 4

-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.F.

Reactor core Isolation Coolina 4.5.F Reactor Core Isolation Coolina System (RCICS)

EV311m (RCICS) 3.5.F.1 (Cont'd) 4.5.F.1 (Cont'd) i be determined within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

b. Pump Per after reactor steam pressure OPERABILITY Specifi-reaches 150 psig from a COLD cation-CONDITION or alternatively 1.0.MM PRIOR TO STARTUP by using an auxiliary steam supply.

c. Motor-Operated Per Valve Specifi-OPERABILITY cation 1.0.MM d.

Flow Rate at Once/3 normal reactor months vessel operating pressure e.

Flow Rate at Once/18 150 psig months The RCIC pump shall deliver at least 600 gpm during each flow test.

2.

If the RCICS is inoperable, f.

Verify that Once/ Month the reactor may remain in each valve operation for a period not (manual,. power-to exceed 7 days if the operated, or HPCIS is OPERABLE during automatic) in the such time.

injection flowpath that is not locked, 3.

If Specifications 3.5.F.1 sealed, or other-or 3.5.F.2 are not met, an vise secured in orderly shutdown shall be position, is in its-initiated and the reactor correct

• position, shall be depressurized to less than 150 psig within-

2. No additional surveillances 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, are required.

• Except that an automatic valve capable of automatic return to its normal position when a signal is Present may be in a position for another mode of operation.

BFN 3.5/4.5-15 Amendment No. 140, 144 Unit 3

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. 3.5 RASES (Cont'd) j r

'3.5.E.

Himh Pressure Coolant Iniection System (HPCIS) l I

The KPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss of coolant which does not result in rapid depressurization of the reactor, vessel. fThe HPCI system permits the l

reactor to be shut down while maintaining sufficient reactor vessel t

water: level inventory until the vessel is depressurized. The HPCIS continues to operate until reactor vessel pressure is below the precsure at which LPCI operation or Core Spray system operation maintains core cooling. The capacity of the system is selected to provide the required core cooling. The HPCI pump is designed to pump 5000 spa at reactor pressures between 1120 and 150 psig. The HPCIS is not required to be operable below 150 psig since this is well within the range of the low pressure cooling systems and below the pressure of any events for which HPCI is required to provide core cooling.

7 The HPCIS is not designed to operate at full capacity until reactor pressure exceeds 150 psig and the steam supply to the HPCI turbine is automatically isolated before reactor pressure decreases below 100 pais. The ADS, CSS, and RHRS (LPOI) must be OPERABLE when starting up from a Cold Condition.

Steam pressure is sufficient at 150 pais to run the HPCI turbine for operability testing, yet still below the shutoff head of the CSS and RHRS pumps so they will inject water into the vessel if. required. The ADS provides additional backup to reduce pressure to the range where the CSS and RHRS will inject into the vessel if necessary. Considering the low reactor pressure, the redundancy and availability of CSS, RHRS, and ADS during startup from a Cold Condition, twelve hours is allowed as a reasonable time to demonstrate HPCI operability once sufficient steam pressure becomes L

available. The alternative to demonstrate HPCI operability prior to i

startup using auxiliary steam is provided for plant operating flexibility.

With the HPCIS inoperable, a seven-day period to return the system to service is justified based on the availability of the ADS, CSS, RHRS (LPCI) and the RCICS. The availability of these redundant and diversified systema provides adequate assurance of core cooling while HPCIS is out of service.

The surveillance requirements, which are based on industry codes and standards, provide adequate assurance that the HPCIS will be OPERABLE when required.

BFN 3.5/4.5-31 Amendment No. 140, 144 Unit 3

I y

e 3.5 BASIE (C:nt'd) 3.5.F Reactor Core Isolation Coolina System (RCICS)

The RCICS functions to provide core cooling and makeup water to the i

reactor vessel during shutdown and isolation from the main heat sink and for certain pipe break accidents. The RCICS provides its design flow between 150 pais and 1120 pais reactor pressure.

Below 150 pais, RCICS i

is not required to be operable since this pressura is substantially i

l below that for any events in which RCICS is required to provide core

-cooling.

RCICS will continue to operate below 150 pois at reduced flow until it automatically isolates at greater than or equal to 50 pais reactor steam pressure.

150 pois is also below the shutoff head of the CSS and RRRS, thus, considerable overlap exists with the cooling systems that provide core cooling at low reactor pressure.

1 l

J The ADS, CSS, and RERS (LPCI) must be OPERABLE when starting up from a Cold Condition.

Steam pressure is sufficient at 1$0 pais to run the RCIC turbine for operability testing, yet still below the shutoff head of the CSS and RHRS pumps so they will inject water into the vessel if required.

Considering the low reactor pressure and the availability of the low pressure coolant systems during startup from a Cold Conditicn, twelve hours is allowed as a reasonable time to demonstrate RCIC operability once sufficient steam pressure becomes available. The alternative to demonstrate RCIC operability prior to startup using auxiliary steam is provided for plant operating flexibility.

With the RCICS inoperable, a seven-day period to return the system to service is justified based on the availability of the HPCIS to cool the core and upon consideration that the average risk associated with failure of the RCICS to cool the core when required is not increased.

I The surveillance requirements, which are based on induetry codes and 1-standards, provide adequate assurance that the RCICS will be OPERABLE when required.

3.5 G ' Automatic Depressurization System (ADS)

This specification ensures the operability of the ADS under all conditions for which the depressurization of the nuclear system is an essential response to station abnormalities.

The nuclear system pressure reitef system provides automatic nuclear system depressurizatcion for small breaks in the nuclear system so that l

the low-pressure coolant injection (LPCI) and the core spray subsystems

[

can operate to protect the fuel barrier. Note that this specification applies only to the automatic feature of the pressure relief system.

Specification 3.6.D specifies the requirements for the pressure reltaf function of the valves.

It is possible for any number of the valves assigned to the ADS to be incapable of performing their ADS functions because of instrumentation failures, yet be fully capable of performing their pressure relief function.

BrN 3.5/4.5-32 Amendment No. 144 Unit 3

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