Text

Proposed Tech Specs Incorporating Requirements of ASME Code Section XI Re Inservice Pump & Valve Testing
	ML18026A963
Person / Time
Site:	Browns Ferry
Issue date:	04/26/1984
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML16341C140	List: ML16341C139; ML18026A963;
References
	NUDOCS 8405080287
	Download: ML18026A963 (46)
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ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS TVA BFNP TS 181 SUPPLEMENT 1

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UNIT 1

PROPOSED TECHNICAL SPECIFICATIONS

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM A licabilit Applies to the operating status of the Standby Liquid Control System.

~0b ective To assure the availability of a system with the capability to shut down the reactor and maintain the shutdown condition without the use of control rods ~

Applies to the surveillance require-ments of the Standby Liquid Control System.

Ob ective To verify the operability of the Standby Liquid Control System.

S ecification S ecification A. Normal S stem Availabilit A.

Normal S stem Availabilit 1.

The standby liquid con-trol system shall be operable at all times when there is fuel in the reactor vessel and the reactor is not in a shut-down condition with all operable control rods fully inserted except as specified in 3.4.B. 1.

The operability of the Standby Liquid Control System shall be verified by the per-formance of the following tests:

1. Verify that, when tested pursuant to Specification 4. 12.A, each pump develops a flow of at least 39 gpm against a system head of 1275 psig.

2. At least once per month each pump loop shall be functionally tested.

3. At least once during each operating cycle:

a.

Check that the setting of the system r elief valves is 1425 +

75 psig.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM A.

Normal S stem Availabilit b.

Manually init'late the system, except explosive valves.

Pump boron solution through the recirculation, path and back to the Standby Liquid Control Solution Tank.

Minimum pump flow rate of 39 gpm 135a

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 CORE AND CONTAINMENT COOLING SYSTEMS Applies to the operational status of the core and containment cooling systems.

A licabilitv Applies to the surveillance requirements of the core and containment cooling systems when the corresponding limiting condi-tion for operation is in effect.

~Ob ective Ob ective To assure the oper ability of the core and containment cooling systems under all conditions for which this cooling capability is an essential response to the plant abnormalities.

To verify the operability of the core and containment cooling systems under all conditions for which this cooling capability is an essential response to plant abnormalities.

A. Core S ra S stem (CSS)

A. Core S ra S stem

{CSS) 1.

The CSS shall be operable:

1. Core Spray System Testing.

( 1) prior to reactor startup from a cold condition, or (2) when there is irra-diated fuel in the vessel and when the reactor vessel pressure is greater than atmos-pheric pressure, except as specified in. Specifi-cation 3.5.A.2.

Item

a. Simulated Automatic Actuation test b.

Pump Opera-bility c.

(Deleted)

~pre cene Once/

Oper ating Cycle Once/

month

d. Verify that, when tested pursuant to Specification 4. 12.A each loop delivers at least 6,250 gpm against a system head corres ponding to 'a 143

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.B Residual Heat Removal S stem (RHRS)

(LPCI and Containment Cooling) 1.

The RHRS shall be operable:

( 1) prior to a reactor startup from a Cold Condition; or

1. a. Simulated Automatic.

Actuation.'est Once/

Operating Cycle 4.5.B. Residual Heat Removal S stem (RHRS)

(LPCI and'ontainment Cooling)

(2) when there is irradiated fuel in the reactor vessel and when the reactor vessel pressure is greater than atmospheric, except as specified in Specification 3.5.B.2 through 3.5.B.7.

b.

Pump Opera-bility c.

(Deleted)

Once/

month

2. With the reactor vessel pressure less than 105 psig, the RHRS may be removed from service (except that two RHR pumps-containment cooling mode and associated heat exchangers must remain operable) for a period not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while being drained of suppression chamber quality.water and filled with primary coolant quality water provided that during cooldown two loops with one pump per loop or one loop with two pumps,'. and associated diesel generators, in the core spray system are operable.

3. If one RHR pump (LPCI mode) is inoperable, the reactor may remain in operation for a period not to exceed 7 days provided the remaining RHR pumps (LPCI mode) and both access paths of the RHRS (LPCI mode) and 'the CSS and the diesel generators remain oper able.

d.

When tested in accordance with Specification 4. 12.A, each LPCI pump shall deliver at least 9,000 gpm against an indicated system pressure of 125 psig.

Two LPCI pumps in the same loop shall deliver 12,000 gpm against an indicated system pressure of 250 psig.

e. Valves shall be tested in accordance with Specifi-cation 4.12.A.

2.

An air test on the drywell and torus headers and nozzles shall be conducted once/5 years.

A water test may be performed on the torus header in lieu of the air test.

3.

No additional surveillance required.

145

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.D E ui ment Area Coolers 0.5.D EcCui ment Area Coolers 1.

The equipment area cooler associated with each RHR pump and the equipment area cooler associated with each set of core spray pumps (A

and C or B and D) must be operable at all times when the pump or pumps served by that specific cooler is considered to be operable.

1. Each equipment area coolel is operated in conjunction with the equipment served by that particular cooler; therefore, the equipment area coolers are tested at the same frequency as the pumps which they serve.

2.

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

E. Hi h Pressure Coolant In ection S stem (HPCIS)

1. The HPCI system shall be operable:

1. HPCI Subsystem testing shall be performed as follows:

( 1) prior to startup from a Cold Shutdown;, or (2) whenever there is irra-diated fuel in the reac-tor vessel and the reactor vessel pressure is greater than 122 psig, except as specified in Specification 3.5.E.2.

a. Simulated Automatic Actuation Test b.

Pump Opera-bility c.

(Deleted)

Once/

operating cycle Once/

month d.

When tested zn accordance with Specification 0. 12.A the HPCI pump shall deliver at least 5000 gpm at normal reactor vessel operating pressure.

e. Valves shall be tested in accordance with Specifi-cation

>f. 12.A.

154

LIMITING CONDITIONS FOR OPERATION E. Hi h Pressure Coolant In ection S stem HPCIS)

SURVEILLANCE REQUIREMENT E. Hi h Pressure Coolant In ection S stem (HPCIS)

f. When flow rate tested at equal to or greater than 150 psig steam pressure to the turbine, the HPCI pump shall deliver at 1'east 5000 gpm.

This test shall be performed once per operating cycle.

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REC}UIREMENT 3.5.F Reactor Core Isolation Coolin M

2. If the RCICS is inoperable, the reactor may remain in operation for a period not to exceed 7 days if the HPCIS is operable during such time.

0.5.F Reactor Core Isolation Coolin S stem (RCICS)

f. When flow rate tested at equal to or greater than 150 psig steam pressure to the turbine, the RCIC pump shall deliver at least 600 gpm.

This test shall be performed once per operating cycle.

2.

No additional surveillance required.

3. If specifications 3.5.F.1 or 3.5.F.2 are not met, an orderly shutdown shall be initiated and the reactor shall be depressurized to less than 122 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l56a

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.G Automatic De ressurization

1. Four of the six valves of the Automatic Depressuriza-tion System shall be operable:

( 1) prior to a startup from a Cold Condition, or, (2) whenever there is irra-diated fuel in the reactor vessel and the reactor vessel pressure is greater than 105 psig, except as specified in 3.5.G.2 and 3.5.G.3 below.

.5.G Automatic De ressurization 44

1. During each operating cycle the following tests shall be performed on the ADS:

cl a.

A simulated automatic actuation test shall be performed prior to startup

'after each refueling out-age.

Manual surveillance of the relief valves is covered, in 4.6.D.2.

2. If three of the six ADS valves are known to be incapable of automatic operation, the reactor may remain in oper ation for a period not to exceed 7 days, pro-vided the HPCI system is operable.

(Note that the pressure relief function of these valves is assured by section 3.6.D of these specifications and that this specification only applies to the ADS functus,on.) If more than three of the six ADS valves are known to be incapable of automatic operation, an immediate orderly shutdown shall be initi-ated, with the reactor in a hot shutdown condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in a cold shutdown condition in the following 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2.

No additional surveillance required.

157

4.5 Core and Containment Coolin S stems Surveillance Fre uencies The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability anaylsis, Judgement, and practicality.

The core cooling systems have not been designed to be fully testable during operation.

For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable.

Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory.

To increase the availability of the core and containment cooling system, the components which make up the system; i.e.,

instrumentation,

pumps, valves, etc., are tested frequently.

The pumps are also tested each month to assure their operability.

A simulated automatic actuation test once each cycle combined with monthly tests of the pumps is deemed to be adequate testing of these systems.

When components and subsystems are out-of-service, overall core and containment cooling reliability is maintained by redundant operable equipment.

Out-of-service time is selected as a small fraction of normal surveillance frequency to add further conservatism.

Maximum Avera e Planar LHGR LHGR and MCPR The MAPLHGR, LHGR, and MCPR shall be checked daily to determine if fuel

burnup, or control rod movement has caused changes in power distribution.

Since changes due to burnup are slow, and only a few control rods are moved daily, a daily check of power distribution is adequate.

170

UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.4 STANDBY LIQUID CONTROL SYSTEM A licabilit 4.4 STANDBY LIQUID CONTROL SYSTEM A licabilit Applies to the operating status of the Standby Liquid Control System.

Ob ective To assure the availability of a system with the capability to shut down the reactor and maintain the shutdown condition without the use of control rods ~

Applies to the surveillance require-ments of the Standby Liquid Control System.

~Ob ect1ve To verify the operability of the Standby Liquid Control System.

A. Normal S stem Availabilit A.

Normal S stem Availabilit 1.

The standby liquid con-

'rol system shall be operable at all times when there is fuel in the reactor vessel and the reactor is not in a shut-down condition with all operable control rods fully inserted except as specified in 3.4.B. l.

The operability of the Standby Liquid Control System shall be verified by the per-formance of the following tests:

1. Verify that, when tested pursuant to Specification 4. 12.A, each pump develops a flow of at least 39 gpm against a system head of 1275 psig.

2. At least once per month each pump loop shall be functionally tested.

3. At least once during each operating cycle:

a.

Check that the setting 'of the system relief valves is 1425 +

75 psig.

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.B Residual Heat Removal S stem (RHRS)

(LPCI and Containment Cooling) 4.5.B. Residual Heat Removal S stern (RHRS)

(LPCI and Containment Cooling)

1. The RHRS shall be operable:

(1) prior to a reactor startup from a Cold Condition; or

1. a. Simulated Automatic Actuation'-

Test Once/

.Operating Cycle (2) when there is irradiated fuel in the reactor vessel and when the reactor vessel pressure is greater than atmospher ic, except as specified in Specification 3.5.B.2 through 3.5.B.7.

b.

Pump Opera-bility c.

(Deleted)

Once/

month

2. With the reactor vessel pressure less than 105 psig, the'RHRS may be removed from service (except that two RHR pumps-containment cooling mode and associated heat exchangers must remain operable) for a period not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while being drained of suppression chamber quality water and filled with primary coolant quality water provided that during cooldown two loops with one pump per loop or one loop with two pumps, and associated diesel generators, in the core spray system are operable.

3. If one RHR pump (LPCI mode) is inoperable, the reactor may remain in operation for a period not to exceed 7 days provided the remaining RHR pumps (LPCI mode) and. both access paths of the RHRS (LPCI mode) and the CSS and the diesel generators remain operable.

d.

When tested in accordance with Specification 4. 12.A, each LPCI pump shall deliver at least 9,000 gpm against an indicated system pressure of 125 psig.

Two LPCI pumps in the same loop shall deliver 12,000 gpm against an indicated system pressure of 250 psig.

e. Valves shall be tested in accordance with Specifi-cation 4.12.A.

2.

An air test on the dtywell.and torus headers and nozzles shall be conducted once/5 years.

A water test may be performed on the torus header in lieu of the air test.

3.

No additional surveillance required.

145

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREEKNT 3.5.D E uioment Area Coolers 4.5.D Ecuinment Area Coolers

~ 1.

The equipment area cooler associated with each RHR pump and the equipment area cooler associated with each set of core spray pumps (A

and C or B and D) must be operable at all times when the pump or pumps served by that specific cooler is considered to be operable.

l. Each equipment area cooler is operated in conjunction with the equipment served by that particular cooler; therefore, the equipment area coolers are tested at the same frequency as the pumps which they serve.

2.

Mhen an equipment area cooler is not operable, the pump(s) served by that cooler must be considered inoperable for Technical Specification pur-poses.

E. Hi h Pressure Coolant In ection S stem (HPCIS)

E. High Pressure Coolant, In ection S stem (HPCIS)

1. The HPCI system shall be operable:

( 1) prior to startup from a Cold Shutdown; or (2) whenever there is irra-diated fuel in the reac-tor vessel and the reactor vessel pressure is greater than 122 psig, except as specified in Specification 3.5.E.2.

1.

HPCI Subsystem testing shall be performed as follows:

a. Simulated Automatic Actuation Test Once/

operating cycle b.

Pump Opera-bility Once/

month c.

(Deleted) 7 d.

When tested in accordance with Specification 0.12.A the HPCI pump.",hall deliver at lca"t 5000 gpm at normal reactor vessel operating pressure.

e. Valves shal'e tested in accordance with Specifi-cation 4. 12.A.

154

I

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT E. Hi h Pressure Coolant In ection S stem (HPCIS)

E. Hi h Pressure Coolant In ection S stem (HPCIS)

f. When flow rate tested at equal to or greater than 150 psig steam pressure to the turbine, the HPCI pump shall deliver at least 5000 gpm.

This test shall be performed once per operating cycle..

155

a n

LI'i4IITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.E Hi h Pressure Coolant In ection S stem (HPCIS) 4.5.E Hi h Pressure Coo'ant In,1ection S stem (HPCIS)

2. If the HPCI system is inopera-ble, the reactor may remain in operation for a period not to exceed 7 days, pro-vided the

ADS, CSS, RHRS (LPCX), and RCICS are operable.

2.

No additional surveillance required.

~ 3. If Specification 3.5.E.1 or 3.5.E.2 are not met, an orderly shutdown shall be initiated and the reactor vessel pressure shall be reduced to 122 psig or less within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s.

F. Reactor Core Isolation Coolin S stem (RCICS)

1. The RCICS shall be operable:

F. Reactor Core Isolation Coolinz S stem (RCICS) 1.

RCIC Subsystem testing shall be performed as follows:

( 1) prior to startUp from a Cold Condition; or (2) whenever there is irra--

diated fuel in the reac-tor vessel and the reac-tor vessel pressure is above 122 psig, except as specified in 3.5.F.2.

a. Simulated Automatic Actuation Test b.

Pump Opera-bility c.

(Deleted)

Once/

operating

cycle, Once/

month d.

Mhen tested in accordance with Specification 4.12.A the RCIC pump shall deliver at least 600 gpm at normal reactor operating pressur e.

e. Valves shall be tested in accordance with Speci.i-cation 4.12.A.

156

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.F Reactor Core Isolation Coolin 4.5.F Reactor Core Isolation Coolin

2. If the RCICS is inoperable, the reactor may remain in operation for a period not to exceed 7 days if the HPCIS is operable during such time.

f. When flow rate tested at, equal to or greater than 150 psig.steam pressure to the turbine, the RCIC pump shalg deliver at least 600 gpm.

This test shall be performed once per operating cycle.

2.

No additional surveillance required.

3. If specifications 3.5.F.

1 or 3.5.F.2 are not met, an orderly shutdown shall be initiated and the reactor shall be depressur ized to less than 122 psig within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

lS6a

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.G Automatic De ressurization

.5.G Automatic De ressurization

1. Four of the six valves of the Automatic Depressuriza-tion System shall be operable:

(1) prior to a startup from a Cold Condition, or, (2) whenever there is irra-diated fuel in the reactor vessel and the reactor vessel pressure is greater than 105 psig, except as specified in 3.5.G.2 and 3.5.G.3 below.

1. During each operating cycle the following tests shall be performed on the ADS:

a.

A simulated automatic actuation test shall be performed prior to startup after each refueling out-age.

Manual surveillance of the relief valves is covered, in 0.6.D.2.

2. If three of the six ADS valves are known to be incapable of automatic operation, the reactor may remain in operation for a period not to exceed 7 days, pro-vided the HPCI system is operable.

(Note that the pressure relief function of these valves is assured by section 3.6.D of these specifications and that this specification only applies to the ADS function.) If more than three of the six ADS valves are known to be incapable of automatic operation, an immediate orderly shutdown shall be,initi-ated, with the reactor in a hot shutdown condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in a cold shutdown condition in the following 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2.

No additional surveillance required.

157 x

4.5 Core and Containment Coolin S stems Surveillance Fre uencies The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability anaylsig; judgement>

and practicality.

The core cooling systems have not been designed to be fully testable during operation.

For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable.

Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory.

To increase the availability of the core and containment cooling system, the components which make up the system; i.e.,

instrumentation, pumps, valves, etc., are tested frequently.

The pumps are also tested each month to assure their operability.

A simulated automatic actuation test once each cycle combined with monthly tests of the pumps is deemed to be adequate testing of these systems.

When components and subsystems are out-of-service, overall core and containment cooling reliability is maintained by redundant operable equipment.

Out-of-service time is selected as a small fraction of normal surveillance frequency to add further conservatism.

Maximum Avera e Planar LHGR LHGR and MCPR The MAPLHGR, LHGR, and MCPR shall be checked daily to determine if fuel burnup, or control rod movement has caused changes in power distribution.

Since changes due to burnup are slow, and only a few control rods are moved daily, a daily check of power distribution is adequate.

170

UNIT 3 PROPOSED TECHNICAL SPECIFICATIONS

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Applies to the operating status of the Standby Liquid Control System.

~Ob ect1ve To assure the availability of a system with the capability to shut down the reactor and maintain the shutdown condition without the use of control rods.

S ecification Applies to the surveillance require-ments of the Standby Liquid Control System.

~Ob ect1ve To verify the operability of the Standby Liquid Control System.

S ecification A. Noimal S stem Availabilit A.

Normal S stem Availabilit 1.

The standby liquid con-trol system shall be operable at all times when there is fuel in the reactor vessel and the reactor is not in a shut-down condition with all operable control rods fully inserted except as specified in 3.4.B.1.

The operability of the Standby Liquid Control System shall be verified by the per-formance of the following tests:

1, Verify that, when tested pursuant to Specification 4. 12.A, each pump develops a flow of at least 39.gpm against a system head of 1275 psig.

2. At least once per month each pump loop shall be functionally tested.

3. At least once during each operating cycle:

a.

Check that the setting of the system relief valves is 1425 +

75 psig.

b.

Manually initiate the system, except explosive valves.

Pump boron solution through 'the 137

4

LIiMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENT 3.5 CORE AND CONTAINMENT COOLING SYSTEMS 4.5 COBE AND CONTAINMENT COOLING SYSTEMS A licabilitv Applies to the operational status of the core and containment cooling systems.

Applies to the surveillance requirements of the core and containment cooling systems when the corresponding limiting condi-tion for operation is in effect.

Ob ective

~Ob eotive To assure the operability of the core and containment cooling systems under all conditions for which this cooling capability is an essential response to the plant abnormalities.

To verify the operability of the core and containment cooling systems under all conditions for which this cooling capability is an essential response to plant abnor malities.

A. Core Spray System (CSS)

A. Core Sora S stem (CSS) 1.

The CSS shall be operable:

1. Core Spray System Testing.

( 1) prior to reactor startup from a cold condition, or (2) when there is irra-diated fuel in the vessel and when the reactor vessel pressure is greater than atmos-pheric pressure, except as specified in Specifi-cation 3.5.A.2.

Item

a. Simulated Automatic Actuation

-test b.

Pump Opera-bility c.

(Deleted)

Freaaeaar Once/

Oper ating Cycle Once/

month

d. Verify that, when tested pursuant to Specification 4. 12.A each loop delivers at least 6,250 gpm against a system head corres-ponding to a 146

~

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3-5 CORE AND CONTAINMEN.R COOLING S YSTEMS

4. 5 CORE AND CONTAINMENT COOLING SYS.EMS B.

R~ sidual Heal Removal

,"yste~t."RRR (LPCZ and Containment Cooling)

The RHRSshall be operable:

(1) prior to a re~ctor startup from a Cold Condi tion; or B.

Residual Heat: Removal Containment Cooling) a.

Simulated Automatic Actuation Test b.

Pump Opera-bility Once/

Operatinq Cycle Once/

montn 2.

(2) when there is irradiated fuel

, in the reactor vessel and when the reactor vesse'ressure is greater than atmospheric, except as specified in specifications 3.5.B.2, throuqh 3.5.B.7 With the reactor vessel pressure less than 105 psiq, the RHR may be removed f rom service (except that two RHR pumps-containment cooling mode and associated heat exchangers must remain operable) for a period not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while beinq drained of c.

(Deleted)

'I If d.

When tested in accordance with Specification

11. 12.A, each LPCI pump shall deliver at least 9,000 gpm against an indicated system pressure, of 125 psig.

Two LPCI pumps in the same loop shall deliver 15.000 gpm against an indicated system pressure of 200 psig.

e. Valves shall be tested in accordance with Specifi-cation

11. 12.A.

2.

An air test on the drywell and torus headers and nozzles shall be conducted once/5 years.

A water test may be performed on the torus header in lieu of the air test.

149

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LIHITING CONDITIONS FOR OPERATION SURVEILLANCE RFQUI REMENTS COOf ING SYSTEMS rl ~ 5 CORE AND CONTAINHERP COOLING SYS T MS E.

Hi h Pressure Coolant In ection S stem HPCIS E.

Hi h Pressure Coolant

'n ection S stem HPCIS (2) whenever there is irradiated fuel in the reactor vessel and the reactor vessel pressure is greater than 122 psig, except as specified in specification 3.5.E.2.

2.

If the HPCI system in inoperable, the reactor may remain in operation for a period not to exceed 7 days, provided the ADSs CSSs RHRS (LPCI), and RCICS are operable.

3 ~

If specifications

3. 5. E-1 or 3.5.E. 2 are not met, an orderly shutdown shall be initiated and the reactor" vessle pressure shall be reduced to 122 psig or less within 2W hours.

1.

The HPCI system shall be operable:

(1) prior to startup from a,Cold Condition; or 1.

HPCI Subsystem testing shall be performed as follows:

a.

Simulated Automatic "Actuation Test Once/

operating cycle b.. Pump Opera-bility Once/

month c.

(Deleted) d.

When tested in accordance with Specification 4. 12.A the HPCI pump shall deliver at least 5000 gpm at normal reactor vessel operating pressure.

e. Valves shall be tested in accordance with Specifi-cation ll.12.A.

f. When flow rate tested at equal to or greater than 150 psig steam pressur e

to the turbine, the HPCI pump shall deliver at least 5000 gpm.

This test shall be performed once per operating cycle.

l 2.

No additional surveillance required.'59

~j'.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT i, rr CORE AND CONTAINMENT COOLING SYSTEMS 4

4 ~ 5 CORE MD CONTAINMENT COOLING SYSTEMS F.

Reactor Core Isolation Coolin S stem RCICS

'l.

The RCICS shall be oper abl e:

F. Reactor Core Isolation Coolinz S stem (RCICS) 1.

RCIC Subsystem testing shall be performed as follows:

2 ~

3 ~

(1)

Prior to startup from a Cold Condition; or (2) whenever there is irradiated fuel in the reactor vessel and the reactor vessel pressure is above 122

psig, except as specified in 3.5.F.2.

If the RCICS is inoperable, the reactor may remain in operation for a period not to exceed 7 days if the HPCIS is operable during such time.

If specifications 3.5.F.

1 or 3.5.F.2 are not met, an orderly shutdown shall be initiated and the reactor shall be depressurized to less than 105 psig within'Q hours.

a. Simulated Automatic Actuation Test Once/

operating cycle b.

Pump Opera-bility Once/

month c.

(Deleted)

f. When flow rate tested at equal to or greater than 150 psig steam pressure to the turbine, the RCIC pump shall deliver at least 600 gpm.

This test shall be performed once per operating cycle.

d.

When tested in accordance with Specification 4.12.A the RCIC pump shall deliver at least 600 gpm at normal reactor operating pressure.

e. Valves shall be tested in accordance with Specifi-cation 4. 12.A.

2.

No additional surveillance required.

160

4.5 Core and Containment Coolin S stems Surveillance Fre uencies The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability anaylsis, judgement-;

and practicality.

The core cooling systems have not been designed to be fully testable during operation.

For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable.

Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory.

To increase the availability of the core and containment cooling system,. the components which make up the system; i.e.,

instrumentation, pumps, valves, etc.,

are tested frequently.

The pumps i are also tested each month to assure their operability.

A simulated automatic actuation test once each cycle combined with monthly tests of the pumps is deemed to be adequate testing of these systems.

When components and subsystems are out-of-service, overall core and containment cooling reliability is maintained by redundant, operable equipment.

Out-of-service time is selected as a small fraction of normal surveillance frequency to add further conservatism.

Maximum Avera e Planar LHGR LHGR and MCPR The MAPLHGR, LHGR, and MCPR shall be checked daily to determine if fuel burnup, or control rod movement has caused changes in power distribution.

Since changes due to burnup are slow, and only a few control rods are moved daily, a daily check of power distribution is adequate.

179

ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION TVA BFNP TS 181 SUPPLEMENT 1

4

Reference:

TVA letter from L. M. Mills to H.

R. Denton dated November 12, 1982 (TVA BFNP TS 181)

The referenced letter submitted proposed technical specification revisions for implementing the ASME Section XI inservice pump and valve testing program at Browns Ferry.

Part of that submittal proposed deletion of the requirement to conduct monthly operability testing of pumps and valves.

We wer e informed by the NRC staff (Browns Ferry Project Manager) that the proposed change would have to be prenoticed as a possible significant hazards consideration.

We decided to avoid that situation by submitting additional revisions to reinstate the monthly testing requirement.

The specifications submitted do that.

i4(,

I

ML18026A963

Text

Reference:

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