ML20072L657

Proposed Tech Spec Changes Re Drywell Leakage

ML20072L657
Person / Time
Site:	Browns Ferry
Issue date:	03/25/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20072L655	List: ML20072L651 ML20072L657
References
REF-SSINS-6820 IEB-82-03, IEB-82-3, NUDOCS 8303310424
Download: ML20072L657 (11)

Text

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SURVEILLANCE ATSCIREMENYS L1HITING CONDITIONS FOR OPERATION e

4.6 PRIMARY SYSTEM BOUNDARY 3.6 PRpjARY SYSTEM BOUNDARY C. Coolant Leakage C. Coolant Leakane

a. Any time irradiated 1. Reactor coolant f '1.

system leakage shall fuel is in the be checked by the reactor vessel and sump and air.sampfing reactor coolant system and recorded temperature is above at least once per' 2120F, reactor day, coolant leakage into the primary

2. With the air sampling containment from system inoperable, unidentified cources grab samples shall be shall not exceed 5 obtained and analyzed gpm. In addition, at lecnt once every-the total reactor 24 hou<n.

coolant system leakage into the primary containment shall not exceed 25 g om .

b. Anytime the reactor is in f;-

RUN mode, reactor coolant leakage into the primary (

containment from unidentified sources shall not increase by more than 2 gpm averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in which the reactor is in the RUN mode except

! as defined in 3.6.C.1.c i

below.

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

! the RUN mode following startup, an increase in

! reactor coolant leakage into the primary containment of

>2 gpm is acceptable as long as the requirements of 3.6.C.I.a are met.

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFOUIREMENTS s- N 3.6.C Coolant Leakage 4.6.c Coolant Leaiege '

2. Both the sump and air sampling systems ahall be operable during D. Pelfef Valves, reactor power operation. From and af ter the date that one of 1. At least one safety valve and' these systems is made or found approximately Jne-half of to be inoperable for any reason, all relief valves shall be reactor power operation is bench-checked or replaced with permissible only during the a bench-checked valve each the succeeding seven days. operating cycle. All 13 valves (2 safety and 11 relief) will have been The air sampling system may checked or replaced upon the be removed from service for a completion of every second period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for cali- cycle.

bration, functional testing, and maintenance without providing 2. Once during each operating a temporary monitor. cycle, each relief valve shall be manually opened

3. If the condition in 1 or 2 until thermocouples and above cannot be met, an orderly acoustic monitors downstream shutdown shall be initiated of the valve indicate and the reactor shall be shut- steam is flowing from the down in the Cold Condition valve, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. The integrity of the relief D. Relief Valves safety valve bellows shall be continuously monitored.

1. When more than one relief valve or one or more safety 4. At least one relief volve valves are known to be shall be disassembled and failed, an orderly shutdown inspected each operating shall be initiated and the cycle.

reactor depressurized to less than 105 psig withia E. Jet Pumps 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Whenever there is recircula-1.

tion flow with the reactor in E. Jet Pumps the startup or run modes with both recirculation pumps

1. Whenever the reactor is in running, jet pump operability the startup or run modes, shall be checked daily by all jet pumps shall be verifying that the following operable. If it is deter- c nditions do not occur mined that a jet pump is in- simultaneously:

operable, or if two or more

a. The two recirculation loops jet pump flow instrument failures occur and cannot be have a flow imbalance of corrected within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 15% or mo,re when the pumps are operated at the same an orderly shutdown shall be initiated and the reactor speed, shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

181

. . __ __ . __ _ _ _ _ _ . _ _ . _ - _ _ . _ _ . _ m .- _ ..,._

. 3.6/4 BASES

-detected reasonably in a matter of few hours utilizing the available

%s- leakage detection schemes, and if the origin cannot be determined in a ,

reasonably short time the urnit should be shut down to allow further investigation and corrective action.

- The 2 gpm linit for coolant leakaa.c rate increnna over any 2/ hour period is a limit specified by the NRC (Reference 2.) This limit

-' . applies only during the RUN mode to avoid being penalized-for the- -

. expected coolant leakage increase during pressurization.

l The total leakage rate consists of all leakage, identified and unidentified, which flows to the drywell floor drai,n and equipment drain sumps.

The capacity of the drywell floor sump pump is 50 gpm and the capacity of the drywell equipeent sump pump is also 50 gps.

Removal of 25 gpa from either of these sumps can be accomplished with considerable margin.

REFERENCE g . .

1. Nuclear System Leakage Rate Limits (BFNP FSAR Subsection 4.10)

2. Safety Evaluation Report (SER) on IE Bulletin . 82-03 l i

3.6.D/4.6.D Relief Valves To meet the safety basis thirteen relief valves have been installed.on the unit with a total capacity of 83.9% of nuclear boiler rated steam flow. The analysis of the worst overpressure transient, (3-second closure of all-main steam line isolation valves) neglecting the direct scram (valve position scram) results in a maximum vessel pressure which, if a neutron flux scram is assumed i considering 12 valves operable, results in adequate margin i to the code allowable overpressure limit of 1375 psig.

To meet operational design, the analysis of the plant isolation transient (generator load reject with bypass valve failure to open) shows that 12 of the 13 relief valves limit peak system pressure to a value which is well below the allowed vessel overpressure of 1375 psig.

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4.6 PRIMARY SYSTEM BOUNDkRY 3.6 PRIMARY SYSTEM BOUNDART C. Coolant Leakarte ,

C. Coolant LeakaQe

1. A. Any time irradiated 1.

Reactor coolant l

f uel is in the system leakage shall be checked by the' reactor vess'51 and '

sump and air sampling reactor coolant temperature is above system and recorded 2120P, reactor at least once per coolant leakage into day.

the primary containment from '

2. With the air sampling unidentified sources system inoperable, shall not exceed 5 grab samples shall be gpm. In addition, obtained and analyzed

. at least once every

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

leakage into the primary containment shall not exceed 25

b. Anytime the reactor is in RUN mode, reactor coolant leakage into the primary  ;

i containment from unidentified sources shall not increase by more than 2 gpm averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in which the reactor is in the RUN mode except as defined in 3.6.C.I.c below.

c. During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the RUN mode following startup, an increase in reactor coolant leakage into the primary containment of

>2 gpm is acceptable as

- long as the requirements of 3.6.C.1.a are met.

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.C Coolant Leakage 4.6.C Coolant Leakage

2. Both the sump and air sampling systems shall be operable during D. Relief Valves reactor power operation. From 1. Approximately one-half of all and after the date that one of relief valves shall bc bench-these systems is made or found checked or replaced with a to be inoperable for any reason, bench-checked valve each reactor power operation is operating cycle. All 13 permissible only during the valves will have been checked succeeding seven days. or replaced upon the comple-The air sampling system may be removed from service for a 2. Once during each operating period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for cali- cycle, each relief valve bration, function testing, and shall be manually opened maintenance without providing until thermocouples and a temporary monitor, acoustic monitors downstream of the valve indicate steam

3. If the condition in 1 or 2 is flowing from the valve.

above cannot be met, an orderly shutdown shall be initiated 3. The integrity of the relief /

and the reactor shall be shut- safety valve bellows shall be down in the Cold Condition continuously monitored, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Relief Valves

4. At least one relief valve shall be disassembled and inspected

1. E en more than one relief valves each operating cycle.

are known to be failed, an orderly shutdown shall be initiat-ed and the reactor depressurized E. Jet Pumps to less than 105 psig within 1. W enever there is recirculation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. flow with the reactor in the startup or run modes with both E. Jet Pumps # # ' " E" E" "" '

1. Whenever the reactor is in the jet pump operability shall be startup or run modes, all jet checked daily by verifying that pumps shall be operable. If the following conditions do not it is determined that a jet pump occur simultaneously:

is inoperable, or if two or more jet pump flow instrument a. The two recirculation loops failures occur and cannot be have a flow imbalance of corrected within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an 15% or more when the pumps orderly shutdown shall be initi- are operated at the same ated and the reactor shall be speed.

shutdown in the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

181

.-wa s 3.6/4.6 BASES

~~

detected reasonably in a matter of few hours utilizing the available leakage detection schemes, and if the origin cannot be determined in a reasonably short time the unit should be shut down to allow further investigation and corrective action.

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'The 2 gpm 11 nit for coolant leakaa.c rate increano over any 2/ hour period is a limit specified by the NRC (Reference 2.) This limit. -

applies only dufl'ng the RUN mode to avoid being penalized for the expected coolant leakage increase during pressurization. -

. - . . . . - ---- - ~ -

The total leakage rate consists of all leakage, identified and unidentified, which flows to the drywell floor drai,n and equipment drain sumps.

The capacity of the drywell floor sump pump is 50 gpm and the capacity of the drywell equipment sump pump is also 50 gpm.

Removal of 25 gpm from either of these sumps can be accomplished with considerable margin.

REFERENCE

1. Nuclear System Leakage Rate Limits (BFNP FSAR Subsection 4.10)

2. Safety Evaluation Report (SER) on IE Bulletin 82-03

^

• 3.6.D/4.6.D Relief Valves To meet the safety basis, thirteen relief valves have been installed on the unit with a total capacity of 84.1% of nuclear boiler rated steam flow. The analysis of the worst overpressure transient (3-second closure or all main steam line isolation valves) neglecting the direct scram (valve position scram) i results in a maximum vessel pressure which, if a neutron flux ,

l scram is assumed considering 12 valves operable, results in adequate margin to the code allowable overpressure limit of 1375 psig.

To meet operational design, the analysis of the plant isolation transient (generator load reject with bypass valve failure to open) shows that 12 of the 13 relier valves limit peak system pressure to a value which is well below the allowed vessel overpressure of 1375 psis.

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4 1;IMITING CONDITIONS FOR OPERATION SURVEILt.ANCE A r'jtlI R EMENTS

^

4 I4. 6 PRIMARY SYSTEM BOUNDARY 1.6 ERIMARY SYSTEM BOUNDARY Coolant Leakaqe C. coolant Leakage C.

1. a. Any time irradiated 1. Reactor coolant fuel is in the system leakage shall be checked by the reactor vessel and semp and air sampling reactor coolant temperature is above system and recorded --

2120F, reactor at least once per coolant leakage into day.

the primary With the air sampling containment from 2.

system inoperable, unidentified sources grab samples shall be shall not exceed 5 obtained and analyzed gpm. In addition, at least once eve'ry the total reactor coolant system 2 86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br />.

leakage into the primary containment shall not exceed 25 qpm.

b. Anytime the reactor is in m RUN mode, reactor coolant

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leakage into the primary containment from unidentified sources shall not increase by more than 2 gpm averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in which the reactor is in the RUN mode except as defined in 3.6.C.1.c below. .

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c. During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the RUN mode following ,

startup, an increase in reactor coolant leakage into ,

the primary containment of

• i >2 gpm is acceptable as ' ' '

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3 long as the requirements '

i of 3.6.C.I.a are met. ,

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIMARY SYSTDI BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY

2. Both the sump and air sampling sampling systems shall be operable during reactor power D. Relief Valves operation. From and after the date that one of these systems 1. Approximately one-half of is made or found to be all relief valves shall be inoperable'for any reason, bench-checked or replaced reactor power operation is with a bench-checked valve permissible only during the each operating cycle.

succeeding seven days. All 13 valves will have been checked or replaced The air sampling system may upon the completion of be removed from service for a every second cycle.

period of 4. hours for calibra-tion, functional testing, and maintenance without providing 2. Or.ce during each operating a temporary monitor, cycle, each relief valve shall be manually opened

3. If the condition in 1 or 2 above until thermocouples and cannot be met, an orderly acoustic monitors down-shutdown shall be initiated and stream of the valve indicate the reactor shall be shutdown steam is flowing from the in the Cold Condition within valve.

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

D. Relief Valves _

1. When more than one relief 3, At least one relief valve valve is known to be failed, shall be disassembled and an orderly shutdown shall be inspected each operating initiated and the reactor cycle.

depressurized to less than 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

192

e 3.6/4.6 BASES limit specified for unidentified leakage, the probability is small that imperfections or cracks associated with such leakage would grow rapidly.

Ilowever, the establishment of allowabic unidentified leakage greater than that given in 3.6.C on the basis of the data presently available would be premature because of uncertainties associated with the data. For leakage of the order of 5-gpm, as specified in 3.6.C, the experimental and analytical data suggest a reasonable margin of safety that such leakage magnitude would not result from a crack approaching the critical size for rapid propagation. Leakage less than the magnitude specifi,ed can be detected reasonably in a matter of few hours utilizing the available leakage detection schemes, and if the origin cannot be determined in a.

reasonably short time the unit should be shutdown to allow further investigation and corrective action.

The 2 gpm limit for coolant leakage rate increase over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is a limit specified by the NRC (Reference 2). This limit applies only during the RUN mode to avoid being penalized for the expected coolant leakage increase during pressurization.

The total leakage rate consists of all leakage, identified and unidentified, which flows to the drywell floor drain and equipment drain sumps.

'The capacity of the drywell floor sump pump is 50 gpm and the capacity of the drywell equipment sump pump is also 50 gpm. Removal of 25 gpm from either of these sumps can be accomplished with considerable margin..

REFERENCES

1. Nuclear System Leakage Rate Limits (BFNP FSAR Subsection 4.10)

2. Safety Evaluation Report (SER) on IE Bulletin 82-03 e

224

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