Text

Proposed TS 3/4.6.2 Re Suppression Chamber Water Temp Instrumentation
	ML20078K020
Person / Time
Site:	Brunswick
Issue date:	11/16/1994
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20078K013	List: BSEP-94-0469, Application for Amends to Licenses DPR-62 & DPR-71,removing Specific Instrumentation Requirements for Suppression Chamber Water Temp Monitoring from TS 3/4.6.2,on Suppression Chamber; ML20078K020;
References
	NUDOCS 9411220167
	Download: ML20078K020 (24)
	v • d • e

.

ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 9411220167 941116 DR ADOCK 050v0324 PDR

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER l

LIMITING CONDITION FOR OPERATION l

3.6.2.1 The suppression chamber shall be OPERABLE with:

1 a.

The pool water:

3 1.

Volume between 87,600 ft and 89,600 ft3, equivalent to a level between -27 inches and -31 inches, and a 2.

Maximum average temperature of 95*F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:

a) 105'F during testing which adds heat to the suppression chamber.

j b) 110*F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

c)

20*F with the main steam line isolation valves closed following a scram.

b.

Tuc OPEPABLE suppression-chamber--wat4r-temperature inct rumentat ion

-ehannete-with-e-minimum of-1-1-operable--RTD-i-nput-e pc r channel.

i A total leakage from the drywell to the suppression chamber of less

-o.

than the equivalent leakage through a 1-inch diameter orifice at a differential pressure of 1 psig.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

1 With the suppression chamber water level outside the above limits, a.

restore the water level to within the limits within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in i

at least HOT SHUTDOWN within the n' ext 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than 95'F, restore the average temperature to less than or equal to 95'E within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , except, as permitted above:

BRUNSWICK - UNIT 1 3/4 6-9 Amendment No. 85

4 i

CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION (Continued) i ACTION:

(Continued) 1.

With the suppression chamber average water temperature greater than 105'F during testing which adds heat to the suppression chamber,stop all testing which adds heat to the suppression chamber and restore the average temperature to less than or equal to 95*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With the suppression chamber average water temperature greater than 110*F manually scram the reactor and operate at least one residual heat removal loop in the suppression poci cooling mode.

3.

With the suppression chamber average water temperature greater than 120*F, depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Hith one--suppeesden-chamber uater-temperature-instrumentation c.

-shannel-inoperable --restore-the-inoperat>Le-channel-to-OPERABLE-stet-sts r

-wkhir 7 day: ae-veeMy-suppresdon-eha mber--wate r-t-empe ra t u re-to-be-

-within the !!mit ct I ces-t-en c e pe r 12 hou r s.

d.

"ith bceh-suppression-chamber-water-temperature-instrumentat44n channels ireper2ble, rettere et lecct onc inc p c rebic - t empc rettece-

-inst rumentat ion chcnnel-tc OPEP>AE-etetu vi thin 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months cc-be-in-et-iuant !!Of-9HtfTDOWN within the next-12-hours and in COLD SiiUTDGWN

-4+hi*-the-fel4 ewing-24-hours,-

With the drywell-to-suppression chamber bypass leakage in excess of

-e r-the limit, restore the bypass leakage to within the limit prior to increasing reactor coolant temperature above 212*F.

i SURVEILLANCE REQUIREMENTS I

4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

liy vedfying the suppression chamber water volume to be within the a

limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l f

d BRUNSWICK - UNIT 1 3/4 6-10 Amendment No. 85 4

hI

. _. ~. -. _

~..~

... _.. ~

)

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in.0PERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to be, less than or equal to 95'F, except:

1.

At least once per.5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber average water temperature to be less than or equal to 105*F.

l 2.

At least once per hour when suppression chamber average water temperature is greater than 95'F, by verifying:

a)

Suppression chamber average water temperature to be less than or equal to 110*F, and b)

THERMAL POWER to be less than or equal to 1% of RATED THERMAL POWER.

i 3.

At least once per 30 minutes following a scram with suppression chamber average water temperature greate: than 95'F, by verifying suppression chamber average water temperature less th'an or equal to 120*F.

By an external visual examination of selected emergency, core cooling c.

' system suction line penetrations of the suppression chamber enclosure prior to taking the reactor from COLD SHUTDOWN after safety / relief-valve operation with the suppression chamber average water temperature greater than or equal to 160*F and reactor coolant system pressure greater than 200 psig.

d.

By "erifyiag at least tue supprec eien chember ester-temperetwe-Inserscatatica channets-OPERABLE-by perfuuuance of a:

1.

CHANNELCHECK-at-4eac t ence per 26 heurev-N "INEb FUNCTICFA1. TEST 2t leret enee per 31 daye, and i

3.

0"A!!NElr-GAldBRAT-ION-a t-leas t-ence-per-18r-monthe-(-MG-daysh--

irth the temperature-ekerm-secpoint--Jor-high-water temperature lee:

4 hen er eque bec 95'Fr-. DQ{'((O At least once per 18 months by:

l e.

1.

A visual inspection of the accessible interior of the suppression chamber and exterior of the suppression chamber enclosure.

MGE port:

ppcc 3/4 f ~lO b h1(RG60 oco TMS i

BRUNSWICK - UNIT 1 3/4 6-10a Amendment No. 130

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) fnoVC ro 2.

Conducting a drywell-to-suppression chamber bypass leak te t at pACC

\\

an initial differential pressure of 1 psig and verifying that the differential pressure does not decrease by more than l

3 /4 6-10'*

0.25 inches of water per minute for a 10 minute period.

l

~

D ELE TE THI 5 %GE l

BRUNSWICK - UNIT 1 3/4 6-10b Amendment No. 85 1

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued)

Experimental data indicate that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is maintained 0

below 160 F during any period of relief valve operation with sonic conditions at the discharge exit.

Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure suppression chamber loadings.

Because of the large volume and thermal capacity of the pressure suppression pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends.

By requiring the pressure suppression pool temperature to be continually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken.

The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

In addition to the limits on temperature of the suppression chamber pool water, cperating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open.

As a minimum this action shall include:

(1) use of all available means to close the valve, (2) initiate suppression pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of energy insertion to the pool.

The suppression chamber water temperature monitoring system performs a dual function.

It provides for post-accident monitoring as recommended by Regulatory Guide 1.97.

This system is also designed to meet the acceptance criteria of NUREC-0661, Appendix A in monitoring average suppression chamber water temperature during normal operating conditions.

Rufc6 i. v Seet-iens-3 /4.3 A4-end 3/4.64rl-fee-4rimiting-Condi+i

-for-Ope ca t ion-and-Surveillance-Requi+ement+-pecteining te each-function.

/)DD JtJSLAT rnom 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES ArrACHED PAGC The OPERABILITY of the primary containment isolation valves ensures that the primary containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the primary containment atmosphere or pressurization of the containment.

Primary containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

J BRUNSWICK - UNIT 1 B 3/4 6-4 Amendment No. 85

l Insert for Brunswick Unit 1 page B 3/4 6-4 During normal operating conditions, suppression chamber average water temperature is determined by using input from 11 of the 12 RTD locations. During accident / transient conditions the resultant mixing in the suppression chamber allows j

for valid average temperatures with fewer inputs.

I l

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR 62 REQUEST FOR LICENSE AMENDMENT SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:

a.

The pool water:

1.

Volume between 87,600 ft and 89,600 ft3, equivalent to a level 3

between -27 inches and -31 inches, and a 2.

Maximum average temperature of 95*F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:

a) 105*F during testing which adds heat to the suppression chamber.

b) 110*F with THERMAL POWER less than or equal to 17. of RATED THERMAL POWER.

c) 120*F with the main steam line isolation valves closed following a scram.

(j b.

Two OPERABLE cuppression-ehamberwater-temperature--lutrumancation.

ebenne-is-*tth-e-mittmum-of-41-operable-RTD inputa per channcl.

A total leakage from the drywell to the suppression chamber of less e,-

than the equivalent leakage through a 1-inch diameter orifice at a differential pressure of 1 psig.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION.

With the suppression chamber water level outside the above limits, a.

restore the water level to within the limits within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average f

water temperature greater than 95*F, restore the average temperature to less than or equal to 95*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT l

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the f ollowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , except, as permitted above.

l BRUNSWICK - UNIT 2 3/4 6-9 Amendment No.103

CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION (Continued)

ACTION:

(Continued) 1.

With the suppression chamber average water temperature greater than LO5'E caring testing which adds heat to the suppression chamber, stop all testing which adds heat to the suppression chamber and restore the average temperature to less than or equal to 95 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With the suppression chamber average water temperature greater than 110*F manually scram the reactor and operate at least one residual heat removal loop in the suppression pool cooling mode.

3.

With the suppression chamber average water temperature greater than 120*F, depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Wi-th--one-suppression-chamber--water-cesperecurc inetrumentation c.

ch2nnel inoperabic, restore-che-ieopereble-ehenncl to OPERAELE 5tatus days-or-verLf y-suppression-ehamber-wacar-temper-ature-to-be-wi-chin 7 within the limitc cc--4 east-once-perJ2-hours-d.

5?ith both cuppression-ehaaber-water--cemperature Lnst-rumentation inopar4ble-camparature ehannels-Laoperable -castore-at laast one r

1 *^ nmm # m eus-wLthin 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months s-er-be in 2t Lastrumencation channe

-least HOT SHUTD0!P' within the acxt 12 Scura and in COLD S"UT00tP' wi-tMw-the-4el4ewLng 24 Scucc.

With the drywell-to-suppression chamber bypass leakage in excess of

-er the licit, restore the bypass leakage to within the limit prior to increasing reactor coolant temperature above 212*F.

SURVEILLANCE REQUIREMENTS

4. 6. 2.1 The suppression chamber shall be demonstra'ted OPERABLE:

By verifying the suppression chamber water volume to be within the a.

limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

BRUNSWICK - UNIT 2 3/4 6-10 Amendment No. 103

4 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying ~he suppression chamber average water temperature to be 1e'ss than or equal to 95'F, ex' cept:

1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber average water' temperature to be less than or equal to 105'F.

2.

At least once per hour when suppression chamber average water temperature is greater than 95'F, by verifying:

a)

Suppression chamber average water temperature to be less than or equal to 110*F, and b)

THERHAL POWER to be less than or equal to 1% of RATED THERMAL POWER.

3.

At least once per 30 minutes following a scram with suppression chamber average water temperature greater than 95'F, by verifying suppression chamber average water temperature less than or equal to 120*F.

By an external visual examination of selected emergency core cooling c.

system suction line penetrations of the suppression chamber enclosure prior to taking the reactor from COLD SHUTDOWN af ter safety / relief valve operation with the suppression chamber average water temperature greater than or equal to 160*F and reactor coolant system pressure greater than 200 psig.

d.

By-ver4fying%c--4eest---two-suppre+eien-chamber essee-tempecesuee---

6t mme n t at i e n c h a nnels--OPERABLE--by-performanoe-of-a+-

1.

CMANNEL 0"ECK-et-1 cast oncepcrbbhour;.

2.

==L =CTwNAL = se les t oace per n asys, and-

)

i 4.

c=:Neu-eit-mR*= st te,atcocep ic maths c5ca.fsw eith the tcmpcrcturc clermdetpoint-4eMgh-water tcmpcraterc lc0c than or equa1-te-952Fr []Q{ "J'Q e.

At least once per.18 months by:

1.

A visual inspection of the accessible interior of the suppression chamber and exterior of the suppression chamber enclosure.

NOTC : Pact 3/4 i,-lob MEAG O * * * *

BRUNSWICK - UNIT 2 3/4 6-10a Amendment No. 160

~

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

Conducting a drywell-to-suppression chamber bypass leak test at PAGC an initial differential pressure of 1 psig and verifying that the dif ferential pressure does not decrease by more than 3/4 4-log 0.25 inches of water per minute for a 10 minute period.

~

DELETE THIs PAGE

(._)

1 BRUNSWICK - UNIT 2 3/4 6-10b Amendment No. 103

CONTAINMENT SYSTEMS

' BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued)

^

Experimental data indicate that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is maintained below 160 F during any period of relief valve operation with sonic conditions at the discharge exit.

Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure suppression chamber loadings.

Because of the large volume and thermal capacity of the pressure suppression pool, the volume and temperature normally change very slowly, and monitoring these parameters daily is sufficient to establish any temperature trends.

By requiring the pressure suppression pool temperature to be heat continually monitored and f requently logged during periods of significant addition, the temperature trends will be closely followed so that appropriate action can be taken.

The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

In addition to the limits on temperature of the suppression chamber pool water, operating procedures define the action to be taken in the event a relief valve inadvertently opeas or sticks open. As a minimum this action

(' 'j (1) use of all available means to close the valve, (2) shall include:

initiate suppression pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that o.f the stuck-open relief valve to assure mixing and unif ormity of energy insertion to the pool.

The suppression chamber water temperature monitoring system performs a dual function.

It provides for post-accident monitoring as recommended by Regulatory Guide 1.97.

This system la also designed to meet the acceptance criteria of NUREG-0661, Appendix A in monitoring average suppression chamber i

Refee-to-Sections-j water temperature during normal operating conditions.

//

3/^ 3.5.3 cad 3/^.4.2.1 f er Limiting Ccaditiene f cr Opc ction and Sdriebl-1-ance

~

acquire 22nes pertaining-to-esch-feneti-ent Abb JMSEnr (no m j

1-3 / 4. 6. 3 PRIMARY CONTAINMENT ISOLATION VALVES Arr4cHEb pAgg The OPERABILITY of the primary containment isolation valves ensures that q.

the primary containment atmosphere will be isolated f rom the outside in the event of a release of radioactive material to the primary environment S

containment atmosphere or pressurization of the containment.

Primary containment isolation within the time limits specified ensures that the re'Iease of radioactive material to the environment will be consistent with the I

assumptions used in the analyses for a LOCA.

j I,

)

BRUNSWICK - UNIT 2 B 3/4 6-4 Amendment No. 103

'1 l

I

Insert for Brunswick Unit 2 page B 3/4 6-4 During normal operating conditions, suppression chamber average water temperature is determined by using input from 11 of the 12 RTD locations. During accident / transient conditions the resultant mixing in the suppression chamber allows for valid average temperatures with fewer inputs.

s 4

s I

O 5

ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:

a.

The pool water:

1.

Volume between 87.600 ft and 89.600 ft, equivalent to a 3

3 level between -27 inches and -31 inches, and a 2.

Maximum average temperature of 95 F during OPERATIONAL i

CONDITION 1 or 2, except that the maximum average temperature may.be permitted to increase to:

a) 105 F during testing which adds heat to the suppression chamber.

b) 110 F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

~

c) 120 F with the main steam line isolation valves closed following a scram.

b.

A total leakage from the drywell to the suppression chamber of less than the equivalent leakage through a 1-inch diameter orifice at a differential pressure of 1 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1. 2 and 3.

ACTION:

a.

With the suppression chamber water level outside the above limits.

restore the water level to within the limits within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than 95 F, restore the average temperature to less than or equal to 95 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in.

at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , except, as permitted above:

BRUNSWICK - UNIT 1 3/4 6-9 Amendment No.

I

CONTA!NMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION (Continued)

ACTION:

(Continued) 1.

With the suppression chamber average water temperature greater than 105 F during testing which adds heat to the suppression chamber, stop all testing which adds heat to the suppression chamber and restore the average temperature to less than or equal to 95 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With the suppression chamber average water temperature greater than 110 F manually scram the reactor and operate at least one residual heat removal loop in the suppression pool cooling mode.

3.

With the suppression chamber average water temperature greater than 120 F. depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the drywell-to-sup3ression chamber bypass leakage in excess of the limit, restore t1e bypass leakage to within the limit prior to increasing reactor coolant temperature above 212 F.

1 SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

a.

By verifying the suppression chamber water volume to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to be less than or equal to 95 F. except:

1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber average water temperature to be less than or equal to 105 F.

BRUNSWICK - UNIT 1 3/4 6-10 Amendment No.

I q

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

At least once per hour when su)pression chamber average water temperature is greater tian 95 F. by verifying:

a)

Suppression chamber average water temperature to be less than or equal to 110 F. and b)

THERMAL POWER to be less than or equal to 1% of RATED THERMAL POWER.

3.

At least once per 30 minutes following a scram with suppression chamber average water temperature greater than 95 F, by verifying suppression chamber average water temperature less than or equal to 120 F.

c.

By an external visual examination of selected emergency core cooling system suction line penetrations of the suppression chamber enclosure prior to taking the reactor from COLD SHUTDOWN after safety / relief valve operation with the suppression chamber average water temperature greater than or equal to 160 F and reactor coolant system pressure greater than 200 psig.

d.

Deleted.

I e.

At least once per 18 months by:

1.

A visual inspection of the accessible interior of the suppression chamber and exterior of the suppression chamber enclosure.

2.

Conducting a drywell-to-suppression chamber bypass leak test at an initial differential pressure of 1 psig and verifying that the differential pressure does not decrease by more than 0.25 inches of water per minute for a 10 minute period.

l 4

e (Page 3/4 6-10b has been deleted.)

l BRUNSWICK - UNIT 1 3/4 6-10a Amendment No.

l

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued)

Experimental data indicate that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is maintained below 160 F during any period of relief valve operation with sonic conditions at the discharge exit.

Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure suppression 4

chamber loadings.

Because of the large volume and thermal capacity of the pressure suppression 3001, the volume and temperature normally changes very slowly, and monitoring t1ese parameters daily is sufficient to establish any temperature trends.

By requiring the pressure suppression pool temperature to be continually monitored and frequently logged during periods of significant heat addition. the temperature trends will be closely followed so that appropriate action can be taken.

The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

In addition to the limits on temperature of the suppression chamber pool water, operating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open.

As a minimum this action shall include:

(1) use of all available means to close the valve, (2) initiate suppression pool water cooling heat exchangers. (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of energy insertion to the pool.

The suppression chamber water temperature monitoring system performs a dual function.

It provides for post-accident monitoring as recommended by Regulatory Guide 1.97. This system is also designed to meet the acceptance criteria of NUREG-0661. Appendix A in monitoring average suppression chamber water temperature during normal operating conditions, During normal operating conditions, suppression chamber average water temperature is determined by using input from 11 of the 12 RTD locations.

During accident / transient conditions the resultant mixing in the suppression chamber allows for valid average temperatures with fewer inputs.

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES The OPERABILITY of the primary containment isolation valves ensures that the primary containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the primary containment atmosphere or pressurization of the containment.

Primary 1

containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

BRUNSWICK - UNIT 1 B 3/4 6-4 Amendment No.

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1 ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 NRC DOCKETS 50-325 AND 50-324 OPERATING LICENSES DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2

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CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDIT:3N FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:

a.

The pool water:

3 3

1.

Volume between 87.600 ft and 89.600 ft. equivalent to a level between -27 inches and -31 inches, and a 2.

Maximum average temperature of 95 F during OPERATIONAL CONDITION 1 or 2. except that the maximum average temperature may be permitted to increase to:

a) 105 F during 'osting which adds heat to the suppression Frabor.

b) 110 F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.

c) 120 F with the main steam line isolation valves closed following a scram.

b.

A total leakage from the drywell to the suppression chamber of less than the equivalent leakage through a 1-inch diameter orifice at a differential pressure of 1 psig.

APPL.ICABILITY: OPERATIONAL CONDITIONS 1. 2 and 3.

ACTION:

a.

With the suppression chamber water level outside the above limits, restore the water level to within the limits within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUIDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than 95 F. restore the average temperature to less than or equal to 95 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months except as permitted above:

BRUNSWICK - UNIT 2 3/4 6-9 Amendment No.

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CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION (Continued)

ACTION:

(Continued) i 1.

With the suppression chamber average water temperature

. greater than 105 F during testing which adds heat to the suppression chamber, stop all testing which adds heat to the suppression chamber and restore the average temperature to less than or equal to 95 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With the suppression chamber average water temperature greater than 110 F manually scram the reactor and operate at least one residual heat removal loop in the suppression pool cooling mode.

3.

With the suppression chamber average water temperature greater than 120 F depressurize the reactor pressure vessel.

to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

With the drywell-to-suparession chamber bypass leakage in excess of the limit, restore t1e bypass leakage to within the limit prior to increasing reacter coolant temperature above 212 F.

SURVEILLANCE REQUIREMENTS 4.6.2.1 The. suppression chamber shall be demonstrated OPERABLE:

a.

By verifying the suppression chamber water volume to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to be less than or equal to 95 F, except:

1.

At least once per 5 minutes during testing which adds heat to the suppression chamber, by verifying the suppression chamber average water temperature to be less than or equal to 105 F.

r BRUNSWICK - UNIT 2 3/4 6-10 Amendment No.

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CONTAINMEhe SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

At least once per hour when su]pression chamber average water temperature is greater tlan 95 F. by verifying:

a)

Suppression chamber average water temperature to be less than or equal to 110 F, and b)

THERMAL POWER to be less than or equal to 1% of RATED j

THERMAL POWER.

3.-

At least once per 30 minutes following a' scram with suppression chamber average water temperature greater than 95 F. by verifying suppression chamber average water j

temperature less than or equal to 120 F.

c.

By an external ~ visual examination of selected emergency core cooling system suction line penetrations of the suppression chamber enclosure prior to taking the reactor from COLD SHUTDOWN after safety / relief. valve operation with the suppression chamber average water temperature greater than or equal to 160 F and reactor coolant system pressure greater than 200 psig.

d.

Deleted.

I e.

At least once per 18 months by:

1.

A visual inspection of the accessible interior of the suppression chamber and exterior of the suppression chamber enclosure.

2.

Conducting a drywell-to-suppression chamber bypass leak test at an initial differential pressure of 1 psig and verifying that the differential pressure does not decrease by more than 0.25 inches of water per minute for a 10 minute period.

t i

P (Page 3/4 6-10b has been deleted.)

I BRUNSWICK - UNIT 2 3/4 6-10a Amendment No.

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C0tITAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued)

Experimental data indicate that excessive steam condensing loads can be avoided if the peak temperature of the pressure suppression pool is maintained below 160 F during any period of relief valve operation with sonic conditions at the discharge exit. Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid the regime of potentially high pressure suppression chamber loadings.

Because of the large volume and thermal capacity of the pressure suppression 3001, the volume and temperature normally change very slowly, and monitoring t1ese parameters daily is sufficient to establish any temperature trends.

By requiring the pressure suppression pool temperature to be l

continually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken. The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

In addition to the limits on temperature of the suppression chamber pool water operating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open.

As a minimum this action shall include:

(1) use of all available means to close the valve. (2) initiate suppression pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if other relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief ~ valve to assure mixing and uniformity of energy insertion to the pool.

The suppression chamber water temperature monitoring system performs a dual function.

It provides for post-accident monitoring as recommended by Regulatory Guide 1.97.

This system is also designed to meet the acceptance criteria of NUREG-0661. Appendix A in monitoring average suppression chamber water temperature during normal operating conditions.

During normal operating conditions, suppression chamber average water temperature is determined by using input from 11 of the 12 RTD locations.

During accident / transient conditions the resultant mixing in the suppression chamber allows for valid average temperatures with fewer inputs.

3/4.6.3 PRIMARY CONTAINMENT 1501 ATION VALVES The OPERABILITY of the primary containment isolation valves ensures that the primary containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the primary containment atmosphere or pressurization of the containment.

Primary containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

BRUNSWICK - UNIT 2 B 3/4 6-4 Amendment No.

I

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ML20078K020

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