Text

Proposed Tech Specs,Revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements
	ML20216G796
Person / Time
Site:	Brunswick
Issue date:	04/09/1998
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20216G789	List: BSEP-98-0037, Application for Amends to Licenses DPR-62 & DPR-72,revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements; ML20216G796;
References
	NUDOCS 9804200489
	Download: ML20216G796 (20)
	v • d • e

.

ENCLOSURE 5 13RUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50 325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS SUPPRESSION CilAMBER WATER TEMPERATURE MONITORING INSTRUMENTATION (NRC TAC NOS. M90954 AND M90955) l l

TYPED TECHNICAL SPECIFICATION PAGES - UNIT NO. I i

l l

I 4

9804200489 980409 PDR ADOCK 05000324 P PDR

. 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 -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) 110aF 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. I

b. (Deleted) l c. A total leakage from the drywell to the suppression chamber of l 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:

I l a. With the suppression chamber water level outside the above limits. I l 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 4 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 i 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

CONTAINMENT 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 THERMAL POWER.

3. At least once per 30 minutes following a scram with sup)ression chamber average water temperature greater than 95 , 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.

l

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.

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

. CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION (Continued)

ACTIO!i: (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 , i

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 reattor 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. (Deleted)

d. (Deleted)

e. 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. l 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

h0NTAINMENTSYSTEMS 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 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 fellowing 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. I 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.

I 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVLS The OPERABILITY of the primary containment isolation valves ensures that j 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.

l l

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

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS SUPPRESSION CilAMBER WATER TEMPERATURE MONITORING INSTRUMENTATION (NRC TAC NOS. M90954 AND M90955) 4 1

l l

I TYPED TECilNICAL SPECIFICATION PAGES - UNIT NO. 2 l

. 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:

i

a. The pool water:

1. Volume 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 1% of RATED THERMAL POWER. :

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

b. (Deleted)

c. 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.

l ACTION:

I

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 l average water temperature greater than 95 F. restore the average j 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 l SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , except, as permitted !

above: )

l l

l i

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

CONTAINMENTSYSTEMS LIMITING LONDITIONS 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, j

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 .

l c. (Deleted)

d. (Deleted)

e. With the drywell-to-sup3ression chamber bypass leakage in excess

of the limit, restore t1e bypass leakage to within the limit prior l to increasing reactor coolant temperature above 212*F.

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

1

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

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

CONTAINHENT 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 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.

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

a) Suppressionchamberaveragewatertemperaturetobe 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 supressionchamberaveragewatertemperaturegreaterthan 95 2 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)

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

, 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 l below 160 F during any period of relief valve operation with sonic conditions l at the discharge exit. Specifications have been placed on the envelope of

reactor operating conditions so that the reactor can be depressurized in a I timely manner to avoid the regime of potentially high pressure suppression l chamber loadings.

Because of the lar e volume and thermal capacity of the pressure i suppression 2001, the vo ume and temperature normally change very slowly, and l 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 l addition, the temperature trends will be closely followed so that appropriate action can be taken. The requirement for an external visual examination l following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention i 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 i 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 l shall include: (1) use of all available means to close the valve, (2) l initiate suppression pool water cooling heat exchangers, (3) initiate rm ctor

! 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.

i I 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES l The OPERABILITY of the primary containment isolation valves ensures that I the primary containment atmosphere will be isolated from the outside

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

l l

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

ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS SUPPRESSION CIIAMBER WATER TEMPERATURE MONITORING INSTRUMENTATION (NRC TAC NOS. M90954 AND M90955)

\

MARKED-UP TECIINICAL SPEC'FICATION PAGES - UNIT NO. I

L 1

. CONTAINMENT SYSTEMS l

o j 3/4.6.2 DEPRESSUR12ATION SYSTEMS l.

SUPPRESSION CHAMBER l

l LIMITING CONDITION FOR OPERATION 1

3.6.2.1 The suppression chamber shall be OPERABLE with:

I

a. The pool water: '

1. 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.

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.

h Ln ADCDADIC ci annene c 4 nn chsmhar ustar t amna r nt n era 4 n ct ri smant s t i nn

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. ka. i.[. Nr. r.5 h.i. bb.b.h. b. nar

r. E.h. .E.n. E. A. 5 r .Es.[~e

c. 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. I ACTION: i

a. Wi-th 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:

l l

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

l CONTAINMENT SYSTEMS LIMITINC 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 l 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 temperatura greater than 120'F, depressurize the reactor pressure vessel to less than 200 psis within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. (9!(Deleted) h ::: ce;;r ::!ce '--5:: r ter t:r;:::ter: !:::: : tetic:

c'-- 21 1 ep ::512, ::: tere the ine; ::ble c' - 1 t: OP!"^=LE ::::::

r 8 th8- day: er :: !fy ee;;::::!: c': ':: r:ter :: ;::::::: :: L a-l -ri*'8- the 18 8 t: et 1 ::t :::: p:: 12 h::::.

(Dekked)

d. ( With 5:th cr;;::::!en c'--'er reter :::;:::ture in:t r -tetien l c'-- :1: 12:;::51 , ::: tere et 1:::: ::: !::p:::51: :: ;:::::::

r__._____...r._

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e. i---

e . .

. . . . . - ..:.t.r

.. __. t._.

r_

l 1:::: "^T 5"" = = rith8: th: :::: 12 h:::: ::d in COLD SHUTDOWN-r th8 8

the f 11er 8 2- ?$ h :::.

1

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

the limit, restore the bypass leakage to within the limit prior to l increasing reactor coolant temperature above 212*F. i l $0RVEILLANCE REQUIREMENTS i

\

l !

! 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:

l

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

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

l e

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

I CONTAINMENT SYSTEMS j 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 the suppression chamber average water temperature to be, less than or equal to 95'F, excepet ,

1. At least once per 5 minutes during testing which adds heat to the suppression chamber, by veeifying the suppression chamber j 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 verifyings .

l a) Suppression chamber average water temperature to be less l than or, equal to 110*F, and i 1

b) THERMAL POWER to be less than or equal to 1% of RATED i THERMAL POWER. l

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 ttian 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. !

{ Deleted) l

d. (By n !!y! : et le::: t= ::;; :::icn c'--i : :::: :-;:::ter: i

!::tr--- t:t!= '-- :1: 0""" ^ =L_" by p::f:-- :: Of :H

1. """ ~~' 0""CK :: 1 ::: :::: ;;; 24 h :::-

-2. "" ^ =Ei "'2""TI^" MST :: 1:::t :::: p:: 31 drye, tro m !^= :: 1::: : :: ;:: l' :::the (550 E;:)-

--ith the t 1, ::tur: 12 ; ::Op-int f;; hi;;h :::: t z;::::::: 1:::

.u__

_ _ -,..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.

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

CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued) l l Experimental data indicate that excessive steam condensing loads can be i

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 i reactor operating conditions so that the reactor can be depressurized in a l l timely manner to avoid the regime of potentially high pressure suppression i chamber loadings. '

l l

' Because of the large volume and thermal capacity of the pressure l suppression pool, the volume and temperature normally changes very slowly and I 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 I addition, the temperature trends will be closely followed so that appropriate action can be taken. The requirement for an external visual examination l

following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention l 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 l relief 'ralve inadvertently opens or sticks open. As a minimum this action I

shall includes (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, l

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 a ppress* n c r wat tem rature nito ing sys a pe forms a l 1f tion. t pro ides to post ceiden moni ring as reco ded b egula ry Gul e 1.97 This yet is also desig d to a t th accepta ce crite la of C-0 1, Ap dix in non orin average suppr ssion c ber wat tempe sture urirs real ratin cond* ions. efer o Se ions 3 4.3.5. and 3/ .6.2. for Li sting onditi s fo Operati n an 5 rvaill ce Re iremen s per ining ese functio .

- ~ ~ _

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 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 l

BRUNSWICK - UNIT 1 8 3/4 6-4 Amendment No. [

l l

ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2

, DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR 62 l SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS SUPPRESSION CIIAMBER WATER TEMPERATURE MONITORING

INSTRUMENTATION (NRC TAC NOS. M90954 AND M90955) i l

l MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT NO. 2 I

i 1

l

r 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. 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.

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.

s b - ( @1", .X .Y_.f. .m . ,",M,

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,. . .L ..

^--

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.r

?.t..'J.

r

""+

~+

. ..i.. ~'7..."M.

. . ' + ' ~ "V

c. 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:

f l

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

CONTAINMENT SYSTEMS s LIMITING CONDITIONS FOR OPERATION (Continued)

ACTION: (Continued) l

1. With the suppression chamber averaga water temperature greater than 105'F daring 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 .

l ith ::: : ;pr:::ic:

c. q{ h3eleted) :E: bce e ::: : ; ::ter: instrumentasten-her 21 in:;:::ble, ::::::: the 12 ; r ble ch --21 t: OF'"'*LE etzte:

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d. (("ithDeleled) h:th ;;;;;;;:10 ch: b; :::: :;;;;;:ture in:truesatsel : l

., ) chen;;1: in;;;;;ble, ::::::: :: 1:::: ;;: in:p:::ble :::;:::::::

in::rur:::::ic: 'ch::::1 :: OPEEi"LE :::::: eithin 8 h ::: :: be in-et-1 ::: "0T S""TOO"N withi; th :::: 12 h:::: ::d in COLD SSL'TDCUN l vithi th: f:11: ring 24 h::::.-

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

SURVEITTANCE REQUIREMENTS 4'. 6. 2.1 The suppression chamber shall be demonstra'ted'0PERABLE:

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 .

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

CONTAINHENT SYSTEMS I

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 the suppression chamber average water temperature to be 1e'es than or equal to 95'F, ex'cepts

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) 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 I 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. 4; (";Dele :::ifying ted) :: 1eee: ::: ::;;::::i:: c'--t:: :::: :: ;; :::::

8--tr--- tetien e'- OPE"^?t! by perfer-- :: ef :!

1. ""^""*L """"E at 10--! Orr- tr [A h?'2r":

2. " " ' " " * ' . =f""I^"^ t TT :: 1:::: c' : :: ;:: 31 dry:,* -d

2. """==5L "^'T!".^.TI^" :: 1 ::: :::: p:: l' ::th: '550 d y:).-

ith th;: :T;;;;;;;; ;1;r: ^;;;0!!! f0 h!"h ""*"* t"- Tr"*"*" '"""

t'- :: :s;;i :: ""'Fr 4

e. At least once per.18 months by: '

i

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

l

~

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

l l

CONTAIMiENT SYSTEMS BASES f*

l 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued) l l Experimental data indicate

hat excessive steam condensing loads can be avoided if the ped. 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 j

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 continually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate l

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 4 water., operating procedures define the action to be taken in the event a relief valve inadvertently opsna or sticks open. As a minimum this action l(.)

l shall includes (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.

3-- _

ring ystem a The uppres ion ch ber w ter to eratu e moni rfo It pr vides or pos -accid ne non torin as rec nde by ual f ction Regul ory de 1. . Th Lysr is a o desi ned to meet t acc cance G-%6 5, tori aver e supp essio chambe l},i

crit ria of pendixj in Refe to Se ions j wat r temp rs* ca uring normal /oferat g co tions nditi s for Operat n and devei ance 3/ .3. ! . 's and 3/ . 6.2.1 f or Li i t ing il

=

j quire nts pe taini to es fun ion. _

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 f rom 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 reiease of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

\(a BRUNSWICK - UNIT 2 B 3/4 6-4 Amendment No. Y i h

i! l l

ML20216G796

Text

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