ML20138K673
| ML20138K673 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/15/1997 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20138K667 | List: |
| References | |
| NUDOCS 9702190089 | |
| Download: ML20138K673 (11) | |
Text
. 1 ;
i l CONTAINMENT SYSTEMS l
3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION l
3.6.2.1 The suppression chambor shall be OPERABLE with:
- a. The pool water: bh h k
- 1. Volumebetween('/M9ft3 and 6'9 3 @ ft3, equivalent to a level between -27 inches and -31 inches, and a
- 2. Maximum average temperature of 95*F during OPERATIONAL 1 CONDITION 1 or 2, except that the maximum average temperature j may be permitted to increase to: l 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 j
- THERMAL POWER.
c) 120*F with the main s!n.m line isolation valves closed following a scram.
- b. Two OPERABLE suppression chamber water temperature instrumentation channels with a minimum of 11 operable RTD inputs per channel. I J
- c. A total leakage from the drywell to the suppression chamber of less than the equi. valent leakage through a 1-inch diameter orifice at a differentiai pressure of 1 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. I ACTION: l l
- 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the n' ext 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN i within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 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 hou s or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CGLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as sermitted above:
)
9702190089 970115 PDR ADOCK 05000":.24
- P FOR BRUNSWICK - UNIT 1 3/4 6-9 AmendmentNo.hfh)
,, [,CONTAINMENTSYSTEMS BASES 2
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS The specifications of this section ensure that the primary containment pressure will not exceed the calculated pressure of 40 psig during primary system blowdown from full operating pressure.
i The pressure suppression pool water provides the heat sink for the reactor primary system energy release following a postulated r'upture of the system.
The pressure suppression chamb.er water volume must absorb the associated decay
' and structural sensible heat released during primary system blowdown fro'm 1045 psig. Since all of the gases in the drywell are purged into the pressure l-suppression chamber air space during a loss of coolant accident, the pressure -
of the liquid must not exceed 62 psig, the suppression chamher maximum"
, pressure. The design volume of the suppression chamber, water and air, was obtained by considering that the total volume of reactor coolant to be condensed is discharged to the su]pression chamber and that the drywell volume is (M'B43) purged to the suppression chamaer. ~
Using the minimum or maximum water volumes given in the specification, containment pressure during the design basis accident is approximately 4 i which is below the design pressure of 62 psig. Maximum water volume of $,59 ft' results in a downcomer submergence of 3'4" and the minimum volume of./65 ft' results in a submergence approximately four inches less.
%M The Monticello tests were rnn with a submerged length of three feet and with complete condensation. Thus, with respect to the downcomer submergence, this specification is adequate. The maximum temperature at the end of the blowdown .
tested during the Humboldt Bay and Bodega Bay tests was 170*F, and this is conservatively taken to be the limit for complete condensation of the reactor i j coolant, although condensation would ocm for temperatures above 170*F.
When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.3.3.
l Under full power operation conditions, blowdown from an initial suppression chamber water temperature of 90'F results in a water temperature of apptaximately 135'F immediately following blowdown, which is below the temperature 170*F used for complete condensation. At this temperature and atmospheric pressure l and core spray pumps, ; the available thus, there is no NpSH exceeoson dependency that required by both the RHR containment overpressure during the accident injection phase. If both RHR loops are used for containment cooling, there is no dependency on containment overpressure for post-LOCA operations, i
BRUNSWICK - UNIT 1 B 3/4 6-3 Amendment No. @ l
. - _ _ . _ . . . - . - . . _ .. _- . _ . . - . _ . . . .. . - _ _ _ . - . _ _ _ _ . . _ . . _ _ ___m _ _
1- .-
l f
ENCLOSURE 6 L
i I
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 !
!. REQUEST FOR LICENSE AMENDMENTS i
REVISION OF SUPPRESSION POOL WATER VOLUMES h
MARKED-UP TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 2 !
t l
- I t
I :
1 I
l l
l' l
4 Y' I
< a l
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l , ,
CONTAINMENT SYSTEMS 1
, 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER f
LIMITING CONDITION FOR OPERATION ,
t 3.6.2.1 The suppression chamber shall be OPERABLE with:
- a. The pool water: 7 M I
- 1. Volume between 3
a(6QD ft and 3664 ft3, equivalent to a level between -27 inches and -31 inches, and a i
- 2. Maximum average temperature of 95'F during OPERATIONAL !
CONDITION 1 or 2, except that the maximum average temperature f 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. Two OPERABLE suppression chamber water temperature instrumentation channels with a minimum of 11 operable RTD inputs per channel. i
- 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 l 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SEUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT ,
SHJTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SBJTD0WN within the j l
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as permitted above:
]
l l BRUNSWICK - UNIT 2 3/4 6-9 AmendmentNo.(hff)
- . l CONTAINMENT SYSTEMS BASES -
3/4.6.2 DEPRESSURIZATION AND C0OLING SYSTEMS The specifications of this section ensure that the pr.imary containment pressure will not exceed the calculated pressure of 49 psig during primary system blowdown from full operating pressure.
The pressure suppression pool water provides the heat sink for the reactor primary system energy release following a postulated rupture of the system.
The pressure suppression chamber water volume _must absorb the associated decay and structural sensible heat released during primary system blowdown from 1045 psig. Since all of the gases in the drywell are purged into the pressure I suppression chamber air space during a loss of coolant accident, the pressure of the liquid must not exceed 62 asig, the suppression chamber maximum pressure. The design volume of tie suppression chamber, water and air, was obtained by considering that the total volume of reactor coolant to be condensed is discharged to the su3pression chamber and that the drywell volume is purged to the suppression chamaer.
Using the minimum or maximum water volumes given in the specification, containment pressure during the design basis accident is approximately 49 s1 which is below the design pressure of 62 psig. Maximum water volume of . f t' results in a downcomer submergence of 3'4" and the minimum volume of/N/f4Gft results in a submergence approximately four inches less.
The Monticello tests were run with a submerged length of three feet and with 545 omplete condensation. Thus, with respect to the downcomer submergence, this specification is adequate. The maximum temperature at the end of the blowdown test during the Humboldt Bay and Bodes Bay tests was 170*F, and this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170*F.
When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.3.3.
Under full power operation conditions, blowdown from an initial suppression chamber water temperature of 90*F results in a water temperature i of approximately 135'F immediately following blowdown, which is below the '
temperature 170*F used for complete condensation. At this temperature and ;
atmospheric pressure, the available NpSH exceeds that required by both the RHR '
and core spray punps; thus, there is no dependency on containment overpressure during the accident injection phase. If both RHR loops are used for containment cooling, there is no dependency on containment overpressure ;
for post-LOCA operations. '
i i
BRUNSWICK - UNIT 2 B 3/4 6-3 Amendment No, h I
..; e i
l ENCLOSURE 7 l i
l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 i NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REVISION OF SUPPRESSION POOL WATER VOLUMES
.l
'j TYPED TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 1 !
)
i l
l l
W
j** s
!~ CONTAINMENT SYSTEMS
{ 3/4.6.2. DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER i
,. LINITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:
j f
[ a. The pool water: i
- 1. Volume between 86,545 fts and 89,843 fts, equivalent to a l ,
i level between -27 inches and -31 inches, and a l
- i
- 2. Maximum average temperature of 95'F during OPERATIONAL !
CONDITION 1 or 2, except that the maximum average i 1
temperature may be permitted to increase to.
a) 105*F during testing which adds heat to the [
suppression chamber. I 1
b) 110*F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
c) 120*F with sta main steam line isolation valves closed following a scram,
- b. Two OPERABLE suppression chamber water temperature instrumentation channels with a minimum of 11 operable RTD inputs per channel.
- 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN withir the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD.
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as permitted above:
i BRUNSWICK - UNIT 1 3/4 6-9 Amendment No. I
{
L _ _ _ - _ __ _ l
.. I, l ' CONTAINMENT SYSTEMS
! BASES -
i
~
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS The specifications of this section ensure that the primary containment
- pressure will not exceed the calculated pressure of 49 psig during primary system blowdown from full operating pressure.
! The pressure suppression pool water provides the heat sink for the ,
i reactor primary system energy release following a postulated rupture of the :
i system. The pressure suppression chamber water volume must absorb the associated decay and structural sensible heat released during primary system :
blowdown from 1020 psig. Since all of the gases in the drywell are purged
. into the pressure suppression chamber air space during a loss of coolant !
i accident, the pressure of the liquid must not exceed 62 psig, the su)pression '
, chamber maximum pressure. The design volume of the suppression cham >er, water l and air, was obtained by considering that the total volume of reactor coolant !
to be condensed is discharged to the suppression chamber and that the drywell l volume is purged to the suppression chamber.
! Using the minimum or maximum water volumes given in the specification, l containment pressure during the design basis accident is approximately
- 49 psig, which is below the design pressure of 62 psig. Maximum water volume
- of 89,843 ft* results in a downcomer submergence of 3'4" and the minimum i volume of 86,545 ft* results in a submergence approximately four inches less.
The Monticello tests were run with a submerged length of three feet and with ,
! complete condensation. Thus, with respect to the downcomer submergence, this j specification is adequate. The maximum temperature at the end of the blowdown
- ' tested during the Humboldt Bay and Bodega Bay tests was 170*F, and this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170*F.
When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.3.3.
Under full power operation conditions, blowdown from an initial suppression chamber water temperature of 90*F results in a water temperature of approximately 135'F immediately following blowdown, which is below the temperature 170*F used for complete condensation. At this temperature and atmospheric pressure, the available NPSH exceeds that required by both the RHR and core spray pumps; thus, there is no dependency on containment.
overpressure during the accident injection phase. If both RHR loops are used for containment cooling, there is no dependency on containment overpressure for post-LOCA operations.
I BRUNSWICK - UNIT 1 B 3/4 6-3 Amendment No. I
ENCLOSURE 8 I I
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 :
OPERATING LICENSE NOS. DPR-71 AND DPR-62 !
REQUEST FOR LICENSE AMENDMENTS {
REVISION OF SUPPRESSION POOL WATER VOLUMES l TYPED TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 2 I.
1
'1 1
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:
A
- a. The pool water:
- 1. Volume between 86,5458 ft and 89,843 ft*, equivalent to a l 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,
- b. Two OPERABLE suppression chamber water temperature instrumentation 4
channels with a minimum of 11 operable RTD inputs per channel.
- c. A total leakage from the drywell to the suppression chamber of less than ths equivalent leakage through a 1-inch diameter orifice at a differential pressure of 1 psig. ,
1 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD ,
SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. !
- 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in ,
at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD l SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as permitted above:
BRUNSWICK - UNIT ?, 3/4 6-9 Amendment No. I
- - ~ .-
,I.
- j CONTAINMENT SYSTEMS 4 BASES-i
- 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS :
The specifications of this section ensure that the primary containment pressure will not exceed the calculated pressure of 49 psig during primary system blowdown from full operating pressure.
The pressure suppression pool water provides the heat sink for the i
reactor primary system energy release following a postulated rupture of the system. The pressure suppression chamber water volume must absorb the associated decay and structural sensible heat released during primary system blowdown from 1020 psig. Since all of the gases in the drywell are purged j into the pressure suppression chamber air space during a loss of coolant i
accident, the pressure of the liquid must not exceed 62 psig, the suppression j chamber maximum pressure. The design volume of the suppression chamber, water and air, was obtained by considering that the total volume of reactor coolant ;
to be condensed is discharged to the sup>ression chamber and that the drywell '
) volume is purged to the. suppression cham)er, i
Using the minimum or maximum water volumes given in the specification, containment pressure during the design basis accident is approximately 49 psig, which is below the design pressure of 62 psig. Maximum water volume 4
of 89,843 ft* results in a downcomer submergence of 3'4" and the minimum j volume of 86,545 ft* results in a submergence approximately four inches less.
e The Monticello tests were run with a submerged length of three feet and with t
complete condensation. Thus, with respect to the downcomer submergence, this
'- specification is adequate. The maximum temperature at the end of the blowdown test during the Humboldt Bay and Bodega Bay tests was 170*F, and this is conservatively taken to be the limit for complete condensation of the reactor j coolant, although condensation would occur for temperatures above 170*F.
1 When it'is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.3.3.
Under full power operation conditions, blowdown from an initial suppression chamber water temperature of 90*F results in a water temperature of approximately 135'F immediately following blowdown, which is below the temperature 170*F used for complete condensation. At this temperature and atmospheric pressure ,
and core spray pumps;, thethere thus, available NPSH exceeds is no dependency that required by both the RHR on containment overpressure during the accident injection phase. If both RHR loops are used for containment cooling, there is no dependency on containment overpressure for post-LOCA operations.
BRUNSWICK - UNIT 2 B 3/4 6-3 Amendment No. I