ML20093F108
| ML20093F108 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-062) |
| Issue date: | 09/22/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20093F112 | List: |
| References | |
| DPR-62-A-103 NUDOCS 8410120392 | |
| Download: ML20093F108 (15) | |
Text
pa ato og'o UNITED STATES
'g E
NUCLEAR REGULATORY COMMISSION g
D. j WASHINGTON, D. C. 20555 g,
,/
CAROLINA POWER & LIGHT COMPANY' DOCKET NO. 50-324 BRilNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. OPR-62 1.
The Nuclear Regulatory Commission (the Commission) has founc that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 29, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Tec5nical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
8410120392 840922 PDR ADOCK 05000324 P.
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its iscuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/,?Y a.;M G'A
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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 22, 1984 ya d
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l ATTACHMENT TO LICENSE AMENDMENT N0. 103 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as indicated below. The changed areas are indicated by verticalilines.
Remove Insert 3/4 3-51 3/4 3-51 3/4 3-52a 3/4 3-52a 3/4 3-52c 3/4 3-52c 3/4 6-9 3/4 6-9 3/4 6-10 3/4 6-10 3/4 6-10a 3/4 6-10a 3/4 6-10b 3/4 6-10b 3/4 6-18 3/4 6-18 3/4 6-19 3/4 6-19 B 3/4 3-3 B 3/4 3-3 B 3/4 6-3 8 3/4 6-3 8 3/4 6-4 B 3/4 6-4 4
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(BSEP-2-12/28) s T
TABLE 3.3.5.3-1 ACCIDENT MONITORINC INSTRUMENTATION
_Eg HINIMUM APPLICABLE i
REQUIRED NUMBER CHANNELS OPERATIONAL
'f i '
INSTRUMENT AND INSTRUMENT NUMBER OF CHANNELS I
_ OPERABLE CONDITIONS
_ ACTION i a
- 1. Reactor Vessel Pressure 2
I 1, 2 82 (B21-PI-R004A,B; C32-LPR-R608; w
]
and C32-PT-N005A,B)
1 1, 2 82 (821-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,8; B21-LT-NO37; and B21-LTH-N037-1)
- 3. Suppression Chamber Water Level 2.
I 1.,2 82 t*,
(CAC-LT-2601; CAC-LI-2601-1) i*
(CAC-LT-2602; CAC-LR-2602)
! Y U
- 4. Suppression Chamber Water Temperature 2
1 1, 2 82(b) j (CAC-TE-4426-2 thru 13; CAC-TY-4426-l; CAC-TR-4426-1)
(CAC-TE-4426-15 thru 26; CAC-TY-4426-2; CAC-TR-4426-2)
- 5. Suppcession Chamber Atmosphere Temperature 2
1 1, 2 82(b)
(CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
)
CAC-TR-4426-1(2); C91-P602)
- 6. Drywell Pressure 2
1 1, 2 82 (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)
Ir
(
- 7. Drywell Temperature 2
11 1, 2 82(b)
(CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-i(2);
ta CAC-TR-4426-!(2); C91-P602)
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f
- 8. Drywell Radiation 2
2 (CAC-AR-1260; CAC-AQil-1260-1,2,3;
,y 1, 2, 3
.81 m
j 8
, CAC-AR-1261; CAC-AQll-1261-1,2,3;
)
CAC-AR-1262; CAC-AQll-1262-1,2,3) i
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(BSEP-2-12/28)
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5 TABLE 3.3.5.3-1 (Continued)
ACCIDENT HONITORING INSTRIDfENTATION O
1 HINIHlff APPLICABLE i
REQUIRED N19tBER CilANNELS OPERATIONAL O
INSTRitlENT AND INSTRIA1ENT NIRIBER OF CHANNELS OPERABLE
_ CONDITIONS ACTION'.
w
- 13. Turbine Building Ventilation Monitorf,
1 1
1,2,3 81.
(D12-RE-4561; D12-RE-4562; 312-RR-4548-2; D12-ER-4548-3)
\\
- 14. Off gas Stack Ventilation'Honitorf 1
1 1, 2, 3 81 i
(D12-RE-4573; D12-RE-4574;
]
D12-RR-4599-2; D12-RR-4599-3) s~
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1 i
e a
4 i High range noble gas monitors.
j k (a) An OPERABLE instrument channel sha11' consist of the AT instrument and ei,ther the AI instrument or the,
XY-XY-AR instrun.ents.
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i (b) See also specification 3.6.2.1 for ACTION requirements for the Suppression Pool Temperature Monitoring i
System Instrumentation.
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(BSEP-2-12/28)
TABLE 4.3.5.3-1 ACCIDENT HONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1
h'INSTRUMENTANDINSTRUMENTNUMBER CHANNEL CHANNEL Q
CHECK CALIBRATION 4
- 1. Reactor Vessel Pressure i
g (821-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B)
H R
HH~
- 2. Reactor Vessel Water. Level.
(B21-LITS-N026A,8; B21-LR-R615; B21-LI-R604A,B; N
H R
B21-LT-NO37; and B21-LTH-N037-1)
- 3. Suppression Chamber Water Level (CAC-LT-2601; CAC-LI-2601-1)
H R
(CAC-LT-2602; CAC-LR-26,02)
- 4. Suppression Chamber Water Temperature 4
(CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1)
H R
w)
(CAC-TE-4426-15 thru 26; CAC-TY-4426-2; CAC-TR-4426-2)
- 5. Suppression Chamber Atmosphere Temperature
, y (CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
H R
CAC-TR-4426-1(2); C91-P602)
- 6. Drywell Pressure (CAC-PI-4176;. CAC-PT-4176; CAC-PR-1257-1; innd CAC-PT-4175)
H R
- 7. Drywell Temperature (CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-1(2);
H
.R j
CAC-TR-4426-1(2); C91-P602) 1 1I
- 8. Drywell Radiation jE (CAC-AR-1260; CAC-AQH-1260-1,2,3; H
R CAC-AR-1261; CAC-AQil-1261-1,2,3;
] $
CAC-AR-1262; CAC-AQil-1262-1,2,3)
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s l5
- 9. Drywell Oxygen Concentration H
R (CAC-AT-4409-37; CAC-AI-4409-40; CAC-X-XY-4348-2; CAC-X-XY-4349-2; CAC-AR-4409-41) g j
(CAC-AT-4410-37; CAC-AI-4410-40; CAC-X-XY-4362-2;
}
- CAC-X-XY-4363-2; CAC-AR-4410-41) 1 e
(BSEP-2-28)
. s.
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION SYSTEMS SUPPRES'iION CHAMBER LIMITIM CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:
~
i 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.
Nav1=n= average temperature of 95'F during OPERATIONAL CONDITION 1 or 2, except that the==rimum 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 camperature instrumentation channels with a minimum of 11 operable RID 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:
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 <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 I
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 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:
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BRUNSWICK - UNIT 2 3/4 6-9 Amendment No. 103
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' CONTAINMENT SYSTEMS
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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 eh==her, stop all testing which adds heat to the suppression
- ~
1 chamber and 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 atI 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 />.
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 suppressica 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With one suppression chamber water temperature instrumentation c.
channel inoperable, restore the inoperable channel to OPERABLE status within 7 days or verify suppression chamber water temperature to be within che limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.
With both suppression chamber water temperature instrumentation i
channels inoperable, restore at least one inoperable temperature instrumentation channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-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 />.
With the drywell-to-suppression chamber bypass leakage in excess of e.
the limit, restore the bypass leakage to within the limit prior to increasing reactor coolant temperature above 212*F.
SURVEILLANCE REQUIREMENTS I
4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:
By verifying the suppression chamber water volume to be within the a.
limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l BRUNSWICK - UNIT 2 3/4 6-10 Amendment No.103 M+
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(BSEP-2-28)
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continund)
~
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber average water temperature to.be
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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 suppression chamber average vecer temperature is greater than 95'F, by verifying:
a)
Suppression chamber average water temperature to be lesa~
than or equal to 110*F, and b)
THFRMAL POWER to be less than or equal to 1% of RATED THERMAL. POWER after suppression chamber average water i
temperature has exceeded 95*7 for nore than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 lina 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 verifying at least two suppression chamber water temperature instrumentation channels *0PERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.
CHANNEL CALIBRATION.at least once per 18 months (550 days),
with the temperature alarm setpoint for high water temperature less than or equal to 95*F.
(CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1) (CAC-TE-4426-15 thru 26; CAC-IT-4426-2; CAC-TR-4426-2) 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.
e BRUNSWICK - UNIT 2 3/4 6-10a Amendment No.103 h.'
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(BSEP-2-28) 4 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
. Conducting. a drywell-to-suppression chamber bypass gleak test at
'y
, n"an initial -differencial pressure of I psig and verifying that the differential pressure doet not decrease by more than
'/
0.25 inches of water per minue,s for a 10 minute period.
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l BRUNSWICK - UNIT 2 3/4 6-10b
' Amendment No.1 3 0c
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(BSEP-2-28)
CONTAINMENT SYSTEMS i
374.6.4 VACUUM RELIEF DRYWELL - SUPPRESSION CHAMBER VACUUM BREAKER _S_
~
LIMITING CONDITION FOR OPERATION 3.6.4.1 All drywell-suppression chamber vacuum breakers shall be OPERABLE an
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d
- in the closed position with:
a.
The position indicator 0FERABLE, and b.
An opening setpoint of less than or equal to 0.5 psid.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With no more than 2 drywell-suppression chamber vacuum breakers a.
inoperable for opening but known to be in the closed position, the provisions of Specification 3.0.4 are not applicable and operation may continue until the next COLD SHUTDOWN provided the surveillance requirements of Specification 4.6.4.1.a are perfor:ned on the OPERABLE vacuum breakers within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 15 days thereaf ter until the inoperable vacuum breakers are restored to OPERABLE status.
b.
With one drywell-suppression chamber vacuum breaker in the open position, as indicated by the position indicating system, t,he provisions of Specification 3.0.4 are not applicable and opera, tion any continue provided the surveillance requirements of Specificacion 4.6.4.1.a are performed on the OPERABLE vacuum breakers and the surveillance requirements of Specificac1'on 4.6.4.1.b are performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter until the inoperable vacuum breaker is restored to the closed position.
With the position indicator of any drywell-suppression chamber vacuum c.
breaker inoperable, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided the surveillance requirements of Specification 4.6.4.1.b are performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter until the inoperable position indicator is returned to OPERABLE status.
d.
Otherwise, be in at least HOT SHUTDOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 BRUNSWICK - UNIT 2 3/4 6-18 Amendment No. 103
(BSEP-2-28)
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS 4.6.4.1 Each drywell-suppression chamber vacuum breaker st.all be demonstrated OPRRARf2:
a.
At least once per 31 days and after any discharge of steam to the suppression chamber from any source, by exercising each vacuum breaker through one complete cycle and verifying that each vacuum breaker is closed as indicated by the position indication system.
b.
Whenever a vacuum breaker is in the open position, as indicated by the position indication system, by conducting a test that verifies that the differential pressure is maintained greater than 1/2 the l
initial delta P for one hour without N2 makeup.
1 c.
At least once per 18 months during shutdown by:
1.
Verifying the opening setpoint, from the closed position, to be less than or equal to 0.5 psid, l
2.
Performance of a CHANNEL CALIBRATION that each position indicator indicates the vacuum breaker to be open if the vacuum breaker does not satisfy the delta P test in 4.6.4.1.b.
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BRUNSWICK - UNIT 2 3/4 6-19 Amendment No.103 s-
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(BSEP-2-28)
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.5.2 REMOTE SHUTDOWN HONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures
- that sufficient capability is available to permit shutdown and maintenance of BOT SHUTDOWN of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost,.and is consistent with General Design Criterion 19 of CFR 50.
3/4.3.5.3 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the post-accident monitoring instrumentation ensures-t that sufficient information is available on selected plant parameters to l
monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97,
" Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
The suppression chamber water temperature monitoring s.vstem 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 c:.P.arin of NUREG-0661, Appendix A in monitoring average suppression chamber water temperature during normal operating conditions.
Refer to Sections 3/4.3.5.3 and 3/4.6.2.1 for Limiting Conditions for Operation and Surveillance Requirements pertaining to each function.
l 3/4.3.5.4 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low power levels during start-up.
At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automctically isolate the control room and initiate operation in the recirculation mode to provide the required peotection. The detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."
BRUNSWICK - UNIT 2 3 3/4 3-3 Amendment No.103 4
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CONTAINMENT SYSTEM _S_
BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS The specifications of this section snsure that the primary containment pressure will not exceed the design pressure of 49 psig during primary system
. blowdown from full operating pressure.
Ine pressure shppression 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 mast absorb the associated decay and structural sensible heat released during primary system blowdown from 1020 Paig. Since all of the gases in the drywell are purged into the pressure suppression chamber air space during a loss of coolant accident, the pressure of the liquid mast not exceed 62 psig, the suppression 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 suppression chamber and that the drywell volume is purged to the suppression chamber.
Using the minimum or maximum water volumes given in the specification, containment pressure during the design basis accident is approximately 49 is below the design pressure of 62 psig. Maximum water volume of psig, whip gsults in a downcomer submergence of 3'4" and the minimu l
89,600 ft r of 87,600 ft results in a submergsnce approximately four inches less. The Monticello tests were run with a submerged length of three feet and with
'l complet.e condensation. Thus, with resoect to the downcomer submergence, this specification is adequate. The maximum temperature at the end of the blowdown 0
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 0
coolant, although condensation wo721d occur for t,emperatures 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, bicwdowit from an initial suppression chamber water temperature of 90 F results in a water temperature 0
of approximately 1350F immediately following blowdown, which is below the 2
temperature 170*F used for complete condensaticn. 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.
1 BRUNSWICK - UNIT 2 B 3/4 6-3 Amendment No.103 y
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(BSEP-2-28)
' CONTAINMENT SYSTEMS MSES "3/4.'6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued)
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erimental data indicate that excessive steam condensing loads can be w
l avoided if the peak temperature of the pressure suppression pool is maintained below 160'P duri'ng any period of relief valve operation with sonic conditions
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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 continually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that ippropriate 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 expect'ed to be the points of highest stress.
In addition to the limits on temperature of the suppression chamber pool
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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 t;be 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. Refer to Sections 3/4.3.5.3 ano 3/4.6.2.1 for Limiting Conditions for Operation and Surveillance Requirements pertaining to each function.
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
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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 i
assumptions used in the analyses for a LOCA.
BRUNSWICK - UNIT 2 B 3/4 6-4 Amendment No.103 4
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