ML20136E784

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Proposed Tech Specs Incorporating New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation
ML20136E784
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/05/1997
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20136E783 List:
References
NUDOCS 9703130326
Download: ML20136E784 (22)
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... ..a ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 i NRC DOCKET NOS. 50-325 AND 50-324 l OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT CONDENSER VACUUM PUMP ISOLATION PAGE CHANGE INSTRUCTIONS UNIT 1 Removed page Inserted page V V -l 1

X X j 3/4 3-97 3/4 3-98 B 3/4 3-6 B 3/4 3-6 thru B 3/4 3-10 PAGE CHANGE INSTRUCTIONS UNIT 2 Removed page Inserted page V V X X 3/4 3-104 3/4 3-105 B 3/4 3-7 B 3/4 3-7 thru B 3/4 3-11 E 4-1 9703130326 970305 PDR ADOCK 05000324 P pon

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l ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 l NRC DOCKET NOS,50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT CONDENSER VACUUM PUMP ISOLATION 1

l TYPED TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 1 l

l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PA_GE

, 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ ... 3/4 3-1 4

3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..... ..... .. . .. .. 3/4 3-10 4

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.... 3/4 3-33 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION..... ....... 3/4 3-47 3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumentation..... .. ... .. . 3/4 3-53 Remote Shutdown Monitoring Instrumentation. . ....... .... 3/4 3-56 Accident Monitoring Instrumentation. ....... . ..... .. . 3/4 3-59 Source Range Monitors.. . ... .. ............ .. .. . 3/4 3-63 Control Room Emergency Ventilation System.. . . ..... .... 3/4 3-64

Chloride Intrusion Monitors.. . .. . ... . ..... . .. 3/4 3-65 Fire Detection Instrumentation (Deleted). .. . . . .. ..... 3/4 3-69 Radioactive Liquid Effluent Monitoring Instrumentation. . . . . 3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation.... 3/4 3-78 3/4.3.6 ATWS RECIRCULATION PUMP TRIP (RPT) SYSTEM INSTRUMENTATION.. 3/4 3-88 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION. . . .. .... . .. ..... .............. 3/4 3-92 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION... . ..... 3/4/3-97 1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.. .... ... .. . .. ... .. .......... 3/4 4-1 Jet Pumps...... ..... ..... ............... ...... 3/4 4-2 Idle Recirculation Loop Start-up..... . .... ......... .. 3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES. ....... . . .............. .. . 3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.. ...... ....... .. .... ... 3/4 4-5 Operational Leakage. . ..... . ..... .... ......... .. 3/4 4-6 BRUNSWICK - UNIT 1 V Amendment No.

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1 INDEX  !

4 BASES i

SECTION
I PKd 3/4.0 APPLICABILITY................... ..... .. ............... B 3/4 0-1 I l' -3/4.1 REACTIVITY CONTROL SYSTEMS '

3 7 3/4.1.1 SHUTDOWN MARGIN......... ................................ B 3/4 1-1 3/4.1.2 REACTIVITY ANOMALIES.......... . . . .................... B'3/4 1 ! 3/4.1.3 CONTROL R005....................................... ..... B 3/4 1-1

[ 3/4.1.4. CONTROL R00 PROGRAM CONTROLS.... ... ........ .......... B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM. .. ....................... B 3/4 1-4

[ 3/4.2 POWER DISTRIBUTION LIMITS f

3/4.2.1' AVERAGE PLANAR LINEAR HEAT GENERATION RATE............. . B 3/4 2 I 1

3/4.2.2 MINIMUM CRITICAL POWER RATI0................... ... ..... B 3/4 2-2 1 l

3/4.3 INSTRUMENTATION l 1

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.... ......... B 3/4'3-1 ]

3/4.3'2 ISOLATION ACTUATION INSTRUMENTATION.......

........... B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.. B 3/4 3-2

~3/4.3.4 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION......... ... B 3/4 3-2 3/4.3.5 MONITORING INSTRUMENTATION...... ....................... B 3/4 3-2 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION...... B 3/4 3-6 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION......... ... ....................... B 3/4 3-6 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION.......... B 3/4 3-6 1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.......... .......................... B 3/4 4-1. i 3/4.4.2 -SAFETY / RELIEF VALVES...... .............................. B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE........ . .. ..... . .... B 3/4 4-1 BRUNSWICK - UNIT 1 X Amendment No.

INSTRUMENTATION 2

3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 Four channels of the Main Steam Line Radiation-High Function for the condenser vacuum Jump isolation shall be OPERABLE with its trip setting set consistent with t1e required Allowable Value.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 with a condenser vacuum pump in service.

ACTION:

a. With one or more channel (s) of the Main Steam Line Radiation-High Function for condenser vacuum pump isolation inoperable:
1. Restore channel to OPERABLE status within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or

) *2. Place channel or associated trip system in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Otherwise; isolate the condenser vacuum pumps, or isolate the main steam lines, or be in 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 />,

b. With condenser vacuum pump isolation capability not maintained:
1. Isolate the condenser vacuum pumps within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or
2. Isolate the main steam lines within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or
3. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c. When a channel is placed in an inoperable status solely for the performance of required Surveillances, entry into associated Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided condenser vacuum pump isolation capability is maintained.
  • Not applicable if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve.

BRUNSWICK - UNIT 1 3/4 3-97 Amendment No. 1

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INSTRUMENTATION 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.8 Each channel of the Main Steam Line Radiation-High Function for condenser vacuum pump isolation shall be demonstrated OPERABLE by:

a. Performance of a 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 />;
b. Performance of a CHANNEL FUNCTIONAL TEST at least once per 92 days:
c. Performance of a CHANNEL CALIBRATION at least once per 18 months, the Allowable Value shall be s 6 x background; and
d. Performance of a LOGIC SYSTEM FUNCTIONAL TEST, including condenser vacuum pump trip breaker and isolation valve actuation, at least once per 18 months.

BRUNSWICK - UNIT 1 3/4 3-98 Amendment No. I

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INSTRUMENTATION BASES 3/4.3.6 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The ATWS recirculation pump trip system has been added at the suggestion of ACRS as a means of limiting the consecuences of the unlikely occurrence.of a failure to scram during an anticipatec transient. The response of the plant to this postulated event falls within the envelope of study events'given in General Electric Company Tropical Report NED0-10349, dated March, 1971.

Specified surveillance intervals and allowed out-of-service times were  !

established based on the reliability analyses documented in GE report l GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed

- Out-of-Service Times for Selected Instrumentation Technical Specifications "

December 1992.

3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is

,provided to initiate actions to assure. adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Specified surveillance intervals and oilowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A, " Bases for Cha1ges to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," December 1992.

, 3/4.3.8 CONDENSER' VACUUM PUMP ISOLATION INSTRUMENTATION i

Backarocnd i The condenser vacuum pump isolation instrumentation initiates a trip of the

! respective condenser vacuum pump and the common isolation valve following events in which the main steam line radiation monitor (s) exceed a predetermined value. The condenser vacuum pump isolation instrumentation initiates an isolation of the condenser vacuum pump (s) to limit main control room doses resulting from fuel cladding failure in the event of a control rod  !

drop accident (CRDA). The isolation logic consists of two inde)endent trip systems, with two channels of the Main Steam Line Radiation-Higi Function in each trip system. Each trip system is a one-out-of-two logic for this Function. Thus, either channel of the Main Steam Line Radiation-High Function in each trip system are needed to tri) a tri) system. The outputs of the-channels are arranged in a logic so tlat bot 1 trip systems must trip to result in'an isolation signal.

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

,. I INSTRUMENTATION l l

l BASES ~

1 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued) i c

3 i The OPERABILITY.of the condenser vacuum pump isolation is dependent on the OPERABILITY of the individual Main Steam Line Radiation-High Function

! instrument channels, which must have its setpoint within the specified 2

Allowable Value of Surveillance Requirement 4.3.8.c. The actual setpoint is calibrated consistent with applicable setpoint methodology assumptions.

Channel DPERABILITY also includes the condenser vacuum pump trip breaker and isolation valve.

1.

2 Aoolicability

. The condenser vacuum pump isolation is required to be OPERABLE in OPERATIONAL j

CONDITIONS 1 and 2 when a condenser vacuum pump is in service, to mitigate the j consequences of a postulated control rod drop accident. In this condition.

i fission products released during a control rod drop accident could be discharged directly to the environment. Therefore, the condenser vacuum pump isolation is necessary to assure conformance with the radiological evaluation of the control rod drop accident. In OPERATIONAL CONDITIONS 3, 4, or 5, the

. consequences of a control rod drop are insignificant and are not expected to result in any fuel damage or fission product releases. When a condenser vacuum pump is not in operation in OPERATIONAL CONDITIONS 1 or 2. fission-product releases via this pathway would not occur.

-ACTION a.

With one or more channels inoperable, but with condenser vacuum pump isolation capability maintained (refer to ACTION b. Bases), the condenser vacuum pump isolation instrumentation is capable of performing the intended function.

However, the reliability and redundancy of the condenser vacuum pump-isolation instrumentation is reduced, such that a single failure in one of the remaining--

channels could result in the inability of the condenser vacuum pump isolation

. instrumentation to perform the intended function. Therefore, only a limited time is allowed to restore the inoperable channels to OPERABLE status.

Because of the low probability of extensive numbers of inoperabilities affecting multiple channels, and the low probability of an event requiring the initiation of condenser vacuum pump isolation,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> has been shown to be acceptable (Ref.1) to permit restoration of any inoperable channel to OPERABLE status (ACTION a.1). Alternately, the inoperable channel, or associated trip system may be ) laced in trip (ACTION a.2), since this would conservatively compensate for tle inoperability, restore capability to accommodate a single failure, and allow operation to continue. As noted, placing the channel in trip with no further restrictions is not allowed if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or ' isolation valve, since this may not adequately compensate for the BRUNSWICK'- UNIT 1 B 3/4 3-7 Amendment No. I

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INSTRUMENTATION BASES 4

3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION e ACTION a. (continued) inoperable condenser vacuum pump trip breaker or isolation valve (e.g., the trip breaker may be inoperable such that it will'not trip). If it is not

desired to place the channel in trip (e.g., as in the case where placing the f inoperable channel would result in loss of condenser vacuum), or if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve, the plant must be brought to an operating 2

condition in which the Limiting Condition for Operation does not apply. To achieve this status, the plant must be brought to at least OPERATIONAL i CONDITION 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Alternately, the associated condenser vacuum j pump (s) may be removed from service since this performs the intended function i of the instrumentation. An additional option is provided to isolate the main steam lines, which may allow operation to continue. Isolating the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This isolation is accomplished by i 1 solation of all main steam lines and main steam line drains which bypass the

[. main steam isolation valves.

The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating j- experience. to reach OPERATIONAL CONDITION 3 from full x)wer conditions, or to remove the condenser pump from service, or to isolate t1e main steam lines, in an orderly manner and without challenging plant systems.

ACTION b.

, ACTION b. is intended to ensure appropriate actions are taken if multiple, i inoperable, untripped channels result in the Function not maintaining i condenser vacuum pump isolation capability. The Function is considered to be

maintaining condenser vacuum pump isolation capability when _ sufficient channels are OPERABLE or in trip such that the condenser vacuum aump isolation

, instruments will generate a trip signal from a valid Main Steam ine i Radiation-High signal, and the condenser vacuum pumps will trip. This

! requires one channel of the function in each trip system to be OPERABLE or in trip and the condenser vacuum pump trip breakers to be OPERABLE. With 4: condenser vacuum pump isolation capability not maintained, the unit must be brought to an operating condition in which the Limiting Condition for 4

Operation does not apply. Therefore, to achieve this, the unit must be placed in OPERATIONAL CONDITION 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (ACTION b.3). Alternatively, the

! condenser vacuum pump can be removed from service since this performs the j' intended function of the instrumentation (ACTION b.1). An additional option

is provided to isolate the main steam lines (ACTION b.2). Isolation of the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This isolation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

An allowed completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach OPERATIONAL CONDITION 3 from full )ower conditions, or to remove the condenser pump from service, or to isolate t1e main steam lines, in an orderly manner and without challenging plant systems.

-BRUNSWICK - UNIT 1. B 3/4 3-8 Amendment No, l 4

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INSTRUMENTATION BASES 3/4.3.8' CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued)

ACTION c.

ACTION c. allows that when a channel is placed in an inoperable status solely for )erformance of required Surveillances. entry into the associated Actions may 3e delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains condenser vacuum pump isolation trip capability. Upon com)letion of the

, Surveillance, or expiration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance. the clannel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the reliability analysis (Ref. 1) assumption of the average time required to perform channel Surveillance. That i . analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the condenser vacuum pumps will isolate when i- necessary.

Surveillance Reauirement 4.3.8.a Performance of the CHANNEL CHECK once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensures that a gross failure of instrumentation has not occurred. A. CHANNEL CHECK will detect gross channel failure; thus it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Surveillance Reauirement 4.3.8.b A CHANNEL FUNCTIONAL TEST is performed to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day frequency is based on the reliability analysis of Reference 1.

. Surveillance Reauirement 4.3.8.c i A CHANNEL CALIBRATION is a complete check of the instrument loop and the

! sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The 18 month frequency is conservative with respect to the assumption of the calibration interval in the determination of the magnitude of equipment drift

in the setpoint analysis.

For the purposes of this surveillance. background is the dose level experienced at 100% rated thermal power with hydrogen water chemistry at the i maximum injection rate. Under these conditions, an Allowable Value of 6 x background will ensure that General Design Criterion 19 limits will not be i exceeded in the control room in the event of a control rod drop accident.

1 BRUNSWICK - UNIT 1 B 3/4 3-9 Amendment No. I

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INSTRUMENTATION-BASES' 3/4.3.8- CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued)

Surveillance Recuirement 4.3.8.0 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the pump trip breakers and actuation of the associated isolation valve are' included as part of this-Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to 3rovide complete testing of the assumed safety. function. Therefore, if a areaker is incapable of operating or isolation valves incapable of actuating,

-the instrument channel would be inoperable.

The 18 month frequency is based on the need to perform this Surveillance under

.the conditions that apply during a plant outage and the potential for'an 6nplanned transient if the surveillance were performed with the reactor at

' power.

Reference

1. NEDC-30851P-A Supplement 2. Technical Specifications Improvement Analysis for BWR-Isolation Instrumentation Common to RPS and ECCS Instrumentation, March 1989.

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-BRUNSWICK - UNIT 1 B 3/4 3-10 Amendment No. I 1

4 4 5 4 4.IJ 4-. 4 4 m ' 4W.- 4m 4 .J.-d b A. a s = e is ,En 4

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 j OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENT CONDENSER VACUUM PUMP ISOLATION l

i )

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i t

l 1

l TYPED TECHNICAL SPECIFICATION AND BASES PAGES - UNIT 2 "I

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t. ,E' INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.... ........ 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION. . . ..... . . . 3/4 3-10 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION., 3/4 3-33 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.. .. 3/4 3-47 3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumentation.. .. . .. . . 3/4 3-53 Remote Shutdown Monitoring Instrumentation. ..... . . 3/4 3-56 Accident Monitoring Instrumentation.. .. .. . . 3/4 3-59 Source Range Monitors. .. ... . . . .. 3/4 3-63 Control Room Emergency Ventilation System. . . . 3/4 3-64 Chloride Intrusion Monitors. . . . .. .. . .. 3/4 3-65 Fire Detection Instrumentation (Deleted). . . . .. 3/4 3-69 Radioactive Liquid Effluent Monitoring Instrumentation. . 3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-78 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip (RPT) System Instrumentation. 3/4 3-88 End-of-Cycle Recirculation Pump Trip System Instrunentation. . . . . . .. . . ... . .. . 3/4 3-93 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION
INSTRUMENTATION. .. . . . .. . . . .. 3/4 3-99 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION.. 3/4 3-104 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops. .. .... ..... . . .. .. . 3/4 4-1 Jet Pumps.. .. . . ... . .. . . ... 3/4 4-2 4

Idle Recirculation Loop Start-up. .... . . 3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES. .. . . . .... . 3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems. . . . ... ... .. .. . 3/4 4-5 Operational Leakage... ... ........ . ... . ... 3/4 4-6 BRUNSWICK - UNIT 2 V Amendment No.

i INDEX BASES l SECTION PAGE 3/4.0 APPLICABILITY...... . ... .. . . .. ... ... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN. . .. .. . .. ....... ......... B 3/4 1-1 3/4.1.2 REACTIVITY ANOMALIES.. .. .. .. .. . ..... .. B 3/4 1-1 3/4.1.3 CONTROL RODS. ... . .. .... .. . . .. ...... .... . B 3/4 1-1 3/4.1.4 CONTROL ROD PROGRAM CONTROLS. .. .. .. ... B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM.. .. .. .. . ... . B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE... . ... B 3/4 2-1 3/4.2.2 MINIMUM CRITICAL POWER RATIO..... . . ..... . . B 3/4 2-E 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATICN, . . . B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.. . .. .. .. B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION. B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION........... . B 3/4 3-2 3/4.3.5 MONITORING INSTRUMENTATION. . ... . . .... B 3/4 3-2 3/4.3.6 RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION... . .. B 3/4 3-6 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION

, INSTRUMENTATION. .... . .... .. ....... B 3/4 3-7 i 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION. . .

B 3/4 3-7 1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM. .. . . . ... . .. B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES. .. .. .. .. .... B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE.... . .. ... ..... B 3/4 4-1 BRUNSWICK - UNIT 2 X Amendment No.

INSTRUMENTATION 3/4 3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.8 Four channels of the. Main Steam Line Radiation-High Function for the condenser vacuum aump isolation shall be OPERABLE with its trip setting set consistent with tle required Allowable Value.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 with a condenser vacuum pump in service.

ACTION:

l

a. With one or more channel (s) of the Main Steam Line Radiation-High Function for condenser vacuum pump isolation inoperable:
1. Restore channel to OPERABLE status within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or
  • 2. Place channel or associated trip system in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Otherwise; isolate the condenser vacuum pumps, or isolate the main steam lines, or be in 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 />.

b. With condenser vacuum pump isolation capability not maintained:
1. Isolate the condenser vacuum pumps within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or

! 2. Isolate the main steam lines within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s: or

3. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l c. When a channel is placed in an inoperable status solely for the performance of required Surveillances, entry into associated Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided condenser vacuum pump isolation capability is maintained.

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  • Not applicable if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve.

BRUNSWICK - UNIT 2 3/4 3-104 Amendment No. l

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INSTRUMENTATION 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1

4.3.8 Each channel of the Main Steam Line Radiation-High Function for condenser vacuum pump isolation shall be demonstrated OPERABLE by:

a. Performance of a CHANNEL CHECK at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
j. b. Performance of a CHANNEL FUNCTIONAL TEST at least once per 92 days:
c. Performance of a CHANNEL CALIBRATION at least once per 18 months, I i the Allowable Value shall be s 6 x background; and
d. Performance of a LOGIC SYSTEM FUNCTIONAL TEST, including condenser vacuum pump trip breaker and isolation valve actuation, at least once per 18 months.

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BRUNSWICK - UNIT 2 3/4 3-105 Amendment No. l y , -

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LNSTRUMENTATION BASES 3/4.3.6 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The ATWS recirculation pump trip system has been added at the suggestion of ACRS as a means of limiting the consecuences of the unlikely occurrence of a failure to scram during an anticipatec transient. The response of the plant to this Jostulated event falls within the envelope of study events given in General Electric Company Tropical Report NED0-10349, dated March, 1971.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-1-A " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications "

December 1992.

I E4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to i the reactor vessel without providing actuation of any of the emergency core 1

cooling equipment.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A, " Bases for Changes to Surveillance Test Intervals and

  1. . Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," December 1992.

1 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION Backaround i

The condenser vacuum pump isolation instrumentation initiates a trip of the respective condenser vacuum pump and the common isolation valve following

, events in which the main steam line radiation monitor (s) exceed a predetermined vake. The condenser vacuum pump isolation instrumentation initiates an isolation of the condenser vacuum pump (s) to limit main control room doses resultina from fuel cladding failure in the event of a control rod drop accident (CRDA). The isolation logic consists of two independent trip systems, with two channels of the Main Steam Line Radiation-High Function in each trip system. Each trip system is a one-out-of-two logic for this Function. Thus, either channel of the Main Steam Line Radiation-High Function in each trip system are needed to tri) a tri) system. The outputs of the

, channels are arranged in a logic so tlat bot 1 trip systems must trip to result in an isolation signal.

't BRUNSWICK - UNIT 2 B 3/4 3-7 Amendment No. l

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INSTRUMENTATION BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued)

LC0 The OPERABILITY of the condenser vacuum pump isolation is dependent on the OPERABILITY of the individual Main Steam Line Radiation-High Function instrument channels, which must have its setpoint within the specified Allowable Value of Surveillance Requirement 4.3.8.c. The actual setpoint is calibrated consistent with applicable setpoint methodology assumptions.

Channel OPERABILITY also includes the condenser vacuum pump trip breaker and isolation valve.

Anolicability The condenser vacuum pump isolation is required to be OPERABLE in OPERATIONAL CONDITIONS 1 and 2 when a condenser vacuum pump is in service, to mitigate the consequences of a postulated control rod drop accident. In this condition, fission products released during a control rod drop accident could be discharged directly to the environment. Therefore, the condenser vacuum pump isolation is necessary to assure conformance with the radiological evaluation of the control rod drop accident. In OPERATIONAL CONDITIONS 3, 4, or 5, the consequences of a control rod drop are insignificant and are not expected to result in any fuel damage or fission 3roduct releases. When vacuum pump 1s not in operation in OPERATIONAL CONDITIONS 1 o.a condenserr 2, fission product releases via this pathway would not occur.

ACTION a.

With one or more channels inoperable, but with condenser vacuum pump isolation i capability maintained (refer to ACTION b. Bases), the condenser vacuum pump isolation instrumentation is capable of performing the intended function.

However, the reliability and redundancy of the condenser vacuum pump isolation instrumentation is reduced, such that a single failure in one of the remaining channels could result in the inability of the condenser vacuum pump isolation instrumentation to perform the intended function. Therefore, only a limited time is allowed to restore the inoperable channels to OPERABLE status, Because of the low probabilit affecting multiple channels, y of extensive numbers of inoperabilitiesand the low proba initiation of condenser vacuum pump isolation, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> has been shown to be acceptable (Ref.1) to permit restoration of any inoperable channel to OPERABLE status (ACTION a.1). Alternately, the ino3erable channel, or associated trip system, may be 3 laced in trip (ACTI)N a.2)_ since this would consc qatively comoensate for t1e inoperability, restore capability to >

accomodate a single failure, and allow operation to continue. As noted, I placing the channel in trip with no further restrictions is not allowed if the '

inoperable channel is the result of an inoperable condenser vacuum pump trip 1 breaker or isolation valve, since this may not adequately compensate for the l

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BRUNSWICK - UNIT 2 B 3/4 3-8 Amendment No. I

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INSTRUMENTATION BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION ACTION a. (continued) inoperable condenser vacuum pump trip breaker or isolation valve (e.g., the trip breaker may be inoperable such that it will not trip). If it is not desired to place the channel in trip (e.g., as in the case where placing the inoperable channel would result in loss of condenser vacuum), or if the inoperable channel is the result of an inoperable condenser vacuum pump trip breaker or isolation valve, the plant must be brought to an operatin condition in which the Limiting Condition for Operation does not app . To achieve this status the plant must be brought to at least OPERATION CONDITION 3within12 hours. Alternately, the associated condenser vacuum pump (s) may be removed from service since this performs the intended function of the instrumentation. An additional option is provided to isolate the main steam lines, which may allow operation to continue. Isolating the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This 1 solation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operatin experience, to reach OPERATIONAL CONDITION 3 from full ]ower conditions,gor to remove the condenser pump from service, or to isolate t1e main steam lines, in an orderly manner and without challenging plant systems.

ACTION b.

ACTION b. is intended to ensure appropriate actions are taken if multiple, inoperable, untripped channels result in the Function not maintaining condenser vacuum pump isolation capability. The Function is considered to be maintaining condenser vacuum pump 1 solation capability when sufficient channels are OPERABLE or in trip such that the condenser vacuum Jump isolation instruments will generate a trip signal from a valid Main Steam _ine Radiation-High signal, and the condenser vacuum pumps will trip. This requires one channel of the function in each trip system to be OPERABLE or in trip and the condenser vacuum pump trio breakers to be OPERABLE. With condenser vacuum pump isolation capability not maintained, the unit must be brought to an operatin condition in which the Limiting Condition for Operation does not app y. Therefore, to achieve this, the unit must be placed in OPERATIONAL CONDITI N 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (ACTION b.3). Alternatively, the condenser vacuumofpump intended function t (he instrumentation (ACTIONAn b.1).s) can be additional removed from se option is provided to isolate the main steam lines (ACTION b.2). Isolation of the main steam lines effectively provides an equivalent level of protection by precluding fission product transport to the condenser. This 1 solation is accomplished by isolation of all main steam lines and main steam line drains which bypass the main steam isolation valves.

An allowed completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable based on operating experience, to reach OPERATIONAL CONDITION 3 from full ]ower conditions, or to remove the condenser pump from service, or to isolate tie main steam lines, in an orderly manner and without challenging plant systems.

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

a. O INSTRUMENTATION BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued)

-ACTION c.

ACTION c. allows that when a channel is placed in an inoperable status solely for ]erformance of required Surveillances, entry into the associated Actions may 3e delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains condenser vacuum pump isolation trip capability. Upon completion of the Surveillance, or exu ration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance, the channel must be returnedtaken.

Actions to OPERABLE This Notestatus or the is based on applicable Condition the reliability analysisentered (Ref. 1and Req)uired assumption of the average time required to perform channel Surveillance. That analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the condenser vacuum pumps will isolate when necessary.

Surveillance Reauirement 4.3.8.a Performance of the CHANNEL CHECK once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK will detect gross channel failure; thus it is key to verifying the instrumentation continuestooperateproperlybetweeneachCHANNELCALIBRATION.

Surveillance Reauirement 4.3.8.b A CHANNEL FUNCTIONAL TEST is performed to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day frequency is based on the reliability analysis of Reference 1.

Surveillance Reauirement 4.3.8.c A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology. The 18 month frequency is conservative with respect to the assumption of the calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

For the purposes of this surveillance, background is the dose level experienced at 100% rated thermal power with hydrogen water chemistry at the maximum injection rate Under these conditions, an Allowable Value of 6 x background will ensure that General Design Criterion 19 limits will not be exceeded in the control room in the event of a control rod drop accident.

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I BRUNSWICK - UNIT 2 B 3/4 3-10 Amendment No. I L

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INSTRUMENTATION BASES 3/4.3.8 CONDENSER VACUUM PUMP ISOLATION INSTRUMENTATION (continued)

Surveillance Reauirement 4.3.8.d The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the pump trip breakers and actuation of the associated isolation valve are included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to

]rovide complete testing of the assumed safety function. Therefore, if a 3reaker is incapable of operating or isolation valves incapable of actuating, the instrument channel would be inoperable.

The 18 month frequency is based on the need to perform this Surveillance under the conditions that apply during.a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power.

Reference

1. NEDC-30851P-A Supplement 2. Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation, March 1989.

BRUNSWICK - UNIT 2 B 3/4 3-11 Amendment No. l

l ENCLOSURE 7 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 AMENDMENT CONDENSER VACUUM PUMP TRIP ! SOLATION CALCULATION OVA-0106 CONTROL ROOM AND OFFSITE DOSES DUE TO A ROD DROP ACCIDENT

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