ML19305D959

Proposed Revisions to Tech Specs,Sections 1 & 3/4, Reflecting Changes Necessary to Begin Cycle 4 Operation

ML19305D959
Person / Time
Site:	Brunswick
Issue date:	04/11/1980
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML19305D958	List: ML19305D957 ML19305D959 ML19305D960
References
NUDOCS 8004170019
Download: ML19305D959 (17)

Text

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O INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS (Continued)

PHYSICS TEST 5..............................................

1-4 1-4 PRESSURE B0UNDARY LEAKAGE..................................

1-4 PRIMARY CONTAINMENT INTEGRITY.............................. "

1-5 RATED THERMAL P0WER........................................

1-5 REACTOR PROT'ECTION SYSTEM RESPONSE TIME.................... ~

RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME............... 1-5 l 1-5 REPO RT AB LE O CCURREN C E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

DENSITY..........................................'...... 1-5 R0D SECONDARY CONT AINMENT INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . . .

1-6, l SHUTDOWN MARGIN............................................

1-6 THERMAL POWEF .............................................

1-6 TOTAL PEAKING FACT 0R....................................... 1-6 UNIDENTIFIED LEAKAGE.......................................

1-6 FREQUENCY NOTATION, TABLE 1.1........................ ..... 1-7 OPERATIONAL CONDITIONS, TABLE 1.2.......................... 1-8 i

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTEC ION SYSTEM INSTRUMENTATION. . . . . . . . . . . . . . 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION. 3/4 3-30 3/4 3-39 3/4.3.4 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION. . . . . . . . . . .

3/4.3.5 MONITORING INSTRUMENTATION Sei smic Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . 3/4 3-44 Rem 6te Shutdown Monitoring Instrumentation.......... .. 3/4 3-47 Post-accident Monitoring Instrumentation.. ............ 3/4 3-50 Sou rce Range Moni tars . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-53 Chierine Detection System.............................. 3/4 3-54 Chloride Intrusion Monitors............................ 3/4 3-55 Fire Detection Instrumentation..................... ... 3/4 3-59 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation.... 3/4 3-62 .

End-of-Cycle Recirculation Pump Trip System Instrumentation...................................... 3/4 3-66 G/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.................................... 3/4 4-1 Je- Ou os.............................................. 3/4 4-2 ll Id s Racirculation Lecp S artu;:. . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-3

,b a.4.2 SAFETY / RELIEF VAL','ES................................... 3/4 4-4 l

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INDEX BASES PAGE SECTION 3/4.0 APPLICABILITY.......................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN bARGIN................................ B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES........................... B 3/4 1-1 3/4.1.3 CONTROL R0DS................................... B 3/4 1-1 3/4.1.4 CONTROL ROD PROGRAM CONTR0LS. . . . . . . . . . . . . . . . . . . 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 GENERATING RATE..... B 3/4 2-1 3/4.2.2 APRM SETP0!NTS................................. B 3/4 2-3 3/4.2.3 MINIMUM CRITICAL POWER kaT!0................... B 3/4 2-3 LINEAR HEAT GENERATION RATE.................... B 3/4 2-5 3/4.2.4 3/4.3 INSTRUMENTATION REACTOR PROTECTION SYSTEM INSTRUMENTATION. . . . . . B 3/4 3-1 3/4.3.1 ISOLATION ACTUATION INSTRUMENTATION............ B 3/4 3-2 3/4.3.2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION B 3/4 3-2

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INSTRUMENTATION.............................

B 3/4 3-2 3/4.3.4 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION...

MONITORING INSTRUMENTATION..................... B 3/4 3-2 3/4.3.5 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION B 3/4 3-4 I N ST RUMENT AT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. 3/4.4 REACTOR COOLANT SYSTEM

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ECIRCULATION SYSTEM.......... ......... ...... E 3/4 4-1 3/4.4.1 .

3/4.4.2 SAFETY / RELIEF VALVES...........................

B 3/4 4-1 RE ACTOR COOL ANT SYSTEM LE A KA3E . . . . . . . . . . . . . . . . . B 3/4 4-1

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CEFINITIONS -

FREOUENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveil-lance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.13 IDENTIFIED LEAKAGE shall be:

a. Leukage into collection systems, such as pump seal or vain packing leaks that is captured and conductt:d to a sump or ,

collectjngtank,or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with.the operation of the leakage detection systems or not be PRESSURE B0UNDARY LEAKAGE.

ISOLATION SYSTEM RESPONSE TIME 1.14 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its iolation actuation set-point at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays where applicable.

LIMITING CONTR'OL R0D PATTERN 1.15 A LIMITING CONTROL R0D PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limit-ing value for APLHGR, LHGR, or MCP: .

LINEAR HEAT GENERATION RATE l 1.16 LINEAR HEAT GENERATION RATE (LHGR) shall be the power generation in an arbitrary length of fuel rod, usually one foot. It is the integral of the heat flux over the heat transfer area associated with the unit length, usually measured in KW/ft.

LOGIC SYSTEM FUNCTIONAL TEST

't 1.17 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all relays and

,:centacts of a logic circuit, from sensor output thrcugh and including 4: 1 5::usticr. cevice, to ensure tha: components are OPER; ELE.

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..XI"A TOTAL FEAKII:G FACTOR t

'. . ; E The MA:C';M TOTAL PEAKING FACTOR (MTPF) shall be tne largest TPF which exists in the core for a given class of fuel for a given cperating condition.

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DEFINITIONS _

PRIMARY CONTAINMENT INTEGRITY (Continued),

1.24.2 All equipment hatches are closed and sealed.

1.24.3 Each containment air lock is OsERAE'.E pursuant to Speci-  :

fication 3.6.1.3.

1.24.4 The containment leakage rates are within the limits of Specification 3.6.1.2.

1.24.5. The sealing mechanism associated with each penetration ,

'(e.g., welds, bellows or 0-rings is) is OPERACLE.

RATED THERMAL POWER 1.25 R'ATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2436 MWT.

REACTOR PROTECTION SYSTEM RESPONSE TIME 1.26 REACTOR PROTECTION SYSTEM RESPONSE TIME shal'1 be the time intervai from when the monitored parameter exceeds i'- trip setpoint at the channel sensor until de-energization of the . ram pilot valve solenoi'ds.

RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME 1.27 The RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to recirculation pump breaker trip from initial movement of the associated:

a. Turbine stop valves and

b. Turbine control valves. g

~ .h REPORTABLE OCCURRENCE 1.28 A REPORTABLE OCCURRENCE shall be any of those conditions specified l in Specification 6.9.1.8 and 6.9.1.9.

ROD DENSITY 1.29 RCD DENSITY shall be the number of control rod notches inserted as l a fraction of the total number of notches. All rods fully inserted is c 100', ROD DENSITY.

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DEFINITI0*$

SECONDARY CONTAINMENT INTEGRITY 1.30 SECONDARY CONTAINMENT INTEGRITY shall exist when: l

a. All automatic reactor building ventilation system isolation l valves or dampers are OPERABLE or secured in the isolated position,

b. The standby gas treatment system is OPERAELE pursuant to j-Specification 3.6.6.1.

c. At least one door in each access to the reactor building is l closed,

d. The sealing mechanism associated with each penetration (e.g., l welds, bellows or 0-rings) is OPERABLE.

SHUTOOWN MARGIN 1.3l SHUTC0WN MARGIN shall be the amount of reactivity by which the l rear tor would be subrritical assuming that all control rods capable of insertion are fully inserted except for the analytically determined hig'ast worth rod wh'ch is assumed to be fully withdrawn, and the reactor is in the shtdown condition, cold, 68'F, and Xenon free.

STAGGERED TEST BASIS 1.32 A SAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals,

b. ,The testing of one system, sub system, train or other designated component at the beginning of each subinterval.

THERMAL POWER

1.33 THERMAL POWER shall be the total reactor core heat transfer rate l to the reactor coolant.

! TCT;L PEAK:'.~G FACTOR f l.2 ke :T;L PEAKING FACTOR (TPF) shall be the ratic of lccal LHGR l J #v U, 5:6:i#i: icca:icr. on a fval rc: divided by tre 3. era;e Lh2R

".'1 e: '~" The fuel bur.Cles of the la~e I;.?e Cpirating at I"e CCre lI si I.t 1;e b r::e ::.zer.

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. ::E'. :F:E: 'E;';GE i.3E UNICE*;TIFIED LEAKAGE shall be all isakage which is not IDENTIFIED l

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POWER DTSTRIBUTXON LXMITS 3 /4. 2. 3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.'2.3 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of core flow, shall be equal to or greater than MCPR times the K, shown in Ficure 3.2.3-1, provided that the end-of-cycle recirculation pump trip system is OPERABLE per Specification 3.3.6.2, with:

a. MCPR for 7x7 fuel = 1.21* -

b. MCPR for 8x8 fuel = 1.28 -

c. MCPR for 8x8R fuel = 1.21

d. MCPR for P8x8R fuel u 1.21 APPLICASILITY: CGNDITION 1, when THERMAL POWER g 25% RATED THERMAL POWER.

ACTION: I r

a. With the end-of-cycle recirculation pump trip system inoperable per Specification 3.3.6.2 operation may continue and the provisions of Specification 3.0.4 are not applicable with the following MCPR adjustments,

1. Beginning-of-cycle (BOC) to end-of-cycle (EOC) minus 2000  !

MWD /t, with no change in MCPR values from 3.2.3 above.

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2. EOC minus 2000 MWD /t to EOC minus 1000 MWD /t,within one hour determine that MCPR, as a function of core flow, is equal to er greater than MCPR times the Kg shown in Figure 3.2.3-1 with:

a. MCPR for 7x7 fuel = 1.21*

b. MCPR for 8x8 fuel = 1.28

c. MCPR for 8x8R fuel = 1.26, and

d. MCPR for P8x8R fuel = 1.28

3. EOC minus 1000 MWD /t to EOC, within one hour determine that MCPR, as a function of core flow, is equal to or greater than MCPR times the Kg shown in Figure 3.2.3-1 with: .

a. MCPR for 7x7 fuel = 1.28

b. MCPR for 8x8 fuel = 1.35

c. MCPR for 8x8R fuel = 1.34, and

d. MCPR for P8x8P. fuel = 1.36

.b. With MCPR, as a function of core flow, less than the applicable limit determined from Ficure 3.2.3-1, initiate corrective action

w. chin 15 minutes and restore MCPR to within the applicable limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER to less than 25% of RATED

' THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

BRUNSWICK-UNIT 2 3/4 2-10

SU.VETLLANCE REOUTREMENTS .

4.2.3 MCPR, as a function of core flow, shall be determined to be equal to or greater than the applicable limit determined from Figure 3.2.3-1:

a. 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. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROD PATTERN FOR MCPR.

• For 7x7 fuel assemblies the Kg factor is based on the 112% flow curve of Figure 3.2.3-1 rather than on the actual setpoint of 102.5%.

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INSTRUMENTATION 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation trip systems shown in Table 3.3.6.1-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY: CONDITION 1.

ACTION:

a. With an ATWS recirculation pump trip system instrumentation trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6.1-2, declare the trip system inoperable until the trip system is restored to OPEPAFLE status with its trip setroint adjusted consistent with the Trip Setpoint value.

b. Witt, the requirements for the Minimum Number of OPERABLE Trip Systems per Operating Pump not satisfied for cna Trip Function, restore the inoperable trip system to OPERABLE sta't us within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.6.1.1 Each ATWS recirculation pump trip system instrumentation trip system shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at

-he frecuences shown in Table d.3.6.1.1-1.

4.3.6.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated autc= Etic opera-tien of all channels shall be performed at least once cer 18 months.

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INSTRUMENTATION END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM-INSTRUMENTATION LIMITING CONDITION FOR OPERATION.

3.3.6.2 The end-of-cycle recirculation pump trip (E0C-RPT) system instrumentation channels shown in Table 3.3.6.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.2-2 and with the RECIoCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.6.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1 when THER' il POWER is greater than or equal to 30", of RATED THERMAL POWER.

ACTION:

a. With' an end-of-cycle recirculation pump trip system instrumenta-tion channel trip setpoint less conservative than the value shown in; the Allowable Values column of Table 3.3.6.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpo:nt adjusted consistent with the Trip Setpoint valee.

. b. With the num'er of OPERABLE channels oma less than required by the Minimum (.PERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.

c. With the number of OPERABLE channels two or more less than required by the Minimam OPERABLE Channels per Trip System requirement for one trip system and:

1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place -

both inoperable channels in the tripped condition within one hour.

2. If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system inoperable.

d. With one trip system inoperable, operation may continue; restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or take the ACTION required by Scecification 3.2.3.

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3. . ?. ::-h tri: sys:Er.s 'n::srable, res :rs at least One

' rip s,.s er c '5E .AELE sta .:s within ene P:.;r Or take the

.T:'": -e:uired by S:eci#icati:n 2.2.".

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INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.3.6.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHA!!NEL CALIBRATION operations at the frequencies shown in Table 4. 3. 6. 2.1 -1.

4.3.6.2.2. LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once pc- 18 months.

4.3.6.2.3 The RECIRCULATION PUMP TRIP SYSTEM REST 3NSE TIME of both trip systems shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least the 1,ogic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months.

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l TABLE 3.3.6.2-1 END-OF-CYCLE RECIRCul.ATION PUMP TRIP SYSTEM IllSTRUMENTATION MINIMUM i OPERABLECllANNE(j)

... TitlP lilflCTION PER TRIP SYSTEM

l. Inrhine Stop Valve - Closure 2(b)

(EHC-SVOS-1X, 2X, 3X, 4X) -

2. Turbine Control Valve - Fast Closure 2(b)

(EHC-PSL-1756, 1757, 1758, 1759)

' d 0 m t rip system may he placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance i

provided that the other trip system is OPERABLE.

Ih)These functions are bypassed when turbine first stage pressure is < (250) psig, equivalent to TilEltMAL POWER less than 30% of RATED TilERMAL POWER.

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TABLE'3.3.6.2'2 -

END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEtt SETPOINTS li ALLOWABLE TRIP liitlCTI0fl .

TRIP SETPOINT VALVE

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l. lurhine Stop Valve-Closure ~< 10% closed

~< 10% closed (EllC-SVOS-1X, 2X, 3X, 4X)

?. lurbine Control Valve-Fast Closure > 500 psig

> 500 psig (EliC-PSL-1756, 1757, 1758, 1759) .

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TAflLE 3.3.6.2-3 END-0F-CYCL.E RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIttE i.,

RESP 0flSE TlHE (Seconds)

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1. -Tur!>ine Stop Valve-Closure . -< (.175) .

(EllC-SVOS-lX, 2X, 3X, 4X) -

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2. lurhine Control Valve-Fast Closure **

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END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQtilREMENTS N,* ,

',' CilANNEL-FUNCTIONAL CllANNEL c.

TEST CALIBRATION 4

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'" Turbine Stop Valve-Closure M* R

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7. lurbine Control Valve-fast Closure M*

(EllC-PSL-17 56, 1757, 17 58, 1759)

• liic.liiting trip system-logic testing.

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THETRUMENTATf0N BASES MONITORING INSTRUMENTATION (Continued) 90 3/4.3.5.6 CHLORIDE INTRUSION MONITORS WI "

The chloride intrusion monitors provide adequate warning of any leakage in the condenser or hotwell so that actions can be taken to mitigate the consequences of such intrusion in the reactor coolant system. With only a minimum number of instr.:ments available increased sampling frequency provides adequate information for the same purpose.

3/4.3.5.7 FIRE DETECTION INSTRUMENTATION OPE? ABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire oatrols in the affected areas is required to provide detection capabilit. .until the inoperable instrumentation is restored to OPERASILITY.

3/4.3.6 :ECIRCULATIO" PUMP TRIP SYSTEM INSTRU"ENTATION The anticipated transient without scram (ATWS) recirculation pump l trip system has been added at the suggestion of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within an envelope of study events given in General Electric Company Topical Report NED0-10349, dated March,1971.

The end-of-cycle recirculation pump trip (EOC-RPT) system is a part of the Reactor Protection System and is a safety supolement to the reactor trip. The purpose of the E0C-RPT is to recever the loss of thermal margin which occurs at the end-of-cycle.

The chysical chenomenon involved is tha- the void reactivity feedback due c a pressurization transient can add positive reactivity to the

"+100:r sys s at a faster rate than the control rods add neaative Eacn EOC :.PT sys em rips both recirculation pumps,

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scri , reactivity.

reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The two events for which the EOC-RPT protective feature will function are i

BRUNSWICK-Unit 2 B 3/4 3-4 1

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• INSTRUMENTATION BASES RECIRCULATION PUP.P TRIP INSTRUMENTATION (Continued) closure of the turbine stop valves and fast closure of the turbine control valves.

A fast closure sensor from each of two turbine' control valves provides input to one E0C-RPT system; a fast closure sensor from each of the other two turbine contr.ol valves provides input to the second EOC-RPT system. -

similarly, a posi-tion switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch for each of the other two turbine stop valves provides input to the other E0C-RPT system. For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for closure of the turbine stop valves. The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled. The manual bypasses and the automatic operating bypass at < 30% of RATED THERMAL POWER r e annunciated in the control room.

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