ML20217P881

Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual

ML20217P881
Person / Time
Site:	Davis Besse
Issue date:	04/24/1998
From:	CENTERIOR ENERGY
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ML20217P851	List: ML20217P849 ML20217P867 ML20217P881
References
NUDOCS 9805070119
Download: ML20217P881 (16)

Text

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$" INFORMATION ONLY

. DEFINITIONS l

per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

STAGGERED TEST BASIS 1.21 A STAGGERED TEST BASIS shall consist of:

l a. A test schedule for n systems, subsystenis, trains or designated components cbtained by dividing the specified test interval into n equal subintervals,

b. The testing of one system, subsystem, train or designated )

components at the beginning of each subinterval. I FREQUENCY NOTATION l 1.22 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.  !

AXIAL POWER IMBALANCE 1.23 AXIAL POWER IMBALANCE shall be the THERMAL POWER in the top half l of the core expressed as a percentage of RATED THERMAL POWER minus the THERMAL POWER in the bottom half of the core expressed as a percentage of RATED THERMAL POWER.

EIELOBUILDINGINTEGRITY 1.24 SHIELD BUILDING INTEGRITY shall exist when:

a. The airtight doors and the blowout panels listed in Table 4.6-1 )

are closed except the airtight doors may be used for normal 1 transit entry and exit.

b. The emergency ventilation system is OPERABLE.

c. The sealing mechanism associated with each penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

REACTOR PROTECTION SYSTEM RESPONSE TIME 1.25 The REACTOR PROTECTION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until power interruption at the control rod drive breakers.

DAVIS-BESSE, UNIT 1 l-5 9805070119 900424 PDR ADOCK 05000346 P PDR 1

i LAR97-0004 i a- "

INFORMATION ONLY DEFINITIONS .

! SAFETY FEATURE RESPONSE TIME l

1.26 The SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its SFAS actuation setpoint at the channel sensor until the safety feature's equipment is capable of performing its safety l i

function (i.e., the valves travel to their required positions, pump discharge i pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

PHYSICS TESTS , 1.27 PHYSICS TESTS shall be those tests perfortned to measure the fundamental I

nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 14.0 of the FSAR, 2) authorized under the provision's of 10 CFR 50.59, or 3) otherwise approved by the Comission. -

STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME l

1.28 The STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its SFRCS actuation setpoint at the channel sensor until the equipment is capable of performing its safety function (i.e., the valves travel to their required  :

i positions, pump discharge pressures reach their required values, etc.).

1 l

DAVIS-BESSE.' UNIT 1 1-6 Amendment No.135

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LAR97'-0004 Page 12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the Reactor Protection System instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE, with RESPONSE TIMES as shown ic. Tab!c 3.3 2.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REOUIREMENTS 4.3.1.1.1 Each Reactor Protection System instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The total bypass function shall be demonstrated OPERABLE at least once per REFUELING INTERVAL during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME

• of each reactor trip ,

function shall be demonstrated to be within its limit at least once per REFUELING INTERVAL.

Naufron detectors are exemnt from resnonse time testine:Ae resoonse time of the neutron flux gignal nortion of the channel shall be measured from the neutron detector outout or from the inout of the first electronic comnonent in the channel. Each test shall include at least one channel per function such that all channels are tested at least once every N times the REFUELING INTERVAL where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

• The resnonse times include the sensor (excent for the neutron detectorst Reactor Protecjag System instrument delav. and the control rod drive breaker delav. A delay time has been assumed for theleactor Coolant Pumn monitor in the determination of the resoonse_ lime of the Hich Flux / Number of Reactor Coolant Pumos On functional unit, i

DAVIS-BESSE, UNIT 1 3/4 3-1 Amendment No. 218, 1

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l DAVIS-BESSE, UNIT 1 3/4 3-6 Amendment No. 45,148

. 9 LAR97-0004 + 4 Page 14 f INSTRUMENTATION 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Safety Features Actuation System (SFAS) functional units shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of

! Table 3.3-4, with the exception of Instrument Strings Functional Units d and e and Interlock Channels 1 Functional Unit a which shall be set consistent with the Allowable Value column of Table 3.3-4,, and vith RESPOMSE TIMES = dc= in Td!: 3.3 5.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With a SFAS functional unit trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the functional unit inoperable and apply the applicable ACTION requirement of Table 3.3-3, until the functional unit is restored to OPERABLE status with the trip setpoint adjusted consistent with Table 3.3-4.

b. .With a SFAS functional unit inoperable, take the action shown in Table 3.3-3.

SURVETI1ANCE REOUIREMENTS 4.3.2.1.1 Each SFAS functional unit shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shown in Table 4.3-2, 4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of functional units affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per REFUELING INTERVAL during CHANNEL CALIBRATION testing of each functional unit affected by bypass operation.

4.3.2.1.3 The SAFETY FEATURES RESPONSE TIME *, of each SFAS function shall be demonstrated to be within the limit at least once per REFUELING INTERVAL. Each test shall include at least one

' functional unit per function such that all functional units are tested at least once every N times the REFUELING INTERVAL where N is the total number of redundant functional units in a specific SFAS function as shown in the " Total No. of Units" Column of Table 3.3-3.

• The resoonse times (exceot for manual initiation) include diesel cenerator starline and seauence loadine delavs. when aoolicable. The resoonse timqjimit (excent for manual initiation) includes movement of valves and attainment of numn or blower discharce cressure.

DAVIS-BESSE, UNIT 1 3/43-9 Amendment No. 218,

i LAR97-0004 Page 15 TABLE 3.3-5 l l

l S AFETY FEATURES SYSTEM REPONSE TIMES I

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LAR97-0004 Page 22

. INSTRUMENTATION STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION LIMmNG CONDITION FOR OPERATION 3.3.2.2 The Steam and Feedwater Rupture Control System (SFRCS) instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-12, with the exception of the Steam Generator Level-Low Functional Unit which shall be set consistent with the Allowable Value column of Table 3.3-12, and with "ES"ONSE T4MES as shown in Tmbic 3.3-13.

APPLICABILITY: MODES 1,2 and 3.

ACTION:

a. With a SFRCS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-12, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3 11, until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with Table 3.3-12.

b. With a SFRCS instrumentation channel inoperable, take the action shown in Table 3.3-11.

SURVELLANCE REOUIREMENTS 4.3.2.2.1 Each SFRCS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shown in Table 4.3-11.

4.3.2.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per REFUELING INTERVAL during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.2.2.3 The STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMEl of each SFRCS function shall be demonstrated to be within the limit at least once per REFUELING INTERVAL. Each test shall include at least one channel per function such that all channels are tested at least once every N times the REFUELING INTERVAL where N is the total number of redundant channels in a specific SFRCS function as shown in the " Total No. of Channels" Column of Table 3.3-11.

• Ttte Main Steara Isolation Valves (MSIVs) reJprnelime is to_be the_ timer!;psed from the monitored variab e exceedine the trip seto_oint until the MSlV iL[ujjy_ closed. The Turbine Ston a

.V_aLvas (TSVs) rescosse time is to 3e the timeslapseltfrom the main sigamjitte low Dressuredrin condition until the TSV is fujlv close3L DAVIS-BESSE, UNIT 1 3/4 3-23 Amendment No. 218,

1 LAR97-0004 Page 23 T. uA. D. i n s . sT .> C u-

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Page 24

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3/4.3 INSTRUMENTATION EASES 3/k3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEM INSTRUMENTATION l The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systems ensure that 1) the associated action and/or trip will be initiated when the parameter moninted by each channel or combination thereof exceeds its setpoint,2) the specified coincidence logic is maintained,3) sufficient redundancy is  ;

maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system  !

functional capability is available for RPS, SFAS and SFRCS purposes from diverse parameters. I The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests l performed at the minimum frequencies are sufficient to demonstrate this capability. The response time limits for these instrumentation systems are located in the Updated Safety Analysis Report and are used to dgmonstrate OPERABILITY in accordance with each system's resnonsdime surveillance reauirements.

For the RPS, SFAS Table 3.3-4 Functional Unit Instrument Strings d and e and interlock Channel a, and SFRCS Table 3.3-12 Functional Unit 2:

Only the Allowable Value is specified for each Function. Nominal trip setpoints are specified in the setpoint analysis. The nominal trip setpoints are selected to ensure the setpoints measured by CHANNEL FUNCTIONAL TESTS do not exceed the Allowable Value if the bistable is perforrning as required. Operation with a trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value, is acceptable provided that operation and testing are consistent with the assumptions of the specific setpoint calmlations. Each Allowable Value specified is more conservative than the analyti cal limit assumed in the safety analysis to account for instrument uncertainties appropriate to the trip parameter. These uncertainties are defined in the specific setpoint analysis.

A CHANNEL FUNCTIONAL TEST is performed on ea6 required channel to ensure that the ,

entire channel will perform the intended function. Setpoucs must be found within the specified Allowable Values. Any setpoint adjustment shall be consistent with the assumptions ot'the current specific setpoint analysis.

A CHANNEL CALIBRATION is a complete check of the instmnent channel < including the sensor. The test verifies that the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drift to ensure that the instrument channel remains operational between successive tests. CHANNEL CALIBRATION shall find that measurement errors and bistable setpoint errors are within the assumptions of the setpcint analysis. CHANNEL CALIBRATIONS must be performed consistent with the assumptions 01 the setpoint analysis.

The frequency is justified by the assumption of an 18 or 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis. -

DAVIS-BESSE, UNIT 1 B 3/4 3-1 Amendment No. 73,125,128,211,218

( Next page is B3/4 3-la)

1 LAR97-0004 Page 25 3/4.3 INSTRUMENTATION BASES l

l 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEM INSTRUMENTATION (Continued)

L i The measurement of response time at the specified frequencies provides assurance that the RPS, SFAS, and SFRCS action function associated with each channel is completed within the time l limit assumed in the safety analyses. No credit v= : ken in $c analy=3 for $c= channch , i$

l repen= time; indica:cd = not applicek.

l Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or l offsite test measurements or 2) utilizing replacement sensors with certified response times.

! The actuation logic for Functional Units 4.a.,4.b., and 4.c. of Table 3.3-3, Safety Features Actuation System Instrumentation,is designed to provide protection and actuation of a single train of safety features equipment, essential bus or emergency diesel generator. Collectively, Functional Units 4.a.,4.b., and 4.c. function to detect a degraded voltage condition on either of the two 4160 volt essential buses, shed connected loads, disconnect the affected bus (es) from the offsite power source and start the associated emergency diesel generator. In addition, if an SFAS I actuation signal is present under these conditions, the sequencer channels for the two SFAS channels which actuate the train of safety features equipment powered by the affected bus will  !

automatically sequence these loads onto the bus to prevent overloading of the emergency diesel generator. Functional Unit 4.a. has a total of four units, one associated with each SFAS channel (i.e., two for each essential bus). ~ Functional Units 4.b. and 4.c. each have a total of four units, (two associated with each essential bus); each unit consisting of two undervoltage relays and an auxiliary relay.

An SFRCS channel consists of 1) the sensing device (s),2) associated logic and output relays 1 (including Isolation of Main Feedwater Non Essential Valves and Turbine Trip), and 3) power l_ sources.

i The SFRCS response time for the turbine stop valve closure is based on the combined response l times of main steam line low pressure sensors, logic cabinet delay for main steam line low

{

pressure signals and closure time of the turbine stop valves. This SFRCS response time ensures  !

that the auxiliary fee) water to the unaffected steam generator will not be isolated due to a SFRCS low pressure trip during a main steam line break accident.

Safety-grade anticipatory reactor trip is initiated by a turbine trip (above 45 percent of RATED THERMAL POWER) or trip of both main feedwater pump turbines. This anticipatory trip will operate in advance of the reactor coolant system high pressure reactor trip to reduce the peak reactor coolant system pressure and thus reduce challenges to the pilot operated relief valve.

This anticipatory reactor trip system was installed to satisfy Item U.K.2.10 of NUREG-0737.

Thejustification for the ARTS turbine trip arming level of 45% is given in B AW-1893, October, 1985.

DAVIS-bESSE, UNIT 1 B 3/4 3-ia Amendment No. 73,12f,128,135, 211,218