Text

Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation
	ML17353A280
Person / Time
Site:	Turkey Point
Issue date:	07/26/1995
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17353A278	List: L-95-181, Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2; ML17353A280;
References
	NUDOCS 9507310236
	Download: ML17353A280 (22)
	v • d • e

~ ~I~

TABLE 3.3-1 (Continued TABLE NOTATION

When the Reactor. Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

"*When the Reactor Trip System breakers are in the open position, one or both of the backup HIS instrumentation channels may be used to satisfy this require-ment.

For backup NIS testing requirements, see Specification 3/4.3.3.3, ACCIDENT MONITORING.

"*"Reactor Coolant Pump breaker A is tripped by underfrequency sensor UF-3Al (UF-4Al) or UF-3B1(UF-4B1).

Reactor Coolant Pump breakers B and C are tripped by underfrequency sensor UF-3A2(UF-4A2) or UF-3B2(UF-4B2).

¹Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

¹¹Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

ACTION STATEMEHTS

'ACTION 1 -'With the number of OPERABLE channels one less than 'the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels one less, than the Total Humber of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a i b.

The inoperable channel is placed in the tripped condition within g bout, The Minimum Channels OPERABLE requirement is met;

however, the inoperable channel may be bypassed for up to gqhours for surveillance testing of other channels per per Specifica-tion 4.3.1.1, and c.

Either, THERMAL POWER is restricted to less than or equal to 75K of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85K of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored per Specification 4.2.4.2.

950731023b 95072b PDR ADQCK 05000250 P

PDR TURKEY POINT - UNITS 3 8

4

.I j

'/4 3-5 AMENDMENT NOS.

AND

ACTION 3 "

TABLE 3. 3-1 Continued)

ACTION STATEMENTS (Continued With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below lOX of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above lOX of RATED THERMAL POWER.

ACTION 4 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5-ACTION 6-ACTION 7-ACTION 8-ACTION 9 "

ACTION 10 "

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivi.ty changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification

3. l. 1. 1 or 3. 1. 1.2, as appli-cable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I'ove.

With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permiss'ive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3. 1.1, provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8.

The breaker shall not be bypassed while one of the diverse trip features is inoperable, except for the time required for performing mainten-ance to restore the breaker to OPERABLE status.

TURKEY POINT - UNITS 3 & 4 3/4 3-6 AMENDMENT NOS.~7AND ~

TABLE 3. 3-1 Continued 0 ACTION STATEMENTS Continued ACTION 13. - With the number of OPERABLE channels one'less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within hours'.

ACTION 12 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ACTUATION LOGIC TEST provided the inoperable channel is placed in the tripped condition within f houg; ACTION 13 - With the number of OPERABLE channels one less than the Total number of'hannels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within+ houg.

For subsequent required DIGITAL CHANNEL OPERATIONAL TESTS 4'noperable channel may be placed in bypass status for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

TURKEY POINT " UNITS 3 & 4 3/4 3-7 AMENDMENT NOSX40 ANDQS-

4

PCm CDM FUNCTIONAL UNIT TABLE 4.3-1 1

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREHENTS TRIP ANALOG ACTUATING CHANNEL DEVICE CHANNEL CHANNEL OPERATIONAL OPERATIOHAL ACTUATION CHECK CALIBRATION TEST TEST LOGIC TEST I

HOOES:. FOR

WHICH, SURVEILLANCE IS RE UIRED 1.

Hanual Reactor Trip N.A.

H.A.

R(11)

N.A.

4*

pk 2.

Power Range, Neutron Flux a.

High Setpoint O(2, 4),

+ Q H(3, 4},

q(4',

6)','(4)

N.A.

1, 2.

Vl I

CQ b.

Low Setpoint 3.

Intermediate

Range, Neutron Flux 4.

Source

Range, Neutron Flux S

5.

Overtemperature hT 6.

Overpower hT 7.

Pressurizer Pressure Low 8.

Pressurizer Pressure High S

9.

Pressurizer Mater Level--High S Reactor Coolant FlowLow S

ll.

Steam Generator Mater LevelS Low-Low R(4)

R(4)

R(4) e 5/U (i~

N.A.

S/U(1}~

N.A.

S/U(l),~q N.A, H.A.

N.A.

H.A.

N.A.

H.A.

N.A.

H.A.

~~*

~

4 1, 2 1.

2 1,

2

m TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CD CD CD C/1 FUNCTIONAL UNIT 12.

Steam Generator Mater LevelLow Coincident with Steam/Feedwater Flow Mismatch 13.

Undervoltage - 4. 16 kV Busses A and B

14.

Underfrequency - Trip of Reactor Coolant Pump Breakers(s)

Open 15.

Turbine Trip a.

Autostop Oil Pressure b.

Turbine Stop Valve Closure 16.

Safety Injection Input from ESF 17.

Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, P-6 b.

Low Power Reactor Trips Block, P-7 (includes P-10 input and Turbine First Stage Pressure) c.

Power Range Neutron Flux, P-8 N.A.

N.A.

S/U(1, 10)

N.A.

S/U(1, 10)

N.A.

1, 2

N.A.

R(4)

N.A.

R(4)

N.A.

R(4)

N.A.

TRIP ANALOG ACTUATING NODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIO'NAL OPERATIONAL ACTUATION SURVEILLANCE CHECK CALIBRATION TEST TEST LOGIC TEST IS RE UIRED 5

R l4-q N.A.

N.A.

1, 2

m FUNCTIONAL UNIT TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES FOR.

CHANNEL DEVICE MHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE CHECK CALIBRATION TEST TEST LOGIC TEST IS RE UIRED 17.

Reactor Trip System interlocks (Continued) d.

Power Range Neutron FIux, P-10 18.

Reactor Coolant Pump Breaker Position Trip N.A.

N.A.

R(4),

N.A.

1, 2

19.

Reactor Trip Breaker N.A.

N.A.

M(7, ll)

N.A.

4JI CD 20.

Automatic Trip and Inter-lock Logic N.A.

21.

Reactor Trip Bypass Breaker N.A.

N.A.

M(7,14) 1, 2, 3", 4", 5*

M(13),R(15) N.A.

1, 2, 3*, 4", 5" CD m

4, 4 ~

'4

TABLE 4. 3-1 Continued TABLE NOTATIONS "When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

""Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

"""Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous /days.

3l (2)

Comparison of calorimetric to excore power indication above 15K of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2X.

The provisions of Specification 4. 0. 4 are not applicable to entry into MODE 2 or l.

(3)

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15K of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3X.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

This table Notation number is not used.

(6)

Incore-Excore Calibration, above 75K of RATED THERMAL POWER (RTP). If the quarterly surveillance requirement coincides with sustained operation between 30X and 75K of RTP, calibration shall be performed at this lower power level.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)

N-th-powergreater than-or equal-to-the-Interlock Setpo+ntthe-req~d ANALNNAKANNELMAKKAKINKALKKKXh&J

'A~*A ' 'h N

tt lh h*

~nnuncizta~indow g - LF yp 0 Qv+IPKAI.P'9)AaatMy surveillance in MODES 3", 4", and 5" shall also include verifica-

'1 tion that permissive P-6 and P-10 are in their required state for exist-ing plant conditions by observation of the permissive annunciator window.

Q<+~"'.wyMontQy-surveillance shall include verification of the High Flux at Shut-down Alarm Setpoint of 1/2 decade above the existing count rate.

(10) Setpoint verification is not applicable.

(ll) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the OPERABILITY of the undervoltage and shunt trip attachment of the Reactor Trip Breakers.

TURKEY POINT - UNITS 3 8E 4 3/4 3-11 AMENDMENT NOS.~ AND ~

4 Et k

TABLE 3.3-2 Continued TABLE NOTATION ITrip function may be blocked in this NODE below the Pressurizer Pressure Interlock Setpoint of 2000 psig.

NChannels are for particulate rad1oactivity and for gaseous radioactivity.

NPAuxiliary feedwate}

manual in1tiation is included in Specification 3.7.1.2.

NffSteam Generator overfill protection is not part of the Engineered Safety Features Actuation System (ESFAS)',

and is added to the Technical Specifications only 1n accordance with NRC Gener1c Letter 89-19.

Trip funct1on may be blocked in this NODE below the Tavg Low Interlock Setpoint.

~Only during CORE ALTERATIONS or movement of irradiated fuel within the containment.

CTION STATEMENTS ACTION 14 With the number of OPERABLE channels one less than the Minimum Channe s

OPERABLE requirement, be in at least HOT STANDBY withl S hours and ln COLD SHUTDOHH w$thln the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ;

however, one channel may be bypassed for up to Sshour s for surveillance testing per Specif1cation 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15-ACTION 16 ACTION 17-With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST or TRIP ACTUATING DEVICE OPERATIONAL TEST provided the 1noperable channel is placed in the tripped condition within g~houg.

With less than the Minimum Channels OPERABLE requ1rement, comply with the ACTION statement requirements of Specifica-tion 3.3.3.1 Item la of Table 3.3-4.

With the number of OPERABLE channels one less than the Ninimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

JRKEY POINT UNITS 3 K 4 3/4 3-21 AMENDMENT NOS. ~ND K7-

l,,i J'

~ 4

~ ~

TABLE 3.3-2 Continued TABLE NOTATION (Continued)

ACTION 18-ACTION 19 "

ACTION 20 "

ACTION 21 "

ACTION 22 "

ACTION 23 "

ACTION 24-ACTION 25 "

With; the number of OPERABLE channels one less than the Total Numb'er of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within@~hoop, With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specifica-tion 3.0.3.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up top<hours for surveillance testing per Specification 4.3.2.1 pt'ovided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoper-able and take the ACTION required by Specification 3.7.1.5.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up to

+@hours for surveillance testing per Specification 4.3.2.1 pFovided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, comply with Specification 3.0.3.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolate the control room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode.

With the number of OPERABLE channels one less than the Total number of channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within//hove..

For subsequent required DIGITAL CHANNEL OPERATIONA'6 TESTS the inoperable channel may be placed

, in bypass status for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

TURKEY POINT - UNITS 3 4 4 3/4 3-22 AMENDMENT HOSP'-AND~

TABi; 3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION SUV L

N URMN CHANNEL CHANNEL CHECK CALIBRATION N.A.

b.

C.

d.

Automatic Actuation N.A.

Logic and Actuation Relays Containment Pressure--

N.A.

High Pressurizer Pressure S Low N.A.

CHANNEL FUNCTIONAL UNIT 1.

Safety Injection (Reactor Trip, Turbine Trip, Feed-water Isolation, Control Room Ventilation Isolation, Start Diesel Generators, Containment Phase A Isola-tion (except Hanual SI),

Containment Cooling Fans, Containment Filter Fans, Start Sequencer, Component Cooling Mater, Start Auxiliary Feedwater and Intake Cooling Mater) a.

Hanual Initiation N.A.

N.A.

I Q H(5)

N.A.

TRIP ANALOG

'CTUATING CHANNEL 'EVICE OPERATIONAL OPERATIONAL TEST TEST N.A.

1 2

3 1, 2, 3(3)

N.A.

1, 2, 3

1, 2, 3(3)

I I

MODES FOR MHICH ACTUATION SURVEILLANCE LOGIC IG IG IG REISUIREQ e.

High Differential Pressure Between the Steam Line Header and any Steam Line f.

Steam Line FlowHigh S

Coincident with:

Steam Generator Pressure Low S

or T

Low S

Q+5)

Q +5)

$ 9(5) q(5)

N.A.

1 2

3('3) 1, 2, 3(3)

1. 2. 3(3) 1, 2, 3(3)

TABLE 4.3-2 (Continued)

ENGI E

ED S ETY E TURES C UATION SYSTE INSTRU ENT TION SURVEILLANC E UI EVENTS CHANNEL U

C 0

U 4.

Steam Line Isolation (Continued)

TRIP ANALOG ACTUATING NODES CHANNEL DEVICE FOR MHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE QLUI

~<

B-I LBBITES I LJSRUUE c,

Containment Pressure N.A.

High-High Coincident with:

Containment Pressure N.A.

High N.A.

N.A.

1, 2, 3

d.

Steam Line FlowHigh Coincident with:

Steam Generator Pressure Low or T

Low S(3)

S(3)

S(3) 9 e(6)

Q N(S)

Q(5)

N.A.

1, 2, 3

1, 2, 3 1, 2, 3

5.

Feedwater Isolation Automatic Actuation Logic and Actuation Relays N.A.

N.A.

1, 2

b.

Safety Injection See Item.l. above for all Safety Injection Surveillance Requirements.

C.

Steam Generator Mater LevelHigh-High S

R N.A.

N.A.

1, 2 6.

Auxiliary Feedwater (2)

Automatic Actuation Logic and Actuation Relays N.A.

N.A.

1, 2, 3

b.

Steam Generator Mater LevelLow-Low N.A.

N.A.

1, 2, 3

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATIOH SU VEIL C

UIREM H S TRIP ANALOG ACTUATING MODES CHANNEL DEVICE FOR MHICH CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE CALIBRATION TEST TEST LOGIC TESTS IS RE UIRED CHANNEL CHECK CHANNEL FUNCTIONAL UNIT 8.

Engineering Safety Features Actuation System Interlocks a.

Pressurizer Pressure N.A.

b.

T Low N.A.

9.

Control Rooa Ventilation Isolation a.

Automatic Actuation N.A.

Logic and Actuation Relays b.

Safety Injection c.

Containment RadioactivityHigh d.

Contairwent Isolation N.A.

Manual Phase A or Manual Phase 8

e.

Control Room Air S

Intake Radiation Level Q ~5)

Q(5) 1, 2, 3(3) 1, 2, 3(3)

N.A.

See Itea l. above for all Safety Injection Surveillance Requirements.

S R

N N.A.

N.A.

(4)

N.A.

1, 2, 3, 4 N.A.

All N.A.

g tg tt t t t t

t gt t t t tt t I

d gt tt t

t relay and verification of OPERABILITY of each rel~.

TABLE NOTATIONS (1)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2)

Auxiliary feedwater manual initiation is included in Specification 3.7.1.2.

(3)

The provisions of Specification 4.0.4 are not applicable for entering Mode 3, provided that the applicable surveillances are completed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months frea entering Mode 3.

(4)

Applicable in MODES 1, 2, 3, 4 or during CORE ALTERATIONS or Ioveaent of irradiated fuel within the containment.

(5)

Test of alars function not required when alarm locked in.

eL r

I C1 fi

P

~

P 3/4. 3 INSTRUMENTATION0 BASES 3/4. 3. 1 and 3/4. 3.2 REACTOR TRIP SYSTEH and ENGINEERED SAFETY FEATURES A

N S

S NS RUHENTATI N The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that:

(1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint (2) the specified coincidence logic is maintained, (3) sufficient redundancy is main-tained to permit a channel to be out-of-service for testing or maintenance (due to plant specific design, pulling fuses and using jumpers may be used to place channels in trip), and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, 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 safety analyses.

The Surveillance Requirements speci-fied for these systems ensure that the overall system functional capability is maintained comparable to the original design standards.

The periodic surveil-lance tests performed at t min>mum frequencies are sufficient to demonstrate this capability.

y <<

p, Under some pressure and temperature conditions, certain surveillances for Safety Injection cannot be performed because of the system design.

Allowance to change modes is provided under these conditions as long as the surveillances are completed within specified time requirements.

The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit.

The set~oint is considered to be adjusted consistent with the nominal value when the

'as measured" setpoint is within the band allowed for calibration accuracy.

To accommodate the instrument drift that may occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Setpoints have been specified in Table 3.3-3.

Opera-tion with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. If no value is listed in the Allowable column, the Setpoint value is the limiting setting.

For some functions, an optional provision has been included for determining the OPERABILITY of a channel when its trip setpoint is found to exceed the Allowable Value.

The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncer-tainties of the instrumentation to measure the process variable and the uncer tainties in calibrating the instrumentation.

In Equation 2.2-1,

7. + R + S g TA, the interactive effects of the errors in the rack and the sensor, and the "as measured" TURKEY POINT - UNITS 3 Ea 4 B 3/4 3-1 NENDMENT NOS. HGAND H5

0

~ ~

Insert A

Surveillance for the analog RPS/ESFAS Hagan rack instrumentation have been extended to quarterly in accordance with WCAP-10271, "Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System,"

and supplements to that report as generically approved by the NRC and documented in their SERs (Letters to the Westinghouse Owner's Group from the NRC dated February 21, 1985 and February 22, 1989).

~ ~

ML17353A280

Text

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