ML16216A357

Proposed Tech Specs Extending Surveillance Test Intervals & Allowed Outage Times

ML16216A357
Person / Time
Site:	Salem
Issue date:	07/16/1992
From:	Public Service Enterprise Group
To:
Shared Package
ML16216A358	List: ML16216A357 ML18096A839
References
NUDOCS 9207240103
Download: ML16216A357 (51)

Text

ATTACHMENT Al Markup of Salem Unit 1 Technical Specification 3/4.3.1 Reactor Trip System Instrumentation ATTACHMENT Al Technical Specification 3.3.1 insert.

INSERT 1: ACTION 10 -With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

9207240 920716 PDR A 05000272 TABLE 3.3-1 (Continued) tfl REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 11. Pressurizer Water Level--High 3 2 2 1, 2 -9#- &# 12. Loss of Flow -Single Loop 3/loop 2/loop in 2/loop in 1 -# 4M (Above P-8) any oper- each operating loop ating loop 13. Loss of Flow -Two Loops 3/loop 2/loop in 2/loop in 1 t .4 (Above P-7 and below P-8) two oper- each operating loops ating loop 14. Steam Generator Water Level-- 3/loop 2/loop in. 2/loop in 1, 2 -- 6%r Low-Low any oper- each operating loops ating loop 15. Steam/Feedwater Flow Mismatch 2/loop-level 1/loop-level 1/loop-level 1, 2 19 (oE and Low Steam Generator Water and 2/loop- coincident and 2/loopLevel flow mismatch with flow mismatch 1/loop-flow or 2/loopmismatch in level and same loop 1/loop-flow mismatch

16. Undervoltage-Reactor Coolant Pumps 4-1/bus 1/2 twice 4 1 6 (D 17. Underfrequency-Reactor Coolant 4-1/bus 1/2 twice 4 1 6 Pumps rt 0 I-.

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION H 18. Turbine Trip Low Autostop Oil Pressure 3 2 2 1 19 & Turbine Stop Valve Closure 4 4 3 1 -t f 19. Safety Injection Input from ESF 2 1 2 1,2 0 20. Reactor Coolant Pump Breaker 1/breaker 2 1/breaker 1 11 Position Trip (above P-7) per operating loop 21. Reactor Trip Breakers 2 1 2 1, 2 1###, 14 3*,4*,5*

13 22. Automatic Trip Logic 2 1 2 1, 2 +/-t /0 3*,4*,5*

13 D rt. 0 F-TABLE 3.3-1 (Continued)

TABLE NOTATION

• With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

• • The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

1. The provisions of Specification 3.0.4 are not applicable,

1. 1. High voltage to detector may be de-energized above P-6. ### If ACTION Statement 1 is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breakers (RTBB) maintenance testing results exceeding the following acceptance

criteria, NRC reporting shall be made in accordance with Specification 6.9.1.9:

1. A RTB or RTBB trip failure during any surveillance test with less than or equal to 300 grams of weight added to the breaker trip bar. 2. A RTB or RTBB time response failure that results in the overall reactor trip system time response exceeding the Technical Specification limit. ACTION STATEMENTS ACTION 1 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed 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 surveillance testing per Specification 4.3.1.1 provided the other channel is OPERABLE.

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

a. The inoperable channel is placed in the tripped condition within + hour. b. The Minimum Channels OPERABLE requirement is met; however, ene edditioek channel may be bypassed for up to -ffur-s for surveillance testing per Specification 4.3.1.1.

A c. Either, THERMAL POWER is restricted to r 75% of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ACTION 3 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: SALEM UNIT 1 3/4 3-5 Amendment No. 114 TABLE 3.3-1 (Continued)

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

b. Above P-6 but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER. c. Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

ACTION 4 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: a. P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above P-6, operation may continue.

ACTION 5 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 /> thereafter.

ACTION 6 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within -I hour. b. The Minimum Channels OPERABLE requirement is met; however,

-ee dditiewe channel may be bypassed for up to 1q i- hours for surveillance testing per Specification 4.3.1.1.

A OFo Cjh C#j4Ad,,dLS ACTION 7 -Wh the-numbr-ef

-PHRABB nunls l ne-ls thae- the Tetl SAE Mf STATUP UIT r PWBR 3/4PEfl.P.T 3-6FUNCTIO4At TEST ytoLvJA1ed the +/-npral channe.l:

is plcd u-Lh rJpped eend..tLz within 1 heele. SALEM -UNIT 1 3/4 3-6 TABLE 3.3-1 (Continued)

ACTION 9 -With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel associated with an operating loop may be bypassed 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 surveillance testing per Specification 4.3.1.1.

ACTION 10 --Bee ed SEE IVsER ACTION 11 -With less than the Minimum Number of Channels

OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 4-hour.

61 ACTION 12 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour. ACTION 14 -With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels

< 6x10-11 the manual block of amps. source range reactor trip. P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low impulse chamber pressure channels flow in more than one 2 a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER. reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

SALEM -UNIT 1 3/4 3-7 Amendment No. 97

• TABLE 1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip Switch NA NA S/U(9) NA 2. Power Range, Neutron Flux S D(2), M(3) 44- 4 1, 2 and Q(6) 3. Power Range, Neutron Flux, NA R(6) 14- Q 1, 2 High Positive Rate 4. Power Range, Neutron Flux, NA R(6) -M- q 1, 2 High Negative Rate 5. Intermediate Range, Neutron S R(6) S/U(l) 1, 2 and

• Flux 6. Source Range, Neutron Flux S(7) R(6) Q 4 and S/U(l) 2, 3, 4, 5 and

• 7. Overtemperature AT S R 44 1, 2 8. Overpower AT S R -Q 1, 2 9. Pressurizer Pressure--Low S R 4- 9 1, 2 10. Pressurizer Pressure--High S R 4- Q 1, 2 11. Pressurizer Water Level--High S R 44- 1, 2 12. Loss of Flow -Single Loop S R 44- 1 0D 0 Lfl TABLE 4 Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

13. Loss of Flow -Two Loops S R N.A. 1 14. Steam Generator Water Level-- S R 4- Q 1, 2 Low-Low 15. Steam/Feedwater Flow Mismatch

& S R 4 Q 1, 2 Low Steam Generator Water Level 16. Undervoltage

-Reactor Coolant N.A. R 4- Q 1 Pumps 17. Underfrequency

-Reactor Coolant N.A. R 44- Q 1 Pumps 18. Turbine Trip A. Low Autostop Oil Pressure N.A. N.A. S/U(l) 1, 2 B. Turbine Stop Valve Closure N.A. N.A. S/U(1) 1, 2 19. Safety Injection Input from ESF N.A. N.A. M(4)(5) 1, 2 20. Reactor Coolant Pump Breaker N.A. N.A. R N.A. Position Trip 21. Reactor Trip Breaker N.A. N.A. S/U(10),

1, 2 and M(11,13),

SA(12,13) and R(14) (D 22. Automatic Trip Logic N.A. N.A. M(5) 1, 2 and

• r z 0 (.W TABLE 4.3-1 (Continued)

NOTATION

• -With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

31 (1) -If not performed in previous

+ days. (2) -Heat balance only, above 15% of RATED THERMAL POWER. (3) -Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference 3 percent.

(4) -Manual SSPS functional input check every 18 months.

(5) -Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (6) -Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8) -Deleted (9) -If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip wiring.

(10) -o not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test 0 of:

• Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS)

• Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

(11) -Perform a functional test of:

• Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorders)

• Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

(12) -Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:

a. response time testing, (3 times) (visicorder) trend data b. trip bar lift force measurements

c. UV output force measurement

d. dropout voltage check e. servicing/lubrication/adjustments (See Table 3.3-1 Notation

f. repeat testing steps (a-d) following any necessary actions at step (e) SALEM UNIT 1 3/4 3-13 Amendment No. 97 ATTACHMENT A2 Markup of Salem Unit 1 Technical Specification 3/4.3.2 Engineered Safety Feature Actuation System Instrumentation ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM > TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation 2 1 2 1, 2, 3, 4 18 b. Automatic Actuation Logic 2 1 2 1, 2, 3, 4 13 c. Containment Pressure-High 3 2 2 1, 2, 3 14*

• d. Pressurizer Pressure-Low 3 2 2 1, 2, 3# b 19

• e. Differential Pressure Between 1, 2, 3## Steam Lines -High Four Loops 3/steam line 2/steam line 2/steam line +4* 19 Operating any steam line uL Three Loops 3/operating 1 #/steam 2/operating 15 Operating steam line line, any steam line operating steam line D rt 0 TABLE 3.3- &tinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f. Steam Flow in Two Steam 1, 2, 3## Lines-High Four Loops 2/steam line 1/steam line 1/steam line t4N *9* Operating any 2 steam lines Three Loops 2/operating 1 #/any 1/operating 15 Operating steam line operating steam line steam line COINCIDENT WITH EITHER Tavg --Low-Low 1, 2, 3## Four Loops 1 Tavg/loop 2 Tavg any 1 Tavg any -H I9 Operating loops 3 loops 0)1 Three Loops 1 Tavg/opera-1 # Tavg 1 Tavg in 15 Operating ting loop in any any two operating operating loop loops TABLE 3.3-3@tinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3## Four Loops 1 pressure/

1 pressure 1 pressure

+4*- 19 Operating loop any 2 loops any 3 loops 2. CONTAINMENT SPRAY a. Manual 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3, 4 18 b. Automatic Actuation Logic 2 1 2 1, 2, 3, 4 13 c. Containment Pressure--High-High 4 2 3 1, 2, 3 16 3. CONTAINMENT ISOLATION

a. Phase "A" Isolation

1) Manual 2 1 2 1, 2, 3, 4 18 2) From Safety Injection 2 1 2 1, 2, 3, 4 13 Automatic Actuation Logic TABLE 3.3-@ontinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Three Loops 1 Tavg/opera-l### Tavg 1 Tavg in 15 ting loop in any any two operating operating loop loops OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3## Four Loops 1 pressure/

1 pressure/

1 pressure/

14* Operating loop any 2 loops any 3 loops Three Loops 1 pressure/

1 ### pres- 1 pressure in 15 Operating operating loop sure in any any 2 operating operating loops loop o 5. TURBINE TRIP & FEEDWATER ISOLATION

a. Steam Generator Water level-- 3/loop 2/loop in 2/loop in 1, 2, 3 -:4* 19 High-High any opera- each operating loop ting loop 6. SAFEGUARDS EQUIPMENT 3 2 3 1, 2, 3, 4 13 CONTROL SYSTEM (SEC) 7. UNDERVOLTAGE, VITAL BUS a. Loss of Voltage 1/bus 2 3 1, 2, 3 14* b. Sustained Degraded Voltage 3/bus 2/bus 3/bus 1, 2, 3 14* O 0 TABLE 3.3-Bntinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C 8. AUXILIARY FEEDWATER

a. Automatic Actuation Logic** 2 1 2 1, 2, 3 20 b. Manual Initiation 1/pump 1/pump 1/pump 1, 2, 3 22 c. Steam Generator Water Level-Low-Low i. Start Motor Driven Pumps 3/stm. gen. 2/stm. gen. 2 stm. gen. 1, 2, 3 -b4 19o ii. Start Turbine Driven Pumps 3/stm. gen. 2/stm. gen. 2 stm. gen. 1, 2, 3 tbb 194 d. Undervoltage

-RCP Start 4(1/bus) 1/2 x 2 3 1, 2 19 Turbine -Driven Pump e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f. Emergency Trip of Steam Generator 2(1/pump) 2 2(1/pump) 1 21 Feedwater Pumps Start Motor Driven Pumps g. Station Blackout See 6 and 7 above (SEC and U/V Vital Bus) **Applies to items c and d. rt 0)

TABLE 3.3-3 (Continued)

TABLE NOTATION

1. Trip function may be bypassed in this MODE below P-11. ## Trip function may be bypassed in this MODE below P-12. ### The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode. *The provisions of Specification 3.0.4 are not applicable.

RE-sro rN-7H JA16'eiA6.E Ct4A-fJPJL ACTION STATEMENTS To OPEA46LAE 61n.u wrIds & ACTION 13 -With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY withi 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to -'hours for surveillance testing per Specification 4.3.2.1.

1 Peovofo T04 7 c 170S 07W46XC iJAD6L. IC 0#AM4LC, ACTION 14 -With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. ACTION 15 -With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed 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 surveillance testing per Specification 4.3.2.1.1.

ACTION 16 -With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 6 + hour; one additional channel may be bypassed for up to 2-2hours for surveillance testing per Specification 4.3.2.1.1.

ACTION 17 -With less than the Minimum Channels

OPERABLE, operations may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. SALEM -UNIT 1 3/4 3-21 Amendment No. 60 TABLE 3.3-3 (Continued)

ACTION 19 -With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within + hour b. The Minimum Channels OPERABLE requirements is met; T"' 1two'PA4;

however, l channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.2.1.1 A ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels 1925 manual block of safety psig. injection actuation on low pressurizer pressure.

P-12 With 3 of 4 Tavg channels P-12 prevents or defeats 5450F. manual block of safety injection actuation high steam line flow and low steam line pressure.

With 2 of 4 Tavg channels Allows manual block of <54i0F. safety injection actuation on high steam line flow and low steam line pressure.

Causes steam line isolation on high steam flow. Affects RES-4TMr WoP& AdutcJ4,vosteam dump blocks.

wM O)PPP'QAL S -4^'-'ps G/~-J~ ACTION 20 -With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following hours; however, one channel may be bypassed for up to (+/- ours for surveillance testing%

P.E SPeFcA-roe TH "6'C '~4..ZWI P,?0i,04D~E

-p4A. O-q'RAr.

C'4A-.Js~dL IS OP.t4ASLSE.

ACTION 21 -With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either: a. The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or b. If the affected Steam Generator Feedwater Pump is expected to be out of service for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the inoperable channel is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Steam Generator Feedwater Pump. ACTION 22 -With the number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONs of L.C.O. 3.7.1.2 apply. SALEM -UNIT 1 3/4 3-22 Amendment No. 56

• AT ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH tTj CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation NA NA R 1, 2, 3, 4 b. Automatic Actuation Logic NA NA M(2) 1, 2, 3, 4 c. Containment Pressure-High S R 4+(3) 1, 2, 3 d. Pressurizer Pressure--Low S R Q M 1, 2, 3 e. Differential Pressure Between S R C 4 1, 2, 3 Steam Lines--High

f. Steam Flow in Two Steam Lines-- S R 4 1, 2, 3 High Coincident with Tavg--Low Low or Steam Line Pressure-Low

2. CONTAINMENT SPRAY a. Manual Initiation NA NA R 1, 2, 3, 4 b. Automatic Actuation Logic NA NA M(2) 1, 2, 3, 4 c. Containment Pressure--High-High S R + -(3) 1, 2, 3 O :j -0 TABLE 4.3-Bntinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

3. CONTAINMENT ISOLATION rt a. Phase "A" Isolation

1. Manual NA NA R 1, 2, 3, 4 2. From Safety Injection NA NA M(2) 1, 2, 3, 4 Automatic Actuation Logic b. Phase "B" Isolation

1. Manual NA NA R 1, 2, 3, 4 2. Automatic Actuation Logic NA NA M(2) 1, 2, 3, 4 3. Containment Pressure--

S R 44-3) 1, 2, 3 High-High

c. Containment Ventilation Isolation

1. Manual NA NA R 1, 2, 3, 4 2. Automatic Actuation Logic NA NA M(2) 1, 2, 3, 4 3. Containment Radioactivity

-- Per table 4.3-3 High O (D :JI 0t -I TABLE 4.3-*ntinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

4. STEAM LINE ISOLATION

a. Manual NA NA R 1, 2, 3 b. Automatic Actuation Logic NA NA M(2) 1, 2, 3 c. Containment Pressure--

S R t "(3) 1, 2, 3 High-High

d. Steam Flow in Two Steam S R 1, 2, 3 Lines--High Coincident with Tavg--Low or Steam Line Pressure--Low

5. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water S R 1 1, 2, 3 Level--High-High

6. SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) LOGIC a. Inputs NA NA M 1, 2, 3, 4 b. Logic, Timing and NA NA M(1) 1, 2, 3, 4 Outputs 7. UNDERVOLTAGE, VITAL BUS a. Loss of Voltage S R M 1, 2, 3 0 b. Sustained Degraded Voltage S R M 1, 2, 3 U, TABLE 4.3 ntinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

8. AUXILIARY FEEDWATER

a. Automatic Actuation Logic NA NA M(2) 1, 2, 3 b. Manual Initiation NA NA M(4) 1, 2, 3 c. Steam Generator Water S R Q 4 1, 2, 3 Level--Low-Low

d. Undervoltage

-RCP S R Q + 1, 2 e. S.I. See 1 above (All S.I. surveillance requirements)

f. Emergency Trip of Steam NA NA R 1 Generator Feedwater Pumps g. Station Blackout See 6b and 7 above (SEC and U/V Vital Bus) O (D 0%

ATTACHMENT A3 Markup of Salem Unit 1 Technical Specification 3/4.3.1 and 3/4.3.2 Bases ATTACHMENT A3 INSERT 1: New Bases Paragraph

1. 1 (Add to the existing paragraph).

... and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation and, 3) sufficient system functions capability is available from diverse parameters.

INSERT 2: New Bases Paragraph

1. 2 (Add to existing paragraph).

Specified surveillance intervals and surveillance and maintenance outage times have been determined 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. Surveillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,

2) the specified coincidence logice -ma~intained,

3) suffieient edundaney is maintainoed to --i a ehoornol to be ADO 4jcwd oet of seve for testing or maintenanceo, an.d 4) suffleient systeoa fuelnperametera.

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 performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

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 offsite test measurements or 2) utilizing replacement sensors with certified response times. 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served SALEM -UNIT 1 B 3/4 3-1 ATTACHMENT B1 Markup of Salem Unit 2 Technical Specification 3/4.3.1 Reactor Trip System Instrumentation ATTACHMENT B1 Technical Specification 3.3.1 insert.

INSERT 1: ACTION 10 -With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 11. Pressurizer Water Level--High 3 2 2 1, 2 i 6t 12. Loss of Flow -Single Loop 3/loop 2/loop in 2/loop in 1 M* (i (Above P-8) any oper- each operating loop ating loop 13. Loss of Flow -Two Loops 3/loop 2/loop in 2/loop in 1 4- (o (Above P-7 and below P-8) two oper- each operating loops ating loop 14. Steam Generator Water 3/loop 2/loop in 2/loop in 1, 2 -9 + A Level--Low-Low any oper- each operating loops ating loop 15. Steam/Feedwater Flow 2/loop-level 1/loop-level 1/loop-level 1, 2 -6# 4 Mismatch and Low Steam and coincident and Generator Water Level 2/loop-flow with 2/loop-flow mismatch 1/loop-flow mismatch or mismatch in 2/loop-level same loop and 1/loop-flow mismatch 5 16. Undervoltage-Reactor Coolant (D Pumps 4-1/bus 1/2 twice 4 1 6 rt 0 17. Underfrequency-Reactor Coolant Pumps 4-1/bus 1/2 twice 4 1 6 0 En TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 18. Turbine Trip a. Low Autostop Oil Pressure 3 2 2 1 +#- 6 b. Turbine Stop Valve Closure 4 4 4 1 9#- 6# 19. Safety Injection Input from ESF 2 1 2 1,2 4-- 10 20. Reactor Coolant Pump Breaker 1/breaker 2 1/breaker 1 11 Position Trip (above P-7) per operating loop 21. Reactor Trip Breakers 2 1 2 1, 2 1###, 14 3*,4*,5*

13 22. Automatic Trip Logic 2 1 2 1, 2 -10 3*,4*,5*

13 (D z 0 TABLE 3.3-1 (Continued)

TABLE NOTATION

• With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

• • The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

1. The provisions of Specification 3.0.4 are not applicable.

1. 1. High voltage to detector may be de-energized above P-6. ### If ACTION Statement 1 is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breaker (RTBB) maintenance testing results exceeding the following acceptance

criteria, NRC reporting shall be made in accordance with Specification 6.9.1.9:

1. A RTB or RTBB trip failure during any surveillance test with less then or equal to 300 grams of weight added to the breaker trip bar. 2. A RTB or RTBB time response failure that results in the overall reactor trip system time response exceeding the Technical Specification limit. ACTION STATEMENTS ACTION 1 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed 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 surveillance testing per Specification 4.3.1.1 provided the other channel is OPERABLE.

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

a. The inoperable channel is placed in the tripped condition within + hour. .(0 5 b. The Minimum Channels OPERABLE requirement is met; however, Th jAoPe-q'..E cne additicnal channel may be bypassed for up to G- hours for surveillance testing per Specification 4.3.1.1.

oF O7h&Ck CtiA'v6(c. Either, THERMAL POWER is restricted to 75% of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. d. The QUADRANT POWER TILT RATIO, as indicated by the remaining three detectors, is verified consistent with the normalized symmetric power distribution obtained by using the movable in-core detectors in the four pairs of symmetric thimble locations-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 THERMAL POWER is greater than 75% of RATED THERMAL POWER. SALEM -UNIT 2 3/4 3-5 Amendment No. 96 TABLE 3.3-1 (Continued)

-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Block of Source Reactor Trip) setpoint but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER. c. Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d. Above 10% of RATED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

ACTION 4 -With the number.of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level: a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, operation may continue.

ACTION 5 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 /> thereafter.

ACTION 6 -With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within +i hour. b. The Minimum Channel OPERABLE requirement is met; Ti4e voAS -however,

i ne! channel may be bypassed for up to q hours for surveillance testing per Specification 4.3.1.1.

OF -7T 23A3-Je t 2 ACTION 7 -With thenuber~

ef OI'DfABLE ehannls n less than the Total Number~ ofj -ehaznei-,

STARU r PeWflR ePBhRAT+9N my MaJT L'5F0 eereod until-prean-

---

z thzic JCINE rUNCT1ONAB TET reidd the ineperable channel is plaeed -ir Ac--roAj

'V --pe SALEM -UNIT 2 3/4 3-6 Amendment No. 28 TABLE 3.3-1 (Continued)

ACTION 9 -With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel associated with an operating loop may be bypassed 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 surveillance testing per Specification 4.3.1.1.

ACTION 10 -Deleted.

ACTION 11 -With less than the Minimum Number of Channels

OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within +i hour. 6 5 ACTION 12 -With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour. ACTION 14 -With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats Neutron Flux Channels

< 6x10-11 the manual block of amps. source range reactor trip. P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels

-11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low impulse chamber pressure channels flow in more than one 2 a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER. reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

SALEM -UNIT 2 3/4 3-7 Amendment No. 74 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS H CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip Switch N.A. N.A. S/U(9) N.A. 2. Power Range, Neutron Flux S D(2), M(3) 14- 1, 2 and Q(6) 3. Power Range, Neutron Flux, N.A. R(6) 14- 1, 2 High Positive Rate N.A. R(6) Q <*- 1, 2 4. Power Range, Neutron Flux, High Negative Rate 5. Intermediate Range, Neutron Flux S R(6) S/U(1) 1, 2 and

• 6. Source Range, Neutron Flux S(7) R(6) Q --and S/U(1) 2, 3, 4, 5 and

• 7. Overtemperature AT S R 44 1, 2 8. Overpower AT S R -1, 2 9. Pressurizer Pressure--Low S R Q44- 1, 2 10. Pressurizer Pressure--High S R Q -M- 1, 2 (D 11. Pressurizer Water Level--High S R Q 44 1, 2 Z 00 TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH H CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

13. Loss of Flow -Two Loops S R N.A. 1 14. Steam Generator Water Level-- S R 44- C 1, 2 Low-Low 15. Steam/Feedwater Flow Mismatch

& S R 4- Q 1, 2 Low Steam Generator Water Level N 16. Undervoltage

-Reactor Coolant N.A. R -Q 1 Pumps 17. Underfrequency

-Reactor Coolant N.A. R 44 C 1 Pumps 18. Turbine Trip a. Low Autostop Oil Pressure N.A. N.A. S/U(1) N.A. b. Turbine Stop Valve Closure N.A. N.A. S/U(1) N.A. 19. Safety Injection Input from ESF N.A. N.A. M(4)(5) 1, 2 20. Reactor Coolant Pump Breaker N.A. N.A. R N.A. Position Trip : 21. Reactor Trip Breaker N.A. N.A. S/U(10),

1, 2 and

• M(11,13),

o SA(12,13) and R(14) 0 22. Automatic Trip Logic N.A. N.A. M(5) 1, 2 and

• TABLE 4.3-1 (Continued)

NOTATION S* -With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

31 (1) -If not performed in previous 7- days. (2) -Heat balance only, above 15% of RATED THERMAL POWER. (3) -Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference 3 percent.

(4) -Manual SSPS functional input check every 18 months.

(5) -Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (6) -Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -Below P-6 (Block of Source Range Reactor Trip) setpoint.

(8) -Deleted (9) -If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and shunt trip wiring.

(10) -If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

• Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS)

• Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

(11) -Perform a functional test of:

• Reactor Trip Breaker independent operation of U.V. Trip and Shunt Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip/Breakers (event recorders)

• Reactor Trip Breaker Shunt Trip (via manual pushbutton controls)

(12) -Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:

a. response time testing, (3 times) (visicorder) trend data b. trip bar lift force measurements

c. U.V. output force measurement

d. dropout voltage check SALEM -UNIT 2 3/4 3-13 Amendment No. 74 ATTACHMENT B2 Markup of Salem Unit 2 Technical Specification 3/4.3.2 Engineered Safety Features Actuation System Instrumentation

• TA .3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation 2 1 2 1, 2, 3, 4 18 b. Automatic Actuation Logic 2 1 2 1, 2, 3, 4 13 c. Containment Pressure-High 3 2 2 1, 2, 3 14" IR* d. Pressurizer Pressure-Low 3 2 2 1, 2, 3# +/-* 19

• e. Differential Pressure Between 1, 2, 3## Steam Lines -High Four Loops 3/steam line 2/steam line 2/steam line -+4* 19 Operating any steam line TABLE 3. @Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

) FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f. Steam Flow in Two 1, 2, 3## Steam Lines-High H Four Loops 2/steam line 1/steam line 1/steam line +4* 19 A Operating any 2 steam lines COINCIDENT WITH EITHER Tavg --Low-Low 1, 2, 3## Four Loops 1 T g/loop 1 T g any 2 1 T any it4* 19 A Operating loops 3 loo 0)-

TABLE 3.o Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3## Four Loops 1 pressure/

1 pressures 1 pressure SM Operating loop any 2 loops any 3 loops 2. CONTAINMENT SPRAY a. Manual 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3, 4 18 b. Automatic Actuation Logic 2 1 2 1, 2, 3, 4 13 c. Containment Pressure--High-High 4 2 3 1, 2, 3 16 3. CONTAINMENT ISOLATION

a. Phase "A" Isolation

1) Manual 2 1 2 1, 2, 3, 4 18 2) From Safety Injection 2 1 2 1, 2, 3, 4 13 Automatic Actuation Logic TABLE 3. Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4. STEAM LINE ISOLATION

a. Manual 2/steam line 1/steam line 1/operating 1, 2, 3 21 steam line b. Automatic Actuation Logic 2*** 1 2 1, 2, 3 20 c. Containment Pressure--High-High 4 2 3 1, 2, 3 16 d. Steam Flow in Two Steam Lines--High Four Loops 2/steam line 1/steam line 1/steam line 1-ib 19 Operating any 2 steam lines COINCIDENT WITH EITHER T --Low-Low 1, 2, 3## avg Four Loops I T /loop 1 T in 1 T in +/-40 19 Operating avg any 2 loops any 3gloops *** The automatic actuation logic includes two redundant solenoid operated vent valves for each Main Steam Isolation Valve. One vent valve on any one Main Steam Isolation Valve may be isolated without affecting the function of the automatic actuation logic provided the remaining seven solenoid vent valves remain operable.

The isolated MSIV vent valve shall be returned to OPERABLE status upon the first entry into MODE 5 following determination that the vent valve is inoperable.

For any condition where more than one of the eight solenoid vent valves are inoperable, entry into ACTION 20 is required.

O U, TABLE 3. (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Three Loops 1 Tavg/opera-1### Tavg 1 Tavg in 15 ting loop in any any two operating operating loop loops OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3## Four Loops 1 pressure/

1 pressure 1 pressure

-bH IfI Operating loop any 2 loops any 3 loops Three Loops 1 pressure/

1 ### pres- 1 pressure in 15 Operating operating loop sure in any any 2 operating operating loops loop o 5. TURBINE TRIP & FEEDWATER ISOLATION

a. Steam Generator Water level-- 3/loop 2/loop in 2/loop in 1, 2, 3 +/-4. 1RA High-High any opera- each operating loop ting loop 6. SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) 3 2 3 1, 2, 3, 4 13 7. UNDERVOLTAGE, VITAL BUS a. Loss of Voltage 1/bus 2 3 1, 2, 3 14* b. Sustained Degraded Voltage 3/bus 2/bus 3/bus 1, 2, 3 14* O TABLE 3. O Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 8. AUXILIARY FEEDWATER

a. Automatic Actuation Logic** 2 1 2 1, 2, 3 20 b. Manual Initiation 1/pump 1/pump 1/pump 1, 2, 3 23 c. Stm. Gen. Water LevelLow-Low i. Start Motor Driven Pumps 3/stm. gen. 2/stm. gen. 2 atm. gen. 1, 2, 3 +/-4* 19* any atm. gen. ii. Start Turbine Driven Pumps 3/stm. gen. 2/atm. gen. 2 stm. gen. 1, 2, 3 1:41 I any 2 atm. N. gen. d. Undervoltage

-RCP Start 4-1/bus 1/2 x 2 3 1, 2 19 Turbine -Driven Pump e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f. Trip of Main 2/pump 1/pump 1/pump 1, 2 22* Feedwater Pumps Start MotorDriven Pumps M 9. Semiautomatic Transfer to Recirculation r1 a. RWST Level Low 4 2 3 1, 2, 3 16 b. Automatic Actuation Logic 2 1 2 1, 2, 3 -13 20 O m **Applies to items c and d. This page effective prior to startup from the fifth refueling outage. Correction letter dated May 16, 1990.

TABLE 3.3-3 (Continued)

TABLE NOTATION

1. Trip function may be bypassed in this MODE below P-11 (Pressurizer Pressure Block of Safety Injection) setpoint.

1. 1. Trip function may be bypassed in this MODE below P-12 (Tavg Block of Safety Injection) setpoint.

• The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS RESTofet 774 ,OVPeAECf CI fAAJN06L 70 OPR94&%L)CS7A-7U wrr,.-~ (o IO40VZ5 Ole ACTION 13 -With the number of OPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to -2 hours for TPE ALcr surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 14 -With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. ACTION 15 -With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed 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 surveillance testing per Specification 4.3.2.1.

ACTION 16 -With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated by CHANNEL CHECK within 4-hour; one additional channel may be bypassed for up to 29hours for surveillance testing per Specification 4.3.2.1.

ACTION 17 -With less than the Minimum Channels

OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. SALEM -UNIT 2 3/4 3-22 Amendment No. 24 TABLE 3.3-3 (Continued)

ACTION 19 -With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within hou. G b. The Minimum Channels OPERABLE requirements is met; -~I.4E phowevere:

4ddita1 channel may be bypassed for up to hou for surveillance testing per Specification 4.3.2.1.

A OF OT*6 CAIAJL ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels 2 1925 manual block of safety psig. injection actuation on low pressurizer pressure.

P-12 With 3 of 4 Tavg channels P-12 prevents or defeats 5450F. manual block of safety injection actuation high steam line flow and low steam line pressure.

With 2 of 4 Tavg channels Allows manual block of < 5410F. safety injection actuation on high steam line flow and low steam line pressure.

Causes steam line isolation cESTO~k 7-rS 1OAdP6ZAt C L on high steam flow. Affects IMOP~AL 15,W 'Ad.MO. steam dump blocks.

HO& Of-, -T~e- AAXcT ACTION 20 -With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY withinv 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to +'hour for surveillance testing provided the other channel is OPERABLE.

ACTION 21 -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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 22 -With the number of OPERABLE channels one less than the Minimum Channels

OPERABLE, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST. ACTION 23 -With the Number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONS of L.C.O. 3.7.1.2 apply. SALEM -UNIT 2 3/4 3-23 Amendment No. 24 S)TA& 3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH m CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE t FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation N.A. N.A. R 1, 2, 3, 4 b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3, 4 c. Containment Pressure--High S R -+(3) 1, 2, 3 d. Pressurizer Pressure--Low S R +- 1, 2, 3 e. Differential Pressure Between S R Q 1 1, 2, 3 Steam Lines--High

f. Steam Flow in Two Steam Lines-- S R -M- 1, 2, 3 High coincident with Tavg--Low Low or Steam Line Pressure--Low

2. CONTAINMENT SPRAY a. Manual Initiation N.A. N.A. R 1, 2, 3, 4 b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3, 4 c. Containment Pressure--High-High S R )+(3) 1, 2, 3 TABLE 4.3-2@tinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED

3. CONTAINMENT ISOLATION

a. Phase "A" Isolation

1) Manual N.A. N.A. R 1, 2, 3, 4 2) From Safety Injection N.A. N.A. M(2) 1, 2, 3, 4 Automatic Actuation Logic b. Phase "B" Isolation

1) Manual N.A. N.A. R 1, 2, 3, 4 2) Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3, 4 3) Containment Pressure--

S R G 41+3) 1, 2, 3 High-High

c. Containment Ventilation Isolation

1) Manual N.A. N.A. R 1, 2, 3, 4 2) Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3, 4 3) Containment Radioactivity

-- Per table 4.3-3 High 0 (11 TABLE 4.3O ontinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE m FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

4. STEAM LINE ISOLATION

a. Manual N.A. N.A. R 1, 2, 3 b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3 c. Containment Pressure--

S R -M-(3) 1, 2, 3 High-High

d. Steam Flow in Two Steam S R 1 -1, 2, 3 Lines--High Coincident with Tavg--Low or Steam Line Pressure--Low

5. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water S R Q -M 1, 2, 3 Level--High-High W 6. SAFEGUARDS EQUIPMENT Ln CONTROL SYSTEM (SEC) LOGIC a. Inputs N.A. N.A. M 1, 2, 3, 4 b. Logic, Timing and N.A. N.A. M(1) 1, 2, 3, 4 Outputs 7. UNDERVOLTAGE, VITAL BUS (D a. Loss of Voltage S R M 1, 2, 3 b. Sustained Degraded Voltage S R M 1, 2, 3 O-TABLE 4. ontinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

> FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

8. AUXILIARY FEEDWATER

a. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3 b. Manual Initiation N.A. N.A. M(5) 1, 2, 3 c. Steam Generator Water S R Q 41 1, 2, 3 Level--Low-Low

d. Undervoltage

-RCP S R Q +t- 1, 2 e. S.I. See 1 above (All S.I. surveillance requirements)

f. Trip of Main N.A. N.A. S/U(4) 1, 2 Feedwater Pumps 9. SEMIAUTOMATIC TRANSFER TO RECIRCULATION

a. RWST Low Level S R Q M 1, 2, 3 b. Automatic Initiation Logic N.A. N.A. N.A. 1, 2, 3, 4 O (D rt 0)

ATTACHMENT B3 Markup of Salem Unit 2 Technical Specification 3/4.3.1 and 3/4.3.2 Bases.

ATTACHMENT B3 INSERT 1: New Bases Paragraph

1. 1 (Add to the existing paragraph).

... and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation and, 3) sufficient system functions capability is available from diverse parameters.

INSERT 2: New Bases Paragraph

1. 2 (Add to the existing paragraph).

Specified surveillance intervals and surveillance and maintenance outage times have been determined 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. Surveillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.

3/.4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and interlocks ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,

2) the specified coincidence logic4e.ma4~tainzd,

) ufznt redundan-mrtczdt rnt zhrrlt b AOO ju'w eut ef zizrviee fer testing er nmcintzrenne, and 4) suffizizrnt system fu9 iza eapabil.Lty ise available fer prtet-i..

and ESP dive..c~rs-e 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 performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

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 offsite test measurements or 2) utilizing replacement sensors with certified response times. 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

SALEM -UNIT 2 B 3/4 3-1