Text

Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages
	ML091470321
Person / Time
Site:	Vermont Yankee
Issue date:	05/20/2009
From:	Michael Colomb; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BVY 09-035
	Download: ML091470321 (60)
	v • d • e

S0Entergy-Entergy Nuclear Operations, Inc.Vermont Yankee P.O. Box 0250 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 09-035 May 20, 2009 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

REFERENCES:

Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28 1. Letter, VYNPS to USNRC, 'Technical Specification Proposed Change No. 273 Instrumentation Technical Specifications," BVY 08-001, dated February 12, 2008

Dear Sir or Madam:

In Reference (1), Entergy Nuclear Operations Inc. (ENO) submitted a proposed change to the instrumentation sections of the Vermont Yankee Operating License Technical Specifications (TS). Attachment 1 to this submittal provides the final TS pages that have been updated to reflect all supplements.

In addition, during final review, two minor editorial changes were made to accurately reflect the location of information.

These were: " Table of Contents, page "i", was revised to reflect that the degraded grid protection system specifications start on page 68 versus page 67 previously identified.

A blank page was inserted as page 28 to make the TS Bases for Section 3.1 start on page 29 as noted on the Table of Contents.This supplement to the original license amendment request does not change the scope or conclusions in the original application, nor does it change ENO's determination of no significant hazards consideration.

This letter contains no new regulatory commitments.

Should you have any questions or require additional information concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.,4oof BVY 09-035 / Page 2 of 2 I declare under penalty of perjury, that the foregoing is true and accurate.

Executed on May 20, 2009.Sincerely,

Attachment:

1. Final Technical Specification Pages cc: Mr. Samuel J. Collins (w/o Attachments)

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2A Washington, DC 20555 USNRC Resident Inspector (w/o Attachments)

Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, Vermont 05620-2601 Docket 50-271 BVY 09-ý035 Attachment 1 Technical Specification Proposed Change No. 273, Supplement 8 Vermont Yankee Nuclear Power Station Final Technical Specification Pages VYNPS TABLE OF CONTENTS Page No.1.0 DEFINITIONS

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1 LIMITING SAFETY SYSTEM SETTING SAFETY LIMITS 1.1 FUEL CLADDING INTEGRITY

.......................

1.2 REACTOR COOLANT SYSTEM .........................

LIMITING CONDITIONS OF OPERATION 6 ...2.1 18.. .2.2 Page No. SURVEILLANCE 3.0 LIMITING CONDITIONS OF OPERATION and SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...

BASES 3.1 REACTOR PROTECTION SYSTEM .....................

19a 19c 4.0 BASES 3.2 PROTECTIVE INSTRUMENT SYSTEMS .................

A.B.C.D.E.F.G.H.I.J.K.L.Emergency Core Cooling System .............

Primary Containment Isolation

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Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation

................................(Deleted)

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Control Rod Block Actuation

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Mechanical Vacuum Pump Isolation Instrumentation

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Post-Accident Monitoring Instrumentation..(Deleted)

.................................

Recirculation Pump Trip Instrumentation

...........................(Deleted)

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Degraded Grid Protective System ..........

Reactor Core Isolation Cooling System Actuation

.................................

20 29 34 34 43 50 54 54 58 60 64 64 64 68 72 75 81 81 82 85 87 88 89... 4.1... 4.2 A* ..B C D E F G H I J K L BASES 3.3 CONTROL ROD SYSTEM ............................

A. Reactivity Limitations

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B. Control Rods ................................

C. Scram Insertion Times .....................

D. Control Rod Accumulators

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E. Reactivity Anomalies

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... 4.3 A B C D E BASES Amendment No.4-3, 4&, 3-8, 44, 4-64, --9-,, 24, -4,--i-VYNPS 1.0 DEFINITIONS Z. Surveillance Interval -Relocated to Specification 4.0.1.AA. Deleted BB. Source Check -The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.CC. Dose Equivalent 1-131 -The dose equivalent 1-131 shall be that concentration of 1-131 (microcurie/gram) which alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134 and 1-135 actually present. The dose.conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11,"Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988; FGR 12,"External Exposure to Radionuclides In Air, Water, and Soil," 1993; or NRC Regulatory Guide 1.109, Revision 1, October 1977.DD. Deleted EE. Deleted FF. Deleted GG. Deleted HH. Deleted II. Deleted JJ. Deleted KK. Deleted LL. Deleted MM. Deleted NN. Core Operating Limits Report -The Core Operating Limits Report is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.6.C.Plant operation within these operating limits is addressed in individual specifications.

00. Reactor Protection System (RPS) Response Time -RPS Response Time shall be the time from the opening of the sensor contact up to and including the.opening of the scram solenoid relay.Amendment No. 4-4, 24, -44, 44, 6-4, -4. 446-, 4-5-46, 4-64, 4-44-, 4, 4-94, £2-2-, 2-2-4 5 VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING For no combination of loop recirculation flow rateand core thermal power shall the APRM flux scram trip setting be allowed to exceed 120%of rated thermal power.b. Flux Scram Trip Setting (Refuel or Startup/Hot Standby Mode)In accordance with Table 3.1.1, when the reactor mode switch is in the REFUEL position or the STARTUP/HOT STANDBY position, average power range monitor (APRM)scram shall be set down to less than or equal to 15% of rated neutron flux. The IRM flux scram setting shall be set at less than or equal to 120/125 of full scale.B. Deleted C. Reactor low water level scram setting shall be at least 127 inches above the top of the enriched fuel.Amendment No. 4-4, -64, -, 4, 94, --84, ?44 8 VYNPS 1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING D. Reactor low-low water level Emergency Core Cooling System (ECCS) initiation shall be 82.5 inches above the top of the enriched fuel.E. When operating at > 25% of Rated Thermal Power, turbine stop valve scram shall be < 10% valve closure from full open.F. When operating at > 25% of Rated Thermal Power, turbine control valve fast closure scram shall be actuation of the turbine control valve fast closure relay.G. Main steam line isolation valve closure scram shall be 10%valve closure from full open.H. Main steam line low pressure initiation of main steam line isolation valve closure shall be 800 psig.Amendment No. 4&9, .-4, -I- 4 10 VYNPS 3.1 LIMITING CONDITIONS FOR OPERATION 3.1 REACTOR PROTECTION SYSTEM (RPS)Applicability:

Applies to the operability of plant instrumentation and control systems required for reactor safety.Objective:

To specify the limits imposed on plant operation by those instrument and control systems required for reactor safety.Specification:

A. The RPS instrumentation for each Trip Function in Table 3.1.1 shall be operable in accordance with Table 3.1.1.4.1 SURVEILLANCE REQUIREMENTS 4.1 REACTOR PROTECTION SYSTEM (RPS)Applicability:

Applies to the surveillance of the plant instrumentation and control systems required for reactor safety.Objective:

To specify the type and frequency of surveillance to be applied to those instrument and control systems required for reactor safety.Specification:

A.1 RPS instrumentation shall be checked, functionally tested and calibrated as indicated in Table 4.1.1.When an RPS channel is placed in an inoperable status solely for the performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains RPS trip capability.

2. Exercise each automatic scram contactor once every week using the RPS channel test switches or by performing a Functional Test of any automatic RPS Trip Function.3. Verify RPS Response Time is 50 milliseconds for each automatic RPS Trip Function once every Operating Cycle.Amendment No. 4&1, 4-64, 4-&-, 2--4, p-1-2 20 VYNPS 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS

4. Perform a Logic System Functional Test of RPS instrumentation Trip Functions once every Operating Cycle.Amendment No.4-64 20a VYNPS Table 3.1.1 (page 1 of 3)Reactor Protection System Instrumentation ACTIONS WHEN REQUIRED REQUIRED ACTIONS APPLICABLE MODES CHANNELS CHANNELS REFERENCED OR OTHER SPECIFIED

'PER TRIP ARE FROM ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 1. Reactor Mode Switch in Shutdown 2. Manual Scram RUN, STARTUP/HOT STANDBY, Refuel Refuel (b)RUN, STARTUP/HOT STANDBY, Refuel(a)Refuel (b)1 1 Note 1 Note 1 Note 1 Note 1 Note 2.a Note 2.d Note 2.. a Note 2.d NA NA NA NA 3. Intermediate Range Monitors (IRMs)a. High Flux STARTUP/HOT STANDBY, Refuel(a)Refuel (b)STARTUP/HOT STANDBY, Refuel(a)Refuel (b)2 2 2 2 Note 1 Note 1 Note 1 Note 1 Note 2.a 120/125 Note 2.d 120/125 b. Inop Note 2.a Note 2.d NA NA (a) With reactor coolant temperature

> 212 0 F.(b) With reactor coolant temperature 212*F and any control rod withdrawn from-a core cell containing one or more fuel assemblies.

Amendment No. 44 21 VYNPS Table 3.1.1 (page 2 of 3)Reactor Protection System Instrumentation ACTIONS WHEN REQUIRED REQUIRED ACTIONS APPLICABLE MODES CHANNELS CHANNELS REFERENCED OR OTHER SPECIFIED PER TRIP ARE FROM ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 4. Average Power.Range Monitors (APRMs)a. High Flux RUN 2 Note 1 Note 2.b (c)(Flow Bias)b. High Flux STARTUP/HOT 2 Note 1 Note 2.a 15%(Reduced)

STANDBY, Refuel(a)c. Inop RUN, STARTUP/HOT 2 Note 1 Note 2.a NA STANDBY, Refuel (a)(a) With reactor coolant temperature

> 212 0 F.(c) Two loop operation:

S 0.33W+ 50.45% for 0% < W 30.9%S 1.07W+ 27.23% for 30.9% < W 66.7%S 0.55W+ 62.34% for 66.7% < W 99.0%With a maximum of 117.0% power for W > 99.0%Single loop operation:

S 0.33W+ 48.00% for 0% < W 39.1%S 1.07W+ 19.01% for 39.1% < W 61.7%S 0.55W+ 51.22% for 61.7% < W 119.4%With a maximum of 117.0% power for W > 119.4%Amendment No. 4&4-21a VYNPS Table 3.1.1 (page 3 of 3)Reactor Protection System Instrumentation ACTIONS WHEN REQUIRED REQUIRED ACTIONS APPLICABLE MODES CHANNELS CHANNELS REFERENCED OR OTHER SPECIFIED PER TRIP ARE FROM ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 5. High Reactor RUN, STARTUP/HOT 2 Note 1 Note 2.a 1055 Pressure STANDBY, Refuel(a) psig 6. High Drywell RUN, STARTUP/HOT 2 Note 1 Note 2.a 2.5 Pressure STANDBY, Refuel(a) psigt 7. Reactor Low Water RUN, STARTUP/HOT 2 Note 1 Note 2.a 127.0 Level STANDBY, Refuel(a) inches 8. Scram Discharge RUN, STARTUP/HOT 2 per Note 1 Note 2.a .21.0 Volume High Level STANDBY, Refuel(a) volume gallons Refuel (b) 2 per Note 1 Note 2.d : 21.0 volume gallons 9. Main Steam Line RUN 8 Note 1 -Note 2.b 5 10%Isolation Valve valve.Closure closure 10. Turbine Control > 25% RATED 2 Note 1 Note 2.c (d)Valve Fast THERMAL POWER Closure ll.Turbine Stop > 25% RATED '4 Note 1 Note 2.c ! 10%Valve Closure THERMAL POWER valve closure (a) With reactor coolant temperature

> 212 0 F.(b) With reactor coolant temperature 212'F and any control rod- withdrawn from a core cell containing one or more fuel assemblies.(d) Channel signals for the turbine control valve fast closure trip shall be derived from the same event or events which cause the control valve fast closure.Amendment No. 4-64 22 VYNPS Table 3.1.1 ACTION Notes 1. With one or more required Reactor Protection System channels inoperable, take all of the applicable Actions in Notes l.a, l.b, and l.c below.a. With one or more Trip Functions with one or more required channels inoperable:

1) Place an inoperable channel for each Trip Function in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; or 2) Place the associated trip system in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .b. With one or more Trip Functions with one or more required channels inoperable in both trip systems: 1) Place an inoperable channel in one trip system in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or 2) Place one trip system in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .c. With one or more Trip Functions with Reactor Protection System trip capability not maintained:

1) Restore Reactor Protection System trip capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If any applicable -Action and associated completion time of Notes l.a, l.b, or l.c is not met, take the applicable Action of Note 2 below referenced in Table 3.1.1 for the channel.2. a. Place the reactor in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .b. Place the reactor in STARTUP/HOT STANDBY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .c. Reduce reactor power to < 25% Rated Thermal Power within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .d. Immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Amendment No. 1-64 23 VYNPS Table 4.1.1 (page 1 of 3)Reactor Protection System-Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

1. Reactor Mode Switch in Shutdown 2. Manual Scram 3. Intermediate Range Monitors (IRMs)a. High Flux NA Each Refueling Outage NA Every 3 Months NA NA Once/Day, Within 31 Days Before entering (a) STARTUP/HOT STANDBY(b) and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling NA Within 31 Days Before. entering STARTUP/HOT STANDBY(b) and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days DuringRefueling Once/Operating Cycle (b),(c)b. Inop NA 4. Average Power Range Monitors (APRMs)a. High Flux (Flow Bias)NA Every 3 Months Every 7 Days for Output Signal by Heat Balance(d)

Every 3 Months(e)Each Refueling Outage for Flow Bias, Every 2000 MWD/T Averaige Core Exposure for LPRMs using TIP System (a) IRM and Source Range Monitor channels shall be determined to overlap during each startup after entering STARTUP/HOT STANDBY MODE and IRM and APRM channels shall be determined to overlap during each controlled shutdown, if not performed in the previous 7 days.(b) Not required to be completed when entering STARTUP/HOT STANDBY MODE from RUN MODE until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering STARTUP/HOT STANDBY MODE.(c) Neutron detectors are excluded.(d) .Not required to be completed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor power is 23%Rated Thermal Power.(e) Trip unit calibration only.Amendment No 1-64 2A VYNPS Table 4.1.1 (page 2 of 3)Reactor Protection System Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

4. APRMs (continued)

b. High Flux (Reduced)(a) Within 7 Days Before entering STARTUP/HOT STANDBY(b) and Every 7 Days During STARTUP/HOT STANDBY, Every 7 Days During Refueling c. Inop NA 5. High Reactor Pressure 6. High Drywell Pressure 7. Reactor Low Water Level 8. Scram Discharge Volume High Level 9. Main Steam Line Isolation Valve Closure 10.Turbine Control Valve Fast Closure a. First Stage Turbine Pressure Permissive Once/Day NA Every 3 Months Every 3 Months Every 3 Months Every 3 Months Every 3 Months Once/Day NA Within 7 Days Before entering STARTUP/HOT STANDBY'bc),'

ee) and Every 7 Days During STARTUP/HOT STANDBY(c), (e)Every 7 Days During Refueling(c)

,(e)NA Every 3 Months(e)Once/Operating Cycle Every 3 Months(e)Once/Operating Cycle Every 3 Months(e)Once/Operating Cycle Every 3 Months(e)Once/Operating Cycle Each Refueling Outage Every 3 Months Every 6 Months and prior to entering STARTUP/HOT STANDBY for plant startup after Refueling NA Every 3 Months NA NA Every 3 Months Every 6 Months (a) IRM and Source Range Monitor channels shall be determined to overlap during each startup after entering STARTUP/HOT STANDBY MODE and IRM and APRM channels shall be determined to overlap during each controlled shutdown, if not performed in the previous 7 days.(b) Not required to be completed when entering STARTUP/HOT STANDBY MODE from RUN MODE until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering STARTUP/HOT STANDBY MODE.(c) Neutron detectors are excluded.(e). Trip unit calibration only.Amendment No. -642 25 VYNPS Table 4.1.1 (page 3 of 3)Reactor Protection System Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION li.Turbine Stop NA Every 3 Months Each Refueling Valve Closure Outage a. First NA Every 6 Months Every 6 Months and Stage prior to entering Turbine STARTUP/HOT Pressure STANDBY for plant Permissive startup after Refueling Amendment No. 1-64 26 VYNPS I This page intentionally left blank Amendment No.27 VYNPS This page intentionally left blank Amendment No.28 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 3.2 PROTECTIVE INSTRUMENT SYSTEMS Applicability:

Applies to the operational status of the plant instrumentation systems which initiate and control a protective function.Objective:

To assure the operability of protective instrumentation systems.Specification:

A. Emergency Core Cooling System (ECCS)The ECCS instrumentation for each Trip Function in Table 3.2.1 shall be operable in accordance with Table 3.2.1.4.2 PROTECTIVE INSTRUMENT SYSTEMS Applicability:

Applies to the surveillance requirements of the instrumentation systems which initiate and control a protective function.Objective:

To verify the operability of protective instrumentation systems.Specification:

A. Emergency Core Cooling System (ECCS)1. ECCS instrumentation shall be checked, functionally tested and calibrated as indicated in Table 4.2.1.When an ECCS instrumentation channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed as follows: (a)for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Function 3.d; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Functions other than 3.d provided the associated Trip Function or redundant Trip Function maintains ECCS initiation capability.

2. Perform a Logic System Functional Test of ECCS instrumentation Trip Functions once every Operating Cycle.Amendment No.4434 34 VYNPS Table 3.2.1 (page 1 of 4)Emergency Core Cooling System Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER TRIP ARE TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE TRIP SETTING 1. Core Spray System a. High Drywell Pressure b. Low-Low Reactor Vessel Water Level c. Low Reactor Pressure (Initiation)

d. Low Reactor Pressure (System Ready and Valve Permissive)

e. Pump Start Time Delay f. Pump Discharge Pressure g. Auxiliary Power Monitor h. Pump Bus Power Monitor RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (e)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b), (e)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a),(b)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b)RUN, STARTUP/HOT STANDBY(c), HOT SHUTDOWN(C)

Refuel (c)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a), (b)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b)2 2 1 2 1 2 per PUMP Note 1 2.5 psig Note 1 82.5 inches Note 2 300 psig and 350 psig Note 2 300 psig and 350 psig Note 2 8 seconds and 10 seconds Note 8 100 psig 1 1 Note 2 Note 2 NA NA (a) With reactor coolant temperature

> 212 'F.(b) When associated ECCS subsystem is required to be operable per specification 3.5.(c) With reactor steam pressure > 150 psig.(e) Required to initiate the emergency diesel generators when core spray is required to be operable per specification 3.5.Amendment No. 4-64 35 VYNPS Table 3.2.1 (page 2 of 4)Emergency Core Cooling System Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER TRIP ARE TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE TRIP SETTING 2. Low Pressure Coolant Injection (LPCI)System a. Low Reactor Pressure (Initiation)

b. High Drywell Pressure (Initiation)

c. Low-Low Reactor Vessel Water Level d. Reactor Vessel Shroud Level e. LPCI B and C Pump Start Time Delay f. RHR Pump Discharge Pressure g. High Drywell Pressure (Containment Spray Permissive)

h. Low Reactor Pressure (System Ready and Valve Permissive)

RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a) (b)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a). (b)RUN, STARTUP/HOT STANDBY(c), HOT SHUTDOWN(C), Refuel(c)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a), (b)1 2 2 per pump 2 2 Note 2 300 psig and 350 psig Note 1 2.5 psig Note 1 82.5 inches Note 3 2/3 core height Note 2 3 seconds and 5 seconds Note 8 1 100 psig Note 3 2.5 psig Note 2 300 psig and 350 psig (a) With reactor coolant temperature

> 212 'F.(b) When associated ECCS subsystem is required to be operable per specification 3.5.(c) With reactor steam pressure > 150 psig.Amendment No. -44 36 VYNPS Table 3.2.1 (page 3 of 4)Emergency Core Cooling System Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER TRIP ARE TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE TRIP SETTING 2. LPCI System (Continued)

i. Auxiliary RUN, STARTUP/HOT 1 Note 2 NA Power Monitor STANDBY, HOT SHUTDOWN, Refuel(a), (b)j. Pump Bus RUN, STARTUP/HOT 1 Note 2 NA Power Monitor STANDBY, HOT SHUTDOWN, Refuel (a), (b)3. High Pressure Coolant Injection (HPCI)System a. Low-Low RUN, STARTUP/HOT 2 Note 4 82.5 inches Reactor STANDBY(C), HOT Vessel Water SHUTDOWN'c', Refuel(c:)

Level b. Low RUN, STARTUP/HOT 2 Notes _ 4.2 4%{(d Condensate STANDBY(c', HOT 5,9,10 Storage Tank SHUTDOWN(c), Refuel(c)Water Level c. High Drywell RUN, STARTUP/HOT 2 Note 4 < 2.5 psig Pressure STANDBY(c) , HOT SHUTDOWN(c), Refuel(c)d. High Reactor RUN, STARTUP/HOT 2 Note 6. 177 inches Vessel Water STANDBY c), HOT Level SHUTDOWN(c), Refuel(c)(a) With reactor coolant temperature

> 212 OF.(b) When associated ECCS subsystem is required to be operable per specification 3.5.(c) With reactor steam pressure > 150 psig.(d) Percent of instrument span.Amendment No.44 37 VYNPS Table 3.2.1 (page 4 of 4)Emergency Core Cooling System Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER TRIP ARE TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE TRIP SETTING 4. Automatic Depressurization System (ADS)a. Low-Low RUN, STARTUP/HOT 2 Note 7 82.5 inches Reactor STANDBY(c), HOT Vessel Water SHUTDOWN(c), Refuel(c)Level b. High Drywell, RUN, STARTUP/HOT 2' Note 7 2.5 psig Pressure STANDBY(c), HOT SHUTDOWN(c), Refuel(c)c. Time Delay RUN, STARTUP/HOT 1 Note 8 120 seconds STANDBY(c), HOT SHUTDOWN(c), Refuel(c)d. Sustained RUN, STARTUP/HOT 2 Note 8 8 minutes Low-Low STANDBY(c), HOT Reactor SHUTDOWN(C), Refuel(c)Vessel Water Level Time Delay (c) With reactor steam pressure > 150 psig.Amendment No. 44 38 VYNPS Table 3.2.1 ACTION Notes 1. With one or more channels inoperable for ECCS instrumentation Trip Functions l.a, l.b, 2.b and 2.c: a. Declare the associated systems inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of initiation capability for feature(s) in both divisions; and b. Place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note l.a or l.b is not met, immediately declare associated systems inoperable.

2. With one or more channels inoperable for ECCS instrumentation Trip Functions l.c, l.d, l.e, l.g, l.h, 2.a,, 2.e, 2.h, 2.i and 2.j: a. Declare the associated systems inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of initiation capability for feature(s) in both divisions; and b. Restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note 2.a or 2.b is not met, immediately declare associated systems inoperable.

3. With one or more channels inoperable for ECCS instrumentation Trip Functions 2.d and 2.g: a. For Trip Function 2.g only, declare the associated system inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of LPCI initiation capability; and b. For Trip Function 2.g, place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .c. For Trip Function 2.d restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note 3.a, 3.b or 3.c is not met, immediately declare associated systems inoperable.

4. With one or more channels inoperable for ECCS instrumentation Trip Functions 3.a and 3.c: a. Declare the HPCI System inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI System initiation capability; and b. Place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note 4.a or 4.b is not met, immediately declare HPCI System inoperable.

5. With one or more channels inoperable for ECCS instrumentation Trip Function 3.b: a. Declare the. HPCI System inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI initiation capability when HPCI System suction is aligned to the Condensate Storage Tank; and b. Place any inoperable channel in trip or align HPCI System suction to the suppression pool within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note 5.a or 5.b is not met, immediately declare the HPCI System inoperable.

Amendment No. -1 3 39 VYNPS Table 3.2.1 ACTION Notes (Continued)

6. With one or more channels inoperable for ECCS instrumentation Trip Function 3.d: a. Restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If the Action and associated completion time of Note 6.a is not met, immediately declare the HPCI System inoperable.

7. With one or more channels inoperable for ECCS instrumentation Trip Functions 4.a and 4.b: a. Declare ADS inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems; and b. Place any inoperable channel in trip within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from discovery of the inoperable channel concurrent with HPCI System or RCIC System inoperable, and c. Place any inoperable channel in trip within 8 days.If any applicable Action and associated completion time of Note 7.a, 7.b or 7.c is not met, immediately declare ADS inoperable.

8. With one or more channels inoperable for ECCS instrumentation Trip Functions l.f, 2.f, 4.c and 4.d: a. Declare ADS inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems; and b. Restore any inoperable channel to operable status within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from discovery of the inoperable channel concurrent with HPCI System or RCIC System inoperable, and c. Restore any inoperable channel to operable status within 8 days.If any applicable Action and associated completion time of Note 8.a, 8.b or 8.c is not met, immediately declare ADS inoperable.

9. If the as-found channel setpoint *is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.10. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint at the completion of the surveillance; otherwise, the channel shall be declared inoperable.

Setpoints more conservative than the Limiting Trip Setpoint are acceptable provided that as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures to confirm channel performance.

The methodologies used to determine the as-found and the as-left tolerances are specified in the Vermont Yankee Setpoint Program Manual.Amendment No. 4-64 40 VYNPS Table 4.2.1 (page 1 of 2)Core Cooling System Instrumentation Emergency Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

1. Core Spray System a. High Drywell Pressure b. Low-Low Reactor Vessel Water Level c. Low Reactor Pressure (Initiation)

d. Low Reactor Pressure (System Ready and Valve Permissive)

Once/Day Every 3 Months Once/Day NA NA Every 3 Months Every 3 Months Every 3 Months Every 3 Monthsla)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Once/Operating Cycle e. Pump Start Time Delay f. Pump Discharge Pressure g. Auxiliary Power Monitor h. Pump Bus Power Monitor NA NA NA Every 3 Months Every 3 Months Once/Day Every 3 Months Once/Day Every 3 Months NA NA 2. Low Pressure Coolant Injection (LPCI) System a. Low Reactor Pressure (Initiation)

b. High Drywell Pressure (Initiation)

c. Low-Low Reactor'Vessel Water Level d. Reactor Vessel Shroud Level e. LPCI B and C Pump Start Time Delay f. RHR Pump Discharge Pressure g. High Drywell Pressure (Containment Spray Permissive)

NA Every 3 Months Once/Day Every 3 Months Once/Day Every 3 Months NA NA NA NA Every 3 Months Every 3 Months aW Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Once/Operating Cycle Every 3 Months Every 3 Months(a)Once/Operating Cycle NA Every 3 Months Every 3 Months (a) Trip unit calibration only.Amendment No. 4-64 41 VYNPS Emergency Table 4.2.1 (page 2 of 2)Core Cooling System Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

2. LPCI System (Continued)

h. Low Reactor Pressure (System Ready and Valve Permissive)

NA Every 3 Months Every 3 Months(a)Once/Operating Cycle i. Auxiliary Power Monitor j. Pump Bus Power Monitor Once/Day Every 3 Months Once/Day Every 3 Months NA NA 3. High Pressure Coolant Injection (HPCI) System a. Low-Low Reactor Vessel Water Level b. Low Condensate Storage Tank Water Level c. High Drywell Pressure d. High Reactor Vessel Water Level 4. Automatic Depressurization System (ADS)a. Low-Low Reactor Vessel Water Level b. High Drywell Pressure c. Time Delay d. Sustained Low-Low Reactor Vessel Water Level Time Delay Once/Day Every 3 Months NA Every 3 Months Every 3 Months(a)Once/Operating Cycle Every 3 Months Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Once/Day Every 3 Months NA Every 3 Months Once/Day Every 3 Months Once/Day Every 3 Months Every 3*Months(a)

Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Once/Operating Cycle Once/Operating Cycle NA NA NA NA (a) Trip unit calibration only.Amendment No. 4-64 42 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 3.2 PROTECTIVE INSTRUMENT SYSTEMS B. Primary Containment Isolation 4.2 PROTECTIVE INSTRUMENT.SYSTEMS The primary containment isolation instrumentation for each Trip Function in Table 3.2.2 shall be operable in accordance with Table 3.2.2.B. Primary Containment Isolation 1. The primary containment isolation instrumentation shall be checked, functionally tested and calibrated as indicated in Table 4.2.2.When a primary containment isolation channel, and/or the affected primary containment isolation valve, is placed in an inoperable status solely for performance of required instrumentation surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains isolation capability.

2. Perform a Logic System Functional Test of Primary Containment isolation instrumentation Trip Functions once every Operating Cycle.Amendment No. 1-64 43 VYNPS Table 3.2.2 (page 1 of 3)Primary Containment Isolation Instrumentation ACTIONS WHEN ACTIONS APPLICABLE MODES REQUIRED REQUIRED REFERENCED OR OTHER CHANNELS CHANNELS FROM SPECIFIED PER TRIP ARE ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 1. Main Steam Line Isolation a.Low-Low Reactor Vessel Water Level b.High Main Steam Line Area Temperature RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a)2 8 Note 1 Note 2.a 82.5 inches Note 1 Note 2.a 5 196 0 F for channels monitoring outside steam tunnel and 5 200 0 F for channels monitoring inside steam tunnel Note 1 Note 2.a 5 140% of.rated flow Note 1 Note 2.c 800 psig Note 1 Note 2.a 5 40% of rated flow Note 1 Note 2.a 5 12 inches Hg absolute c. High Main Steam Line Flow d.Low Main Steam Line Pressure e.High Main Steam Line Flow -Not in RUN f.Condenser Low Vacuum RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)2 per main steam line RUN STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a)RUN, STARTUP/HOT STANDBY (b), HOT SHUTDOWN (b), Refuel(a)

,(b)2 2 2 2. Primary Containment Isolation a.Low Reactor Vessel Water Level b.High Drywell Pressure RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)2 2 Note 1 Note 2.b 127.0 inches Note 1 Note 2.b 5 2.5 psig (a) With reactor coolant temperature

> 212 OF.(b) With any turbine stop valve or turbine bypass valve not closed.Amendment No. 4-64 44 VYNPS Table 3.2.2 (page 2 Primary Containment Isolation of 3)Instrumentation ACTIONS WHEN ACTIONS APPLICABLE MODES REQUIRED REQUIRED REFERENCED OR OTHER CHANNELS CHANNELS FROM SPECIFIED PER TRIP ARE ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 3. High Pressure Coolant Injection (HPCI) System Isolation a.High Steam Line Space Temperature b.High Steam Line d/p (Steam Line Break)c.Low Steam Supply Pressure d.High Main Steam Line Tunnel Temperature e.High Main Steam*Line Tunnel Temperature Time Delay 4. Reactor Core Isolation Cooling (RCIC) System Isolation a.High Main Steam Line Tunnel Temperature b.High Main Steam Line Tunnel Temperature Time Delay c.High Steam Line Space Temperature RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel(a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)6 4 Note 1 Note 2.d 196 OF Note 1 Note 2.cd 195 inches of water Note 1 Note 2.d 70 psig Note 1 Note 2.d 200 OF Note 1 Note 2.d 35 minutes 2 1 RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (a)2 6 Note 1 Note 1 Note 1 Note 2.d 200 OF Note 2.d 35 minutes Note 2.d 196 OF (a) With reactor coolant temperature

> 212 OF Amendment No. 4-644 45 VYNPS Table 3.2.2 (page 3 of 3)Primary Containment Isolation Instrumentation ACTIONS WHEN ACTIONS APPLICABLE MODES REQUIRED REQUIRED REFERENCED OR OTHER CHANNELS CHANNELS FROM SPECIFIED PER TRIP ARE ACTION TRIP TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE NOTE 1 SETTING 4. RCIC System Isolation (Continued) d.High Steam Line RUN, STARTUP/HOT 1 Note 1 Note 2.d 195 d/p (Steam Line STANDBY, HOT inches of Break) SHUTDOWN, Refuel(a) water e.High Steam Line RUN, STARTUP/HOT 1 Note 1 Note 2.d t 3 seconds.d/p Time Delay STANDBY, HOT and SHUTDOWN, Refuel(a)

< 7 seconds f.Low Steam RUN, STARTUP/HOT 4 Note 1 Note 2.d 50 psig Supply Pressure STANDBY, HOT SHUTDOWN, Refuel(a)5. Residual Heat Removal Shutdown Cooling Isolation a.High Reactor RUN, STARTUP/HOT 1 Note 1 Note 2.d 150 psig Pressure STANDBY, HOT SHUTDOWN, Refuel (a)(a) With reactor coolant temperature

> 212 OF.Amendment No. 4-64 46 VYNPS " Table 3.2.2 ACTION Notes 1. With one or more required Primary Containment Isolation Instrumentation channels inoperable, take all of the applicable Actions in Notes l.a and l.b below.a. With one or more Trip Functions with one or more required channels inoperable:

1) For Trip Functions 2.a and 2.b, place any inoperable channel in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; and 2) For Trip Functions 3.e, 4.b, and 4.e, restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; and 3) For all other Trip Functions, place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .b. With one or more Trip Functions with isolation capability not maintained:

1) Restore isolation capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .Penetration flow paths, isolated as a result of complying with the above Actions, may be unisolated intermittently under administrative controls.If any applicable and associated completion time of Note l.a or l.b is not met, take the applicable Actions of Note 2 below and referenced in Table 3.2.2 for the channel.2. a. Isolate the associated Main Steam Line within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (penetration flow paths may be unisolated intermittently under administrative control);

or Place the reactor in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and place the reactor in COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .b. Place the reactor in COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .c. Place the reactor in STARTUP/HOT STANDBY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .d. Isolate the affected penetration flow path within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and comply with specifications 3.5 and 3.7 (penetration flow paths may be unisolated intermittently under administrative control).Amendment No.4-4 47 VYNPS Table 4.2.2 (page 1 of 2)Primary Containment Isolation Instrumentation Tests and Frequencies TRIP FUNCTION 1. Main Steam Line Isolation a. Low-Low Reactor Vessel Water Level b. High Main Steam Line Area Temperature

c. High Main Steam Line Flow d. Low Main Steam Line Pressure e. High Main Steam Line Flow -Not in RUN f. Condenser Low Vacuum 2. Primary Containment Isolation a. Low Reactor Vessel Water Level b. High Drywell Pressure 3. High Pressure Coolant Injection (HPCI) System Isolation a. High Steam Line Space Temperature

b. High Steam Line d/p (Steam Line Break)c. Low Steam Supply Pressure d. High Main Steam Line Tunnel Temperature

e. High Main Steam Line Tunnel Temperature Time Delay CHECK FUNCTIONAL TEST CALIBRATION Once/Day NA Once/Day NA Once/Day NA NA Once/Day NA NA NA NA NA Every Every Every Every Every Every Every Every Every Every Every Every 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months 3 Months NA Every 3 Months(a)Once/Operating Cycle Each Refueling Outage Every 3 Months(a)Once/Operating Cycle Every 3 Months Every 3 Months(a)Once/Operating Cycle Every 3 Months Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Each Refueling Outage Every 3 Months Every 3 Months Each Refueling Outage Once/Operating Cycle (a) Trip unit calibration only.Amendment No. 4-64 48 VYNPS Table 4.2.2 (page 2 of 2)Primary Containment Isolation Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

4. Reactor Core Isolation Cooling (RCIC) System Isolation a. High Main Steam Line NA Every 3 Months Each Refueling Outage Tunnel Temperature

b. High Main Steam Line NA NA Once/Operating Cycle Tunnel Temperature Time Delay c. High Steam Line NA Every 3 Months Each Refueling Outage Space Temperature

d. High Steam Line d/p NA Every 3 Months Every 3 Months (Steam Line Break)e. High Steam Line d/p NA Every 3 Months Every 3 Months (Steam Line Break)Time Delay f. Low Steam Supply NA Every 3 Months Every 3 Months Pressure 5. Residual Heat Removal Shutdown Cooling Isolation a. High Reactor NA Every 3 Months Every 3 Months Pressure Amendment No. 4-6-4 49 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 4.2 PROTECTIVE INSTRUMENT SYSTEMS 3.2 PROTECTIVE INSTRUMENT SYSTEMS C. Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation The reactor building ventilation isolation and Standby Gas Treatment System initiation instrumentation for each Trip Function in Table 3.2.3 shall be operable in accordance with Table 3.2.3.C. Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation

1. The reactor building ventilation isolation and Standby Gas Treatment System initiation instrumentation shall be checked, functionally tested and calibrated as indicated in Table 4.2.3.When a channel is placed in an inoperable status solely for performance of required instrumentation surveillances, entry into the associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains reactor building ventilation isolation capability and Standby Gas Treatment System initiation capability.

2. Perform a Logic System Functional Test of reactor building ventilation isolation and Standby Gas TreatmentýSystem initiation instrumentation Trip Functions once every Operating Cycle.Amendment No. 4 50 50 VYNPS Table 3.2.3 (page 1 of 1)Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER TRIP ARE TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE TRIP SETTING 1. Low Reactor RUN, STARTUP/HOT 2 Note 1 127.0 inches Vessel Water STANDBY, HOT SHUTDOWN, Level Refuel(a), (b)2. High Drywell RUN, STARTUP/HOT 2 Note 1 2.5 psig Pressure STANDBY, HOT SHUTDOWN, Refuel (a)3. High Reactor RUN, STARTUP/HOT 1 Note 1 14 mR/hr Building STANDBY, HOT SHUTDOWN, Ventilation Refuel(a), (b), (c), (d)Radiation 4. High Refueling RUN, STARTUP/HOT 1 Note 1 1 100 mR/hr Floor Zone STANDBY, HOT SHUTDOWN, Radiation Refuel(a), (b), (c), (d)(a) With reactor coolant temperature

> 212 'F.(b) During operations with potential for draining the reactor vessel.(c) During movement of irradiated fuel assemblies or fuel cask in secondary containment.(d) During Alteration of the Reactor Core.Amendment No. 1-64 VYNPS Table 3.2.3 ACTION Note 1. With one or more required Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation Instrumentation channels inoperable, take all of the applicable Actions in Notes l.a and l.b below.a. With one or more Trip Functions with one or more required channels inoperable:

1) For Trip Functions 1 and 2, place any inoperable channel in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; and 2) For Trip Functions 3 and 4, place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .b. With one or more Trip Functions with isolation or initiation capability not maintained:

1) Restore isolation and initiation capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If any applicable Action and associated completion time of Note l.a or l.b is not met, isolate the Reactor Building Ventilation System and place the Standby Gas Treatment System in operation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .Amendment No. 164 52 VYNPS Table 4.2.3 (page 1 of 1)Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation Instrumentation Tests and Frequencies TRIP FUNCTION 1. Low Reactor Vessel Water Level 2. High Drywell Pressure 3. High Reactor Building Ventilation Radiation 4. High Refueling Floor Zone Radiation CHECK NA NA Once/Day Once/Day During Refueling FUNCTIONAL TEST Every 3 Months Every 3 Months Every 3 Months Every 3 Months CALIBRATION Every 3 Months(a)Once/Operating Cycle Every 3 Months(a)Once/Operating Cycle Every 3 Months Every 3 Months (a) Trip unit calibration only.Amendment No.-145 53 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS D. Deleted.E. Control Rod Block Actuation The control rod block instrumentation for each Trip Function in Table 3.2.5 shall be operable in accordance with Table 3.2.5.D. Deleted.E. Control Rod Block Actuation 1. The control rod block instrumentation shall be functionally tested and calibrated as indicated in Table 4.2.5.When a Rod Block Monitor channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains control rod block initiation capability.

Amendment No. 4, 4-6-45 54 VYNPS Table 3.2.5 (page 1 of 1)Control Rod Block Instrumentation ACTIONS WHEN APPLICABLE REQUIRED REQUIRED MODES OR OTHER CHANNELS CHANNELS SPECIFIED PER TRIP ARE TRIP SETTING TRIP FUNCTION CONDITIONS FUNCTION INOPERABLE

1. Rod Block Monitor a. Upscale (Flow Bias) > 30% RATED 2 Note 1 0.66(W)+N THERMAL POWER with a maximum as defined in the COLR(b)b. Downscale

> 30% RATED 2 Note 1 2/125 full THERMAL POWER scale c. Inop > 30% RATED 2 Note 1 NA THERMAL POWER 2. Reactor Mode Switch -(a) 2 Note 2 NA Shutdown Position (a) When reactor mode switch is in the shutdown position.(b) Trip Setting 0.66 (W-AW)+N for single loop operation.

Amendment No. 4-64 55 VYNPS Table 3.2.5 ACTION Notes 1. With one or two RBM channels inoperable, take all of the applicable Actions in Notes l.a and l.b below.a. If one RBM channel is inoperable, restore the inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .b. If the required Action and associated completion time of Note l.a above is not met, or if two RBM channels are inoperable, place one RBM channel in trip within the next hour.2. With one or more Reactor Mode Switch -Shutdown Position channels inoperable, immediately suspend control rod withdrawal and immediately initiate actions to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Amendment No. *--4 56 VYNPS Table 4.2.5 (page 1 of 1)Control Rod Block Instrumentation Tests and Frequencies TRIP FUNCTION FUNCTIONAL TEST CALIBRATION

1. Rod Block Monitor (RBM)a. Upscale (Flow Bias) Every 3 Months Every 3 Months(b),(c)

b. Downscale Every 3 Months Every 3 Months(b)c. Inop Every 3 Months NA 2. Reactor Mode Switch -Every Refueling NA Shutdown Position Outage(a)(a) Required to be completed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the reactor mode switch is placed in the shutdown position.(b) Neutron detectors are excluded.(c) Includes calibration of the RBM Reference Downscale function (i.e., RBM upscale function is not bypassed when >30% Rated Thermal Power).Amendment No. 4-64 57 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS F. Mechanical Vacuum Pump Isolation Instrumentation F. Mechanical Vacuum Pump Isolation Instrumentation

1. When the reactor is in the RUN or STARTUP/HOT STANDBY Mode and the mechanical vacuum pump is in service, 4 channels of the High Main Steam Line Radiation Trip Function for mechanical vacuum pump isolation shall be operable.1. The High Main Steam Line Radiation Trip Function for mechanical vacuum pump isolation shall be checked, functionally tested and calibrated as indicated in Surveillance Requirements 4.2.F.l.a, b, c, d and e.When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains mechanical vacuum pump isolation capability.

a. Perform an Instrument Check once each day.b. Perform an Instrument Functional Test once every 3 months.c. Perform an Instrument Calibration, except for radiation detectors, using a current source once every 3 months.The Trip Setting shall be < 3.0 X background at rated thermal power.d. Perform an Instrument Calibration using a radiation source once each Refueling Outage.e. Perform a Logic System Functional Test, including mechanical vacuum pump isolation valve, once every Operating Cycle.Amendment No. 1-64, p4 58 VYNPS 3.2 LIMITING CONDITIONS FOR 4.2 SURVEILLANCE REQUIREMENTS OPERATION 2. If Specification 3.2.F.1 is not met, take all of the applicable Actions in Specifications 3.2.F.2.a and 2.b below.a. With one or more channels inoperable:

1) Restore any inoperable channel to operable status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; or 2) Place any inoperable channel or associated trip system in the trip condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (not applicable if the inoperable channel is the result of an inoperable.

mechanical vacuum pump isolation valve).b. If the required Action and associated completion time of Specification 3.2.F.2.a above is not met, or if mechanical vacuum pump isolation capability is not maintained:

1) Isolate the mechanical vacuum pump within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; or 2) Isolate the main steam lines within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; or 3) Place the reactor in the SHUTDOWN Mode within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Amendment No.444, 2 59 59 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION G. Post-Accident Monitoring Instrumentation The post-accident monitoring instrumentation for each Function in Table 3.2.6 shall be operable in accordance with Table 3.2.6.4.2 SURVEILLANCE REQUIREMENTS G. Post-Accident Monitoring Instrumentation

1. The post-accident monitoring instrumentation shall be checked and calibrated in accordance with Table 4.2.6.When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .Amendment No. 4&, 4-64 60 VYNPS Table 3.2.6 (page 1 of 1)Post-Accident Monitoring Instrumentation.

APPLICABLE MODES OR OTHER 1.2.3.4.5.6.7.8.9.FUNCTION Drywell Atmospheric Temperature Drywell Pressure Torus Pressure Torus Water Level Torus Water Temperature Reactor Pressure Reactor Vessel Water Level Torus Air Temperature Containment High Range Radiation Monitor APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS RUN, STARTUP/HOT STANDBY RUN, STARTUP/HOT STANDBY RUN, STARTUP/HOT STANDBY RUN, STARTUP/HOT STANDBY RUN, STARTUP/HOT STANDBY REQUIRED CHANNELS PER FUNCTION 2 2 2 2 2 2 2 2 2 ACTIONS WHEN REQUIRED CHANNELS ARE INOPERABLE Note 1 Note 1 Note 1 Note 1 Note 1 RUN, RUN, RUN, RUN, STARTUP/HOT STARTUP/HOT STARTUP/HOT STARTUP/HOT STANDBY STANDBY STANDBY STANDBY Note Note Note Note 1 1 1 2 Amendment No. 944, -64 61 VYNPS Table 3.2.6 ACTION Notes 1. With one or more Post-Accident Monitoring instrumentation channels, for Functions other than Function 9, inoperable, take all of the applicable.

Actions in Notes l.a and l.b below.a. With one or more Functions with one channel inoperable:

1) Restore channel to operable status within 30 days; or 2) Prepare and submit a special report to the Commission within the next 14 days, outlining the Action taken, the cause of the inoperability, and the plans and schedule for restoring the channel to operable status.b. With one or more Functions with two channels inoperable:

1) Restore one required channel to operable status within 7 days; or 2) Place the reactor in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .2. With one or more Post -Accident Monitoring instrumentation Function 9 channels inoperable, take all of the applicable Actions in Notes 2.a and 2.b below.a. With one channel inoperable:

.1) Restore channel to operable status within 30 days; or 2) Prepare and submit a special report to the Commission within the next 14 days, outlining the Action taken, the cause of the inoperability, and the plans and schedule for restoring the channel to operable status.b. With two channels inoperable:

1) Restore one channel to operable status within 7 days; or 2) Prepare and submit a special report to the Commission within the next 14 days, outlining the Action taken, the cause of the inoperability, and the plans and schedule for restoring the channels to operable status.Amendment No. 4&, 4-64 62 VYNPS Table 4.2.6 (page 1 of 1)Post-Accident Monitoring Instrumentation Tests and Frequencies 1.2.3.4.5.6.7.8.9.FUNCTION Drywell Atmospheric Temperature Drywell Pressure Torus Pressure Torus Water Level Torus Water Temperature Reactor Pressure Reactor Vessel Water Level Torus Air Temperature Containment High Range Radiation Monitor CHECK Once/Day Once/Day Once/Day Once/Day Once/Day Once/Day Once/Day Once/Day Once/Day CALIBRATION Every 6 Months Once/Operating Cycle Once/Operating Cycle Once/Operating Cycle Every 6 Months Once/Operating Cycle Once/Operating Cycle Every 6 Months Once/Operating Cycle Amendment No. 94&, 443 63 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS H. Deleted.I. Recirculation Pump Trip Instrumentation The recirculation pump trip instrumentation for each Trip Function in Table 3.2.7 shall be operable in accordance with Table 3.2.7.J. Deleted.H. Deleted.I. Recirculation Pump Trip Instrumentation

1. The recirculation pump trip instrumentation shall be checked, functionally tested and calibrated in accordance with Table 4.2.7.When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operations and required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Trip Function maintains recirculation pump trip capability.

2. Perform a Logic System Functional Test, including recirculation' pump trip breaker actuation, of recirculation pump trip instrumentation Trip Functions once every Operating Cycle.J. Deleted Amendment No. 19, -&, -i 4-66 64 VYNPS Table 3.2.7 (page 1 of 1)Recirculation Pump Trip Instrumentation ACTIONS WHEN APPLICABLE REQUIRED REQUIRED MODES OR OTHER CHANNELS CHANNELS SPECIFIED PER TRIP ARE TRIP SETTING TRIP FUNCTION CONDITIONS SYSTEM INOPERABLE

1. Low-Low Reactor Vessel RUN 2 Note 1 82.5 inches Water Level 2. Time Delay RUN 2 Note 1 10 seconds 3. High Reactor Pressure RUN 2 Note 1 1150 psig Amendment No. 54, 4-64, 65 VYNPS Table 3.2.7 ACTION Notes 1. With one or more recirculation pump trip instrumentation channels inoperable, take all of the applicable Actions in Notes l.a, l.b and l.c below.a. With one or more Trip Functions with one or more channels inoperable:

1) Restore any inoperable channel to operable status within 14 days; or 2) Place any inoperable channel in trip within 14 days (not applicable for Trip Function.

2 channels and not applicable if the inoperable channel is the result of an inoperable recirculation pump trip breaker).b. With Trip Functions 1 and 2 with recirculation pump trip capability not maintained or with Trip Function 3 with recirculation pump trip capability not maintained:

1) Restore recirculation pump trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .c. With Trip Functions 1, 2 and 3 with recirculation pump trip capability not maintained:

1) Restore recirculation pump trip capability for all but one Trip Function within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If any applicable Action and associated completion time of Note l.a, l.b or l.c is not met, immediately take the applicable Action of Note 2.a or 2.b.2. a. Remove affected recirculation pump from service within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or b. Place the plant in STARTUP/HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .Amendment No. &&, 4-6 66 VYNPS Table 4.2.7 Recirculation Pump Tests and (page 1 of 1)Trip Instrumentation Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

1. Low-Low Reactor Vessel Once/Day Every 3 Months Every 3 Months(a)Water Level Once/Operating Cycle 2. Time Delay NA NA Every 3 Months 3. High Reactor Pressure Once/Day Every 3 Months Every 3 Months(a)Once/Operating Cycle (a) Trip unit calibration only.Amendment No. -646 67 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS K. Degraded Grid Protective Syster The emergency bus undervoltage instrumentation for each Trip Function in Table 3.2.8 shall be operable in accordance with Table 3.2.8.K. Degraded Grid Protective System The emergency bus undervoltage instrumentation shall be functionally tested and calibrated in accordance with Table 4.2.8.Amendment No. 4&, 4-64 68 VYNPS Table 3.2.8 (page 1 of 1)Degraded Grid Protective System Instrumentation ACTIONS WHEN APPLICABLE REQUIRED MODES OR OTHER REQUIRED CHANNELS SPECIFIED CHANNELS ARE TRIP SETTING TRIP FUNCTION CONDITIONS PER- BUS INOPERABLE

1. Degraded Bus Voltage a.. Voltage Trip (b) (a) 2 Note 1 3660 volts and 3740 volts b. Time Delay Trip (b) (a) 1 Note 2 9 seconds and llseconds c. Voltage Alarm (c) (a) 2 Note 3 3660'volts and 3740 volts d. Alarm Time Delay (c) (a) 1 Note 3 9 seconds and 11 seconds (a) When the associated diesel generator is required to be operable per specifications 3.5, 3.7 and 3.10.(b)(c)LOCA condition.

Non-LOCA condition.

Amendment No. 9&, 4-6 69 VYNPS Table 3.2.8 ACTION Notes 1. With one or more required Degraded Bus Voltage -Voltage Trip Function channels inoperable:

a. Place any inoperable channel in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If the Action and associated completion time of Note l.a are not met, immediately declare the associated diesel generator inoperable.

2. With one or more required Degraded Bus Voltage -Time Delay Trip Function channels inoperable:

a. Restore any inoperable channel to operable status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If the Action and associated completion time of Note 2.a are not met, immediately declare the associated diesel generator inoperable.

3. With one or more required Degraded Bus Voltage -Voltage Alarm and/or Alarm Time Delay Trip Function channels inoperable, take all of the applicable Actions in Notes 3.a and 3.b: a. With one or more buses with alarm capability not maintained, restore.alarm capability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; and b. Restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If the Action and associated completion time of Note 3.a or 3.b are not met, immediately initiate increased voltage monitoring of the associated 4.16kV emergency bus(es) to twice per shift.Amendment No. 94&, 4-64 70 VYNPS Table 4.2.8 (page 1 of 1)Degraded Grid Protective System Instrumentation Tests and Frequencies TRIP FUNCTION FUNCTIONAL TEST CALIBRATION

1. Degraded Bus Voltage a. Voltage Trip (a) Once/Operating Cycle b. Time Delay Trip (a) Once/Operating Cycle c. Voltage Alarm (a) Once/Operating Cycle d. Alarm Time Delay (a) Once/Operating Cycle (a) Separate Functional Tests are not required for this Trip Function.

Trip Function operability is demonstrated during Trip Function Calibration and integrated ECCS tests performed once per Operating Cycle.Amendment No. 9&, 4-64 71 VYNPS 3.2 LIMITING CONDITIONS FOR OPERATION L. Reactor Core Isolation Cooling (RCIC) System Actuation The RCIC System instrumentation for each Trip Function in Table 3.2.9 shall be operable in accordance with Table 3.2.9.4.2 SURVEILLANCE REQUIREMENTS L. Reactor Core Isolation Cooling (RCIC) System Actuation 1. The RCIC System instrumentation shall be checked, functionally tested and calibrated as indicated in Table 4.2.9.When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting Conditions for Operation and required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Function 3;and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Functions 1 and 2 provided the associated Trip Function maintains RCIC initiation capability.

2. Perform a Logic System Functional Test of RCIC System instrumentation Trip Functions once every Operating Cycle.Amendment No. 4--,64 72 VYNPS Table 3.2.9 (page 1 of 1)Reactor Core Isolation Cooling System Instrumentation ACTIONS WHEN REQUIRED REQUIRED APPLICABLE MODES OR CHANNELS CHANNELS OTHER SPECIFIED PER ARE TRIP FUNCTION CONDITIONS FUNCTION INOPERABLE TRIP SETTING 1. Low-Low Reactor RUN, STARTUP/HOT 4 Note 1 82.5 inches Vessel Water STANDBY(a), HOT Level SHUTDOWN(a), Refuel(a)2. Low Condensate RUN, STARTUP/HOT 2 Note 2 3.8 1%(b)Storage Tank STANDBY(a), HOT Water Level SHUTDOWN(a), Refuel(a)3. High Reactor RUN, STARTUP/HOT 2 Note 3 177.0 inches Vessel Water STANDBY (a) , HOT Level SHUTDOWN(a), Refuel(a)(a) With reactor steam pressure > 150 psig.(b) Percent of instrument span.Amendment No. 4-1-+/-, 44 73 VYNPS Table 3.2.9 ACTION Notes 1. With one or more RCIC System instrumentation Trip Function 1 channels inoperable:

a. Declare the RCIC System inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of RCIC initiation capability; and b. Place any inoperable channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note l.a or l.b is not met, immediately declare the RCIC System inoperable.

2. With one or more RCIC System instrumentation Trip Function 2 channels inoperable:

a. Declare the RCIC System inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of RCIC initiation capability when RCIC System suction is aligned to the Condensate Storage Tank; and b. Place any inoperable channel in trip or align RCIC System suction to the suppression pool within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If any applicable Action and associated completion time of Note 2.a or 2.b is not met, immediately declare the RCIC System inoperable.

3. With one or more RCIC System instrumentation Trip Function 3 channels inoperable:

a. Restore any inoperable channel to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .If the Action and associated completion time of Note 3.a is not met, immediately declare the RCIC System inoperable.

Amendment No. 46,-4 74 VYNPS Table 4.2.9 (page 1 of 1)Reactor Core Isolation Cooling System Instrumentation Tests and Frequencies TRIP FUNCTION CHECK FUNCTIONAL TEST CALIBRATION

1. Low-Low Reactor Vessel Once/Day Every 3 Months Every 3 Months(ae Water Level Once/Operating Cycle 2. Low Condensate Storage NA Every 3 Months Every 3 Months(a)Tank Water Level Once/Operating Cycle 3. High Reactor Vessel NA Every 3 Months Every 3 Months(a)Water Level Once/Operating Cycle (a) Trip unit calibration only.Amendment No. 4-i-6, 74a

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BVY 09-035, Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages

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