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

{{Adams
| number = ML091470321
| issue date = 05/20/2009
| title = Technical Specifications Proposed Change No. 273, Supplement 8, Transmittal of Final Technical Specification Pages
| author name = Colomb M
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 09-035
| document type = Letter type:BVY, Technical Specifications
| page count = 60
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0250 320 Governor Hunt Road S0Entergy-                                                 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:==
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

==REFERENCES:==
: 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-&#xfd;035 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 ...................................                              1 LIMITING SAFETY SAFETY LIMITS                                                                         SYSTEM SETTING 1.1   FUEL CLADDING INTEGRITY .......................                              6  . ..       2.1 1.2   REACTOR COOLANT SYSTEM .........................                           18   .. .       2.2 LIMITING CONDITIONS                OF OPERATION                        Page No.       SURVEILLANCE 3.0   LIMITING CONDITIONS OF OPERATION and SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...                            19a               4.0 BASES                                                                     19c 3.1   REACTOR PROTECTION SYSTEM .....................                            20   ...         4.1 BASES                                                                      29 3.2   PROTECTIVE  INSTRUMENT SYSTEMS .................                           34   ...         4.2 A. Emergency Core Cooling System .............                            34                 A B. Primary Containment Isolation .............                            43       *  .  .B C. Reactor Building Ventilation Isolation and Standby Gas Treatment System Initiation ................................                            50                 C D.   (Deleted) ..................................                          54                 D E. Control Rod Block Actuation ...............                            54                 E F. Mechanical Vacuum Pump Isolation Instrumentation ..........................                             58                 F G. Post-Accident Monitoring Instrumentation..                             60                 G H.   (Deleted) .................................                           64                 H I. Recirculation Pump Trip Instrumentation ...........................                            64                 I J.   (Deleted) ................................                            64                 J K. Degraded Grid Protective System ..........                             68                 K L. Reactor Core Isolation Cooling System Actuation .................................                            72                 L BASES                                                                      75 3.3   CONTROL ROD SYSTEM ............................                            81   ...         4.3 A. Reactivity Limitations ....................                            81                 A B. Control Rods ................................                          82                 B C. Scram Insertion Times .....................                            85                 C D. Control Rod Accumulators ..................                            87                 D E. Reactivity Anomalies ......................                            88                 E BASES                                                                      89 Amendment No.4-3,  4&, 3-8,           44, 4-64,            9-,,     --
                                                                    -4,- 24,                          -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, &#xa3;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
                                            &#x17d; 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 &#x17d; 800 psig.
Amendment No. 4&9,  4, -I-
                   .-      4                                                10

VYNPS 3.1 LIMITING CONDITIONS FOR                    4.1 SURVEILLANCE REQUIREMENTS OPERATION 3.1 REACTOR PROTECTION SYSTEM    (RPS)         4.1 REACTOR PROTECTION SYSTEM (RPS)
Applicability:                                 Applicability:
Applies to the operability of                  Applies to the surveillance of plant instrumentation and                      the plant instrumentation and control systems required for                   control systems required for reactor safety.                                reactor safety.
Objective:                                     Objective:
To specify the limits imposed on               To specify the type and frequency plant operation by those                       of surveillance to be applied to instrument and control systems                those instrument and control required for reactor safety.                  systems required for reactor safety.
Specification:                                Specification:
A. The RPS instrumentation for              A.1   RPS instrumentation shall each Trip Function in Table                    be checked, functionally 3.1.1 shall be operable in                     tested and calibrated as accordance with Table 3.1.1.                   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 hours 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-&-,    p-1-2 2--4,                                           20

VYNPS 3.1 LIMITING CONDITIONS FOR       4.1 SURVEILLANCE REQUIREMENTS OPERATION
: 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            RUN, STARTUP/HOT            1      Note 1       Note 2.a         NA Switch in             STANDBY, Refuel Shutdown Refuel (b)                         Note 1       Note 2.d         NA 1
: 2. Manual Scram          RUN, STARTUP/HOT                    Note 1      Note 2.. a       NA STANDBY, Refuel(a)
Refuel (b)                          Note 1      Note 2.d         NA
: 3. Intermediate Range Monitors (IRMs)
: a. High Flux         STARTUP/HOT                2       Note 1      Note 2.a
* 120/125 STANDBY, Refuel(a)
Refuel (b)                 2       Note 1      Note 2.d
* 120/125
: b. Inop              STARTUP/HOT                2       Note 1      Note 2.a         NA STANDBY, Refuel(a)
Refuel (b)                 2       Note 1      Note 2.d         NA 0
(a)       With reactor coolant temperature > 212 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    &#x17d; 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 0
(a)      With reactor coolant temperature > 212 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 hours; or
: 2)  Place the associated trip      system in   trip   within 12 hours.
: 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 hours; or
: 2)  Place one trip   system in   trip   within 6 hours.
: c. With one or more Trip Functions with Reactor Protection System trip capability not maintained:
: 1) Restore Reactor Protection System trip           capability within 1 hour.
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 hours.
: b. Place the reactor in     STARTUP/HOT STANDBY within 8 hours.
: c. Reduce reactor power to < 25% Rated Thermal Power within 8 hours.
: 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               NA     Each Refueling Outage                         NA Switch in Shutdown
: 2. Manual Scram             NA     Every 3 Months                                NA
: 3. Intermediate Range Monitors (IRMs)
: a. High Flux        Once/Day,  Within 31 Days Before entering   Once/Operating Cycle  (b),(c)
(a)    STARTUP/HOT STANDBY(b) and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days During Refueling
: b. Inop              NA     Within 31 Days Before. entering                NA STARTUP/HOT STANDBY(b) and Every 31 Days During STARTUP/HOT STANDBY, Every 31 Days DuringRefueling
: 4. Average Power Range Monitors (APRMs)
: a. High Flux         NA     Every 3 Months                   Every 7 Days for (Flow                                                    Output Signal by Bias)                                                     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 hours after entering STARTUP/HOT STANDBY MODE.
(c)        Neutron detectors are excluded.
(d)    . Not required to be completed until 12 hours after reactor power is       &#x17d; 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           (a)    Within 7 Days Before entering    Within 7 Days Before (Reduced)                STARTUP/HOT STANDBY(b) and       entering STARTUP/HOT Every 7 Days During              STANDBY'bc),' ee) and STARTUP/HOT STANDBY,             Every 7 Days During Every 7 Days During Refueling    STARTUP/
(e)
HOT STANDBY(c),
Every 7 Days During Refueling(c) ,(e)
: c. Inop               NA              Every 3 Months                     NA
: 5. High Reactor        Once/Day           Every 3 Months          Every 3 Months(e)
Pressure                                                       Once/Operating Cycle
: 6. High Drywell           NA              Every 3 Months          Every 3 Months(e)
Pressure                                                       Once/Operating Cycle
: 7. Reactor Low         Once/Day           Every 3 Months          Every 3 Months(e)
Water Level                                                    Once/Operating Cycle
: 8. Scram                  NA              Every 3 Months          Every 3 Months(e)
Discharge                                                      Once/Operating Cycle Volume High Level
: 9. Main Steam             NA              Every 3 Months          Each Refueling Line                                                           Outage Isolation Valve Closure 10.Turbine                  NA              Every 3 Months          Every 3 Months Control Valve Fast Closure
: a. First              NA              Every 6 Months          Every 6 Months and Stage                                                      prior to entering Turbine                                                    STARTUP/HOT STANDBY Pressure                                                   for plant startup Permissive                                                 after Refueling (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 hours 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                 4.2  SURVEILLANCE REQUIREMENTS OPERATION 3.2  PROTECTIVE INSTRUMENT  SYSTEMS         4.2  PROTECTIVE        INSTRUMENT SYSTEMS Applicability:                               Applicability:
Applies to the operational status             Applies to the surveillance of the plant instrumentation                  requirements of the systems which initiate  and                  instrumentation systems which control a protective function.               initiate       and control a protective function.
Objective:                                   Objective:
To assure the operability of                  To verify the operability of protective instrumentation                    protective instrumentation systems.                                     systems.
Specification:                              Specification:
A. Emergency Core Cooling System         *A.      Emergency Core Cooling System (ECCS)                                          (ECCS)
The ECCS instrumentation for                   1. ECCS instrumentation shall each Trip Function in Table                        be checked, functionally 3.2.1 shall be operable in                         tested and calibrated as accordance with Table 3.2.1.                       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 hours for Trip Function 3.d; and (b) for up to 6 hours 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      RUN, STARTUP/HOT               2      Note 1
* 2.5 psig Pressure          STANDBY, HOT SHUTDOWN, Refuel (a), (e)
: b. Low-Low           RUN, STARTUP/HOT               2      Note 1   &#x17d; 82.5 inches Reactor           STANDBY, HOT SHUTDOWN, Vessel Water      Refuel (a), (b), (e)
Level
: c. Low Reactor       RUN, STARTUP/HOT               1      Note 2   &#x17d; 300 psig and Pressure          STANDBY, HOT SHUTDOWN,
* 350 psig (Initiation)      Refuel (a), (b)
: d. Low Reactor       RUN, STARTUP/HOT               2      Note 2   &#x17d; 300 psig and Pressure          STANDBY, HOT SHUTDOWN,
* 350 psig (System Ready    Refuel (a),(b) and Valve Permissive)
: e. Pump Start        RUN, STARTUP/HOT               1      Note 2   &#x17d; 8 seconds and Time Delay        STANDBY, HOT SHUTDOWN,                           10 seconds Refuel (a), (b)
: f. Pump              RUN, STARTUP/HOT               2      Note 8   &#x17d; 100 psig Discharge         STANDBY(c), HOT               per Pressure          SHUTDOWN(C) Refuel (c)       PUMP
: g. Auxiliary         RUN, STARTUP/HOT               1      Note 2           NA Power Monitor     STANDBY, HOT SHUTDOWN, Refuel(a), (b)
: h. Pump Bus          RUN, STARTUP/HOT               1      Note 2           NA Power Monitor     STANDBY, HOT SHUTDOWN, Refuel (a), (b)
(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              RUN, STARTUP/HOT                            Note 2   &#x17d; 300 psig and Pressure                 STANDBY, HOT SHUTDOWN,                                 350 psig (Initiation)            Refuel(a)     (b)                    1
: b. High Drywell             RUN, STARTUP/HOT                            Note 1
* 2.5 psig Pressure                 STANDBY, HOT SHUTDOWN, (Initiation)            Refuel (a)                           2
: c. Low-Low                  RUN, STARTUP/HOT                            Note 1   &#x17d; 82.5 inches Reactor                  STANDBY, HOT SHUTDOWN, Vessel Water             Refuel (a), (b)
Level
: d. Reactor                  RUN, STARTUP/HOT                            Note 3   &#x17d; 2/3 core Vessel Shroud            STANDBY, HOT SHUTDOWN,                               height Level                    Refuel (a)
: e. LPCI B and C             RUN, STARTUP/HOT                            Note 2   &#x17d; 3 seconds and Pump Start               STANDBY, HOT SHUTDOWN,                                 5 seconds Time Delay               Refuel(a). (b)
: f. RHR Pump                 RUN, STARTUP/HOT                  2 per     Note 8     100 psig 1
Discharge                STANDBY(c), HOT                    pump Pressure                 SHUTDOWN(C),      Refuel(c)
: g. High Drywell             RUN, STARTUP/HOT                     2      Note 3
* 2.5 psig Pressure                 STANDBY, HOT SHUTDOWN, (Containment            Refuel (a)
Spray Permissive)
: h. Low Reactor              RUN, STARTUP/HOT                     2      Note 2   &#x17d; 300 psig and Pressure                 STANDBY, HOT SHUTDOWN,                                 350 psig (System Ready           Refuel (a), (b) and Valve Permissive)
(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  &#x17d; 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   &#x17d; 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 hour from discovery of loss of initiation         capability for feature(s) in both divisions; and
: b. Place any inoperable channel in trip          within 24 hours.
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 hour from discovery of loss of initiation         capability for feature(s) in both divisions; and
: b. Restore any inoperable channel to operable status within 24 hours.
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 hour from discovery of loss of LPCI initiation          capability; and
: b. For Trip Function 2.g, place any inoperable channel in trip          within 24 hours.
: c. For Trip Function 2.d restore any inoperable channel to operable status within 24 hours.
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 hour from discovery of loss of HPCI System initiation         capability; and
: b. Place any inoperable channel in trip          within 24 hours.
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 hour 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 hours.
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                                                                       339

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 hours.
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 hour from discovery of loss of ADS initiation       capability in both trip   systems; and
: b. Place any inoperable channel in trip          within 96 hours 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 hour from discovery of loss of ADS initiation      capability in both trip    systems; and
: b. Restore any inoperable channel to operable status within 96 hours 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)
Emergency Core Cooling System Instrumentation Tests and Frequencies TRIP FUNCTION            CHECK     FUNCTIONAL TEST         CALIBRATION
: 1. Core Spray System
: a. High Drywell             Once/Day    Every 3 Months    Every 3 Monthsla)
Pressure                                               Once/Operating Cycle
: b. Low-Low Reactor          Once/Day    Every 3 Months    Every 3 Months(a)
Vessel Water Level                                     Once/Operating Cycle
: c. Low Reactor Pressure         NA      Every 3 Months    Every 3 Months(a)
(Initiation)                                          Once/Operating Cycle
: d. Low Reactor Pressure         NA      Every 3 Months    Every 3 Months(a)
(System Ready and                                     Once/Operating Cycle Valve Permissive)
: e. Pump Start Time              NA             NA         Once/Operating Cycle Delay
: f. Pump Discharge               NA      Every 3 Months    Every 3 Months Pressure
: g. Auxiliary Power          Once/Day    Every 3 Months               NA Monitor
: h. Pump Bus Power           Once/Day    Every 3 Months               NA Monitor
: 2. Low Pressure Coolant Injection (LPCI) System
: a. Low Reactor Pressure         NA      Every 3 Months    Every 3 Months aW (Initiation)                                          Once/Operating Cycle
: b. High Drywell             Once/Day    Every 3 Months    Every 3 Months(a)
Pressure                                               Once/Operating Cycle (Initiation)
: c. Low-Low Reactor'         Once/Day    Every 3 Months    Every 3 Months(a)
Vessel Water Level                                     Once/Operating Cycle
: d. Reactor Vessel               NA      Every 3 Months    Every 3 Months(a)
Shroud Level                                           Once/Operating Cycle
: e. LPCI B and C Pump            NA             NA         Once/Operating Cycle Start Time Delay
: f. RHR Pump Discharge           NA      Every 3 Months    Every 3 Months Pressure
: g. High Drywell                 NA      Every 3 Months    Every 3 Months(a)
Pressure                                               Once/Operating Cycle (Containment Spray Permissive)
(a)    Trip unit calibration only.
Amendment No. 4-64                                                               41

VYNPS Table 4.2.1 (page 2 of 2)
Emergency Core Cooling System Instrumentation Tests and Frequencies TRIP FUNCTION           CHECK      FUNCTIONAL TEST         CALIBRATION
: 2. LPCI System (Continued)
: h. Low Reactor Pressure         NA       Every 3 Months    Every 3 Months(a)
(System Ready and                                      Once/Operating Cycle Valve Permissive)
: i. Auxiliary Power           Once/Day    Every 3 Months               NA Monitor
: j. Pump Bus Power            Once/Day    Every 3 Months               NA Monitor
: 3. High Pressure Coolant Injection (HPCI) System
: a. Low-Low Reactor           Once/Day    Every 3 Months    Every 3 Months(a)
Vessel Water Level                                      Once/Operating Cycle
: b. Low Condensate               NA       Every 3 Months    Every 3 Months Storage Tank Water Level
: c. High Drywell              Once/Day    Every 3 Months    Every 3 Months(a)
Pressure                                                Once/Operating Cycle
: d. High Reactor Vessel          NA       Every 3 Months    Every 3 Months(a)
Water Level                                             Once/Operating Cycle
: 4. Automatic Depressurization      System (ADS)
: a. Low-Low Reactor           Once/Day    Every 3 Months    Every 3*Months(a)
Vessel Water Level                                      Once/Operating Cycle
: b. High Drywell                                            Every 3 Months(a)
Once/Day    Every 3 Months Pressure                                                Once/Operating Cycle
: c. Time Delay                   NA              NA         Once/Operating Cycle
: d. Sustained Low-Low            NA              NA         Once/Operating Cycle Reactor Vessel Water Level Time Delay (a)    Trip unit calibration only.
Amendment No. 4-64                                                               42

VYNPS 3.2  LIMITING CONDITIONS FOR                4.2 SURVEILLANCE REQUIREMENTS OPERATION 3.2  PROTECTIVE   INSTRUMENT SYSTEMS        4.2 PROTECTIVE  INSTRUMENT.SYSTEMS B. Primary Containment Isolation          B. Primary Containment  Isolation The primary containment                     1. The primary containment isolation instrumentation for                  isolation instrumentation each Trip Function in Table                    shall be checked, 3.2.2 shall be operable in                     functionally tested and accordance with Table 3.2.2.                   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 hours 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      RUN, STARTUP/HOT            2      Note 1  Note 2.a   &#x17d; 82.5 Vessel Water        STANDBY, HOT                                          inches Level               SHUTDOWN, Refuel (a) 0 b.High Main Steam      RUN, STARTUP/HOT            8      Note 1  Note 2.a   5 196 F for Line Area           STANDBY, HOT                                          channels Temperature         SHUTDOWN, Refuel(a)                                   monitoring outside steam tunnel and 5 200 0 F for channels monitoring inside steam tunnel
: c. High Main Steam     RUN, STARTUP/HOT         2 per     Note 1  Note 2.a   5 140% of.
Line Flow           STANDBY, HOT              main                        rated flow SHUTDOWN, Refuel (a)     steam line d.Low Main Steam       RUN                         2      Note 1  Note 2.c   &#x17d; 800 psig Line Pressure e.High Main Steam      STARTUP/HOT                 2      Note 1  Note 2.a   5 40% of Line Flow - Not     STANDBY, HOT                                          rated flow in RUN              SHUTDOWN, Refuel(a) f.Condenser Low        RUN, STARTUP/HOT            2      Note 1  Note 2.a   5 12 inches Vacuum               STANDBY (b), HOT                                     Hg absolute SHUTDOWN (b),
Refuel(a) ,(b)
: 2. Primary Containment Isolation a.Low Reactor           RUN, STARTUP/HOT           2      Note 1  Note 2.b   &#x17d; 127.0 Vessel Water         STANDBY, HOT                                          inches Level                SHUTDOWN, Refuel (a) b.High Drywell          RUN, STARTUP/HOT           2      Note 1  Note  2.b  5 2.5 psig Pressure             STANDBY, HOT SHUTDOWN, Refuel (a)
(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 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
: 3. High Pressure Coolant Injection (HPCI) System Isolation a.High Steam Line       RUN, STARTUP/HOT          6      Note 1   Note 2.d
* 196 OF Space                 STANDBY, HOT Temperature           SHUTDOWN, Refuel(a) b.High Steam Line       RUN, STARTUP/HOT                 Note 1   Note 2.cd
* 195 d/p (Steam Line       STANDBY, HOT                                         inches of Break)                SHUTDOWN, Refuel (a)                                 water c.Low Steam             RUN, STARTUP/HOT          4      Note 1   Note 2.d   &#x17d; 70 psig Supply Pressure      STANDBY, HOT SHUTDOWN, Refuel(a) d.High Main Steam       RUN, STARTUP/HOT          2      Note 1   Note 2.d
* 200 OF Line Tunnel           STANDBY, HOT Temperature           SHUTDOWN, Refuel(a) e.High Main Steam       RUN, STARTUP/HOT          1      Note 1   Note 2.d
* 35
        *Line Tunnel          STANDBY, HOT                                         minutes Temperature Time      SHUTDOWN, Refuel (a)
Delay
: 4. Reactor Core Isolation Cooling (RCIC) System Isolation a.High Main Steam       RUN, STARTUP/HOT          2      Note   1  Note 2.d
* 200 OF Line Tunnel          STANDBY, HOT Temperature           SHUTDOWN, Refuel (a) b.High Main Steam       RUN, STARTUP/HOT                  Note 1   Note 2.d
* 35 Line Tunnel          STANDBY, HOT                                         minutes Temperature Time      SHUTDOWN, Refuel (a)
Delay c.High Steam Line       RUN, STARTUP/HOT          6       Note 1   Note 2.d
* 196 OF Space                STANDBY, HOT Temperature          SHUTDOWN, Refuel (a)
(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   &#x17d;t3 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   &#x17d; 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 hours; and
: 2)   For Trip Functions 3.e, 4.b, and 4.e, restore any inoperable channel to operable status within 24 hours; and
: 3)   For all  other Trip Functions, place any inoperable channel in trip  within 24 hours.
: b. With one or more Trip Functions with isolation capability not maintained:
: 1)   Restore isolation capability within 1 hour.
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 hours (penetration flow paths may be unisolated intermittently under administrative control); or Place the reactor in HOT SHUTDOWN within 12 hours and place the reactor in COLD SHUTDOWN within the next 12 hours.
: b. Place the reactor in   COLD SHUTDOWN within 24 hours.
: c. Place the reactor in   STARTUP/HOT STANDBY within 8 hours.
: d. Isolate the affected penetration flow path within 1 hour 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           CHECK      FUNCTIONAL TEST         CALIBRATION
: 1. Main Steam Line Isolation
: a. Low-Low Reactor          Once/Day    Every 3 Months    Every 3 Months(a)
Vessel Water Level                                     Once/Operating Cycle
: b. High Main Steam Line        NA       Every 3 Months    Each Refueling Outage Area Temperature
: c. High Main Steam Line     Once/Day    Every 3 Months    Every 3 Months(a)
Flow                                                   Once/Operating Cycle
: d. Low Main Steam Line         NA       Every 3 Months    Every 3 Months Pressure
: e. High Main Steam Line     Once/Day    Every 3 Months    Every 3 Months(a)
Flow - Not in RUN                                      Once/Operating Cycle
: f. Condenser Low Vacuum        NA       Every 3 Months    Every 3 Months
: 2. Primary Containment Isolation
: a. Low Reactor Vessel          NA       Every 3 Months    Every 3 Months(a)
Water Level                                            Once/Operating Cycle
: b. High Drywell             Once/Day    Every 3 Months    Every 3 Months(a)
Pressure                                               Once/Operating Cycle
: 3. High Pressure Coolant Injection (HPCI) System Isolation
: a. High Steam Line             NA       Every 3 Months    Each Refueling Outage Space Temperature
: b. High Steam Line d/p         NA       Every 3 Months    Every 3 Months (Steam Line Break)
: c. Low Steam Supply            NA       Every 3 Months    Every 3 Months Pressure
: d. High Main Steam Line        NA       Every 3 Months    Each Refueling Outage Tunnel Temperature
: e. High Main Steam Line        NA              NA         Once/Operating Cycle Tunnel Temperature Time Delay (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              4.2 SURVEILLANCE REQUIREMENTS OPERATION 3.2  PROTECTIVE INSTRUMENT SYSTEMS           4.2 PROTECTIVE INSTRUMENT     SYSTEMS C. Reactor Building Ventilation            C. Reactor Building Ventilation Isolation and Standby Gas                   Isolation and Standby Gas Treatment System Initiation                 Treatment System Initiation The reactor building                        1. The reactor building ventilation isolation and                       ventilation isolation and Standby Gas Treatment System                    Standby Gas Treatment initiation   instrumentation                    System initiation for each Trip Function in                       instrumentation shall be Table 3.2.3 shall be operable                   checked, functionally in accordance with                              tested and calibrated as Table 3.2.3.                                    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 hours 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 Treatment
                                                        &#xfd;System 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   &#x17d; 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     1100 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                                                                       51*

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 hours; and
: 2) For Trip Functions 3 and 4,      place any inoperable channel  in  trip within 24 hours.
: b. With one or more Trip Functions with isolation or initiation         capability not maintained:
: 1) Restore isolation and initiation      capability within 1 hour.
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 hour.
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             CHECK       FUNCTIONAL TEST           CALIBRATION
: 1. Low Reactor Vessel               NA       Every 3 Months       Every 3 Months(a)
Water Level                                                   Once/Operating Cycle
: 2. High Drywell Pressure           NA        Every 3 Months      Every 3 Months(a)
Once/Operating Cycle
: 3. High Reactor Building        Once/Day     Every 3 Months      Every 3 Months Ventilation Radiation
: 4. High Refueling Floor         Once/Day     Every 3 Months      Every 3 Months Zone Radiation                During Refueling (a)  Trip unit calibration only.
Amendment No.-145                                                                      53

VYNPS 3.2 LIMITING CONDITIONS FOR                4.2 SURVEILLANCE REQUIREMENTS OPERATION D. Deleted.                              D. Deleted.
E. Control Rod Block Actuation           E. Control Rod Block Actuation The control rod block                     1. The control rod block instrumentation for each                      instrumentation shall be Trip Function in Table                        functionally tested and 3.2.5 shall be operable in                    calibrated as indicated accordance with Table                         in Table 4.2.5.
3.2.5.
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 hours 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  &#x17d; 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 hours.
: 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 hour 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               4.2 SURVEILLANCE REQUIREMENTS OPERATION F. Mechanical Vacuum Pump                F. Mechanical Vacuum Pump Isolation Instrumentation                 Isolation Instrumentation
: 1. When the reactor is in the             1. The High Main Steam Line RUN or STARTUP/HOT STANDBY                 Radiation Trip Function Mode and the mechanical                    for mechanical vacuum pump vacuum pump is in service,                 isolation shall be 4 channels of the High                     checked, functionally Main Steam Line Radiation                  tested and calibrated as Trip Function for                          indicated in Surveillance mechanical vacuum pump                     Requirements 4.2.F.l.a, b, isolation shall be                        c, d and e.
operable.
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 hours 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 hours; or
: 2) Place any inoperable channel or associated trip system in the trip condition within 12 hours (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 hours; or
: 2) Isolate the main steam lines within 12 hours; or
: 3) Place the reactor in the SHUTDOWN Mode within 12 hours.
Amendment No.444, 2                                                       59 59

VYNPS 3.2  LIMITING CONDITIONS FOR               4.2 SURVEILLANCE REQUIREMENTS OPERATION G. Post-Accident Monitoring              G. Post-Accident Monitoring Instrumentation                          Instrumentation The post-accident monitoring              1. The post-accident instrumentation for each                      monitoring instrumentation Function in Table 3.2.6 shall shall be checked and be operable in accordance with Table 3.2.6.                             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 hours.
Amendment No. 4&, 4-64                                                         60

VYNPS Table 3.2.6 (page 1 of 1)
Post-Accident Monitoring Instrumentation.
OTHER MODES OR APPLICABLE                 REQUIRED ACTIONS WHEN CHANNELS   REQUIRED APPLICABLE MODES OR OTHER     PER   CHANNELS ARE FUNCTION                 SPECIFIED CONDITIONS    FUNCTION  INOPERABLE
: 1. Drywell Atmospheric        RUN,  STARTUP/HOT STANDBY       2       Note 1 Temperature
: 2. Drywell Pressure           RUN,  STARTUP/HOT STANDBY       2       Note 1
: 3. Torus Pressure             RUN,  STARTUP/HOT STANDBY       2       Note 1
: 4. Torus Water Level          RUN,  STARTUP/HOT STANDBY       2       Note 1
: 5. Torus Water                RUN,  STARTUP/HOT STANDBY       2       Note 1 Temperature
: 6. Reactor Pressure           RUN,  STARTUP/HOT STANDBY       2       Note 1
: 7. Reactor Vessel Water       RUN,  STARTUP/HOT STANDBY       2       Note 1 Level
: 8. Torus Air Temperature      RUN,  STARTUP/HOT STANDBY       2       Note 1
: 9. Containment High           RUN,  STARTUP/HOT STANDBY       2       Note 2 Range Radiation Monitor 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 hours.
: 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 FUNCTION                       CHECK                CALIBRATION
: 1. Drywell Atmospheric                Once/Day         Every 6 Months Temperature
: 2. Drywell Pressure                   Once/Day         Once/Operating Cycle
: 3. Torus Pressure                     Once/Day         Once/Operating Cycle
: 4. Torus Water Level                  Once/Day         Once/Operating Cycle
: 5. Torus Water                        Once/Day         Every 6 Months Temperature
: 6. Reactor Pressure                   Once/Day         Once/Operating Cycle
: 7. Reactor Vessel Water               Once/Day         Once/Operating Level                                               Cycle
: 8. Torus Air Temperature              Once/Day         Every 6 Months
: 9. Containment High                   Once/Day         Once/Operating Range Radiation                                     Cycle Monitor Amendment No. 94&, 443                                                       63

VYNPS 3.2 LIMITING CONDITIONS FOR                4.2 SURVEILLANCE REQUIREMENTS OPERATION H. Deleted.                              H. Deleted.
I. Recirculation Pump Trip               I. Recirculation Pump Trip Instrumentation                           Instrumentation The recirculation pump trip               1. The recirculation             pump instrumentation for each Trip                 trip     instrumentation shall Function in Table 3.2.7 shall                 be checked, functionally be operable in accordance                     tested       and calibrated       in with Table 3.2.7.                             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 hours 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.                              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   &#x17d; 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 hours.
: 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 hour.
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 hours; or
: b. Place the plant in   STARTUP/HOT STANDBY within the next 6 hours.
Amendment   No.   &&, 4-6                                                           66

VYNPS Table 4.2.7  (page 1 of 1)
Recirculation Pump Trip Instrumentation Tests and 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. *44, -646                                                         67

VYNPS 3.2  LIMITING CONDITIONS FOR               4.2 SURVEILLANCE REQUIREMENTS OPERATION K. Degraded Grid Protective              K. Degraded Grid Protective Syster                                    System The emergency bus                         The emergency bus undervoltage instrumentation              undervoltage instrumentation for each Trip Function in                 shall be functionally tested Table 3.2.8 shall be operable             and calibrated in accordance in accordance with Table                  with Table 4.2.8.
3.2.8.
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    &#x17d; 3660 volts and 3740 volts
: b. Time Delay Trip   (b)        (a)             1        Note 2    &#x17d; 9 seconds and llseconds
: c. Voltage Alarm (c)            (a)             2        Note 3    &#x17d; 3660'volts and 3740 volts
: d. Alarm Time Delay (c)         (a)             1        Note 3    &#x17d; 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)    LOCA condition.
(c)    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 hour.
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 hour.
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 hour; and
: b. Restore any inoperable channel to operable status within 24 hours.
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                4.2 SURVEILLANCE REQUIREMENTS OPERATION L. Reactor Core Isolation                L. Reactor Core Isolation Cooling (RCIC) System                     Cooling (RCIC) System Actuation                                 Actuation The RCIC System                           1. The RCIC System instrumentation for each Trip                 instrumentation shall be Function in Table 3.2.9 shall                 checked, functionally be operable in accordance                     tested and calibrated as with Table 3.2.9.                             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 hours for Trip Function 3; and (b) for up to 6 hours 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   &#x17d; 82.5 inches Vessel Water           STANDBY(a), HOT Level                  SHUTDOWN(a), Refuel(a)
: 2. Low Condensate         RUN, STARTUP/HOT              2      Note 2   &#x17d; 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 hour from discovery of loss of RCIC initiation capability; and
: b. Place any inoperable channel in trip  within 24 hours.
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 hour 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 hours.
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 hours.
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}}