ML061920594

R. E. Ginna, Tech Spec Pages for Amendment 97 Regarding 16.8 Percent Power Uprate

ML061920594
Person / Time
Site:	Ginna
Issue date:	07/11/2006
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MC7382
Download: ML061920594 (35)

Text

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

-NOTE-The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ACTUATION An ACTUATION LOGIC TEST shall be the application of various LOGIC TEST simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AXIAL FLUX AFD shall be the difference in normalized flux signals between the top DIFFERENCE and bottom halves of a two section excore neutron detector.

(AFD)

CHANNEL A CHANNEL CALIBRATION shall be the adjustment, as necessary, of CALIBRATION the channel so that it responds within the required range and accuracy to known input. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

R.E. Ginna Nuclear Power Plant 1.1-1 Amendment 07

Definitions 1.1 CHANNEL A COT shall be the injection of a simulated or actual signal into the OPERATIONAL channel as close to the sensor as practicable to verify the OPERABILITY TEST of required alarm, interlock, display, and trip functions. The COT shall (COT) include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

CORE CORE ALTERATIONS shall be the movement of any fuel, sources, or ALTERATIONS reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING The COLR is the plant specific document that provides cycle specific LIMITS REPORT parameter limits for the current reload cycle. These cycle specific (COLR) parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 EQUIVALENT 1-131 (microcurieslgram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP 30, Supplement to Part 1, pages 192-212, table entitled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

-AVERAGE E shall be the average (weighted in proportion to the concentration of DISINTEGRATION each radionuclide in the reactor coolant at the time of sampling) of the ENERGY sum of the average beta and gamma energies (in MeV) per disintegration for non-iodine isotopes, with half lives > 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

R.E. Ginna Nuclear Power Plant 1.1-2 Amendment 0

Definitions 1.1 LEAKAGE LEAKAGE from the RCS shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or return), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System;

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or return) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

MODE A MODE shall correspond to any one inclusive combination of core

- MODES reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE A system, subsystem, train, component, or device shall be OPERABLE

- OPERABILITY or have OPERABILITY when it is capable of performing its specified safety fLinction(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

R.E. Ginna Nuclear Power Plant 1.1-3 Amendment 97

Definitions 1.1 PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Chapter 14, Initial Test Program of the UFSAR;

b. Authorized underthe provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission (NRC).

PRESSURE AND The PTLR is the plant specific document that provides the reactor vessel TEMPERATURE pressure and temperature limits, including heatup and cooldown rates, LIMITS REPORT and the power operated relief valve lift settings and enable temperature (PTLR) associated with the Low Temperature Overpressurization Protection System for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6. Plant operation within these limits is addressed in individual specifications.

QUADRANT QPTR shall be the ratio of the highest average nuclear power in any POWER TILT quadrant to the average nuclear power in the four quadrants.

RATIO (QPTR)

RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor coolant POWER of 1775 MWt.

(RTP)

SHUTDOWN SDM shall be the instantaneous amount of reactivity by which the reactor MARGIN is subcritical or would be subcritical from its present condition assuming:

(SDM)

a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCAs not capable of being fully inserted, the reactivity worth of the RCCAs must be accounted for in the determination of SDM; and

b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal hot zero power temperature.

STAGGERED TEST A STAGGERED TEST BASIS shall consist of the testing of one of the BASIS systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

R.E. Ginna Nuclear Power Plant 1.1-4 Amendment §7

Definitions 1.1 THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING A TADOT shall consist of operating the trip actuating device and verifying DEVICE the OPERABILITY of required alarm, interlock, display, and trip functions.

OPERATIONAL The TADOT shall include adjustment, as necessary, of the trip actuating TEST device so that it actuates at the required setpoint Within the required (TADOT) accuracy.

R.E. Ginna Nuclear Power Plant 1.1-5 Amendment 917

Definitions 1.1 Table 1.1-1 MODES MODE TITLE REACTIVITY  % RATED AVERAGE REACTOR CONDITION (keff) THERMAL COOLANT TEMPERATURE POWER(a) (*F)

I Power Operation *0.99 >5 NA 2 Startup >Ž0.99 <*5 NA 3 Hot Shutdown < 0.99 NA _>350 4 Hot Standby(b) < 0.99 NA 350 > Tavg > 200 5 Cold Shutdown(b) < 0.99 NA < 200 6 Refueling(c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

R.E. Ginna Nuclear Power Plant 1.1-6 Amendment 97

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

-NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one channel referenced in Table 3.3.1-1 inoperable, for the channel(s).

OR Two source range channels inoperable.

B. As required by Required B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Action A.I and referenced OPERABLE status.

by Table 3.3.1-1.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not AND met.

C.2 Initiate action to fully insert 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> all rods.

AND C.3 Place Control Rod Drive 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> System in a condition incapable of rod withdrawal.

R.E. Ginna Nuclear Power Plant 3.3.1-1 Amendment -07

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required

• D.1 Action A.1 and referenced -------------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> E. As required by Required E.1 Reduce THERMAL POWER 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Action A.1 and referenced to < 5E-11 amps.

by Table 3.3.1-1.

OR E.2

-NOTE-Required Action E.2 is not applicable when:

a. Two channels are inoperable, or

b. THERMAL POWER is

< 5E-11 amps.

Increase THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to _Ž8% RTP.

F. As required by Required F.1 Open RTBs and RTBBs Immediately upon Action A.1 and referenced upon discovery of two discovery of two by Table 3.3.1-1. inoperable channels.' inoperable channels AND F.2 Suspend operations Immediately involving positive reactivity additions.

AND F.3 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.3.1-2 Amendment 97

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.A Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition D, E, or F is not met.

H. As required by Required H.1 Restore at least one 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Action A.1 and referenced channel to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable channels inoperable channels.

AND H.2 Suspend operations Immediately involving positive reactivity additions.

AND H.3 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OPERABLE status.

I. Required Action and 1.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition H not met. AND 1.2 Place the Control Rod Drive 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a condition incapable of rod withdrawal.

J. As required by Required J.1 Suspend operations Immediately Action A.1 and referenced involving positive reactivity by Table 3.3.1-1. additions.

AND J.2 Perform SR 3.1.1.1. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter R.E. Ginna Nuclear Power Plant 3.3.1-3 Amendment 97

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required K.1 Action A.1 and referenced- -----------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> L. Required Action and L.1 Reduce THERMAL POWER 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion to < 8.5% RTP.

Time of Condition K not met.

M. As required by Required M.1 Action A.1 and referenced- ------------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.

• Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> N. As required by Required N.1 Restore channel to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action A.1 and referenced OPERABLE status.

by Table 3.3.1-1.

0. Required Action and 0.1 Reduce THERMAL POWER 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I associated Completion to < 30% RTP.

Time of Condition M or N not met.

P. As required by Required P.1 Action A.1 and referenced ------------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> R.E. Ginna Nuclear Power Plant 3.3.1-4 Amendment 97

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME Q. Required Action and Q.1 Reduce THERMAL POWER 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion to < 50% RTP.

Time of Condition P not met. AND Q.2.1 Verify Steam Dump System 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> is OPERABLE.

OR Q.2.2 ReduceTHERMAL POWER 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to < 8% RTP.

R. As required by Required R.1 Action A.1 and referenced -------- -----

by Table 3.3.1-1. - NOTE -

One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.

Restore train to OPERABLE 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> status.

S. As required by Required S.1 Verify interlock is in required 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.1 and referenced state for existing plant by Table 3.3.1-1. conditions.

OR S.2 Declare associated RTS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Function channel(s) inoperable.

R.E. Ginna Nuclear Power Plant 3.3.1-5 Amendment 97

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME T. As required by Required T.1 Action Al and referenced ------------

by Table 3.3.1 -1. - NOTE -

1. One train may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided the other train is OPERABLE.

2. One RTB may be

• bypassed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance on undervoltage or shunt trip mechanisms, provided the other train is OPERABLE.

Restore train to OPERABLE 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> status.

U. As required by Required U.1 Restore at least one trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from ActionA.l and referenced mechanism to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable trip RTBs with inoperable trip mechanisms mechanisms.

AND U.2 Restore trip mechanism to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OPERABLE status.

V.. Required Action and V.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition R, S, T, or U not met.

W. As required by Required W.1 Restore at least one trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Action A-1 and referenced mechanism to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable trip RTBs with inoperable trip mechanisms mechanisms.

AND R.E. Ginna Nuclear Power Plant 3.3.1-6 Amendment 97

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME W.2 Restore trip mechanism or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> train to OPERABLE status.

X. Required Action and X.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition W not met. AND X.2 Place the Control Rod Drive 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> System in a Condition incapable of rod withdrawal.

SURVEILLANCE REQUIREMENTS

-NOTE-Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 5R3.3.--------------------------

SR 3.3.1.2 -NOTE-Required to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is >__50% RTP.

Compare results of calorimetric heat balance 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculation to Nuclear Instrumentation System (NIS) channel output and adjust if calorimetric power is

> 2% higher than indicated NIS power.

SR 3.3.1.3 - NOTE -

1. Required to be performed within 7 days after THERMAL POWER is >_50% RTP but prior to exceeding 90% RTP following each refueling and if the Surveillance has not been performed within the last 31 EFPD.

2. Performance of SR 3.3.1.6 satisfies this SR.

Compare results of the incore detector measurements 31 effective full to NIS AFD and adjust if absolute difference is > 3%. power days (EFPD)

R.E. Ginna Nuclear Power Plant 3.3.1-7 Amendment 97

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.4 Perform TADOT. 31 days on a STAGGEREDTEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGEREDTEST BASIS SR 3.3.1.6 - NOTE -

Not required to be performed until 7 days after THERMAL POWER is > 50% RTP, but prior to exceeding 90% RTP following each refueling.

Calibrate excore channels to agree with incore 92 EFPD detector measurements.

SR 3.3.1.7 ----- NOTE ------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering MODE 3.

Perform COT. 92 days SR--3-3-1-8------------------------

SR 3.3.1.8 -NOTE-

1. Not required for power range and intermediate range instrumentation until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reducing power < 6% RTP.

2. Not required for source range instrumentation until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reducing power < 5E-11 amps.

Perform COT. 92 days

- NOTE -

SR 3.3.1.9 Setpoint verification is not required.

Perform TADOT. 92 days R.E. Ginna Nuclear Power Plant 3.3.1-8 Amendment 97

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.10 - NOTE-

-NOTE--

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.11 Perform TADOT. 24 months SR 3.3.1.12 ------ NOTE -----------------

Setpoint verification is not required.

Perform TADOT. Prior to reactor startup if not performed within previous 31 days SR 3.3.1.13 Perform COT. 24 months R.E. Ginna Nuclear Power Plant 3.3.1-9 Amendment 97

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

1. Manual Reactor Trip 1,2, 2 B,C SR 3.3.1.11 NA 3 (b), 4 (b), 5 (b)

2. Power Range Neutron Flux I a. High 1,2 4 D,G SR 3.3.1.1 <5109.27%

SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.10

b. Low 1 (c), 2 4 D,G SR 3.3.1.1 <*29.28%

SR 3.3.1.8 RTP SR 3.3.1.10 1(c), 2

3. Intermediate Range 2 E,G SR 3.3.1.1 (d)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10

4. Source Range 2 (e) 2 FG SR 3.3.1.1 (d)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10 3 (b), 4 (b), 5 (b) 2 H,I SR 3.3.1.1 (d)

SR 3.3.1.7 SR 3.3.1.10 3(0), 4(0), 5(0 1 J SR 3.3.1.1 NA SR 3.3.1.10

5. Overtemperature AT 1,2 4 D,G SR 3.3.1.1 Refer to SR 3.3.1.3 Note 1 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10

6. Overpower AT 1,2 4 D,G SR 3.3.1.1

• Refer to SR 3.3.1.7 Note 2 SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1-10 Amendment 97

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

7. Pressurizer Pressure

a. Low l(g) 4 K,L SR 3.3.1.1 __1791.3 SR 3.3.1.7 psig SR 3.3.1.10

b. High 1,2 3 D,G SR 3.3.1.1 _2396.2 SR 3.3.1.7 psig SR 3.3.1.10

8. Pressurizer Water 1,2 3 D,G SR 3.3.1.1 _96.47%

Level-High SR 3.3.1.7 SR 3.3.1.10

9. Reactor Coolant Flow-Low

a. Single Loop 3 per loop M,O SR 3.3.1.1 >_89.86%

1(h)

SR 3.3.1.7 SR 3.3.1.10

b. Two Loops 3 per loop K,L SR 3.3.1.1 89.86%

SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Pump (RCP)

Breaker Position

a. Single Loop 1(h) 1 per RCP NO SR 1

3.3.1.11 NA

b. Two Loops 10) 1 per RCP K,L SR 3.3.1.11 NA

11. Undervoltage- 2 per bus K,L SR 3.3.1.9 (d) 1 (g)

Bus 11A and 11B SR 3.3.1.10

12. Underfrequency- 1 (g) 2 per bus K,L SR 3.3.1.9 _ 57.5 HZ Bus 11A and 11B SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1-11t Amendment 97

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

13. Steam Generator 1,2 3 perSG D,G SR 3.3.1.1 >13.88%

(SG) Water Level- SR 3.3.1.7 Low Low SR 3.3.1.10

14. Turbine Trip

a. Low Autostop 1 (k)(I) 3 Po SR 3.3.1.10 (d)

Oil Pressure SR 3.3.1.12

b. Turbine Stop 1l(k)(I) 2 PQ SR 3.3.1.12 NA Valve Closure

15. Safety Injection (SI) 1,2 2 R,V SR 3.3.1.11 NA Input from Engineered Safety Feature Actuation System (ESFAS)

R.E. Ginna Nuclear Power Plant 3.3.1-12 Amendment 07

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

16. ReaclorTnp System Interlocks

a. Intermediate 2(e) 2 S,V SR 3.3.1.10 55E-11 Range SR 3.3.1.13 amp Neutron Flux, P-6

b. Low Power' 1 (g) 4 (power range S,V SR 3.3.1.10 -<8.0% RTP Reactor Trips only) SR 3.3.1.13 Block, P-7 I c. Power Range 1 (h) 4 S,V SR 3.3.1.10 < 29.0%

Neutron Flux, SR 3.3.1.13 RTP P-8

d. Power Range 4 S,V SR 3.3.1.10 < 50.0%

Neutron Flux, SR 3.3.1.13 RTP P-9 4 S,V SR 3.3.1.10 _<8.0% RTP 1 (k)

SR 3.3.1.13

e. Power Range 1 (c), 2 4 S,V SR 3.3.1.10 Ž6.0% RTP Neutron Flux, SR 3.3.1.13 P-10

17. Reactor Trip 1,2 2 trains T,V SR 3.3.1.4 NA Breakers(m) 3 (b), 4 (b), 5 (b) 2 trains w,x SR 3.3.1.4 NA

18. ReactorTrip 1,2 1 each per RTB u,V SR 3.3.1.4 NA Breaker 3 (b), 4 (b). 5 (b) 1 each per RTB wx SR 3.3.1.4 NA Undervottage and Shunt Trip Mechanisms

19. Automatic Trip Logic 1,2 2 trains R,V SR 3.3.1.5 NA 3 (b), 4 (b), 5 (b) 2 trains w,x SR 3.3.1.5 NA R.E. Ginna Nuclear Power Plant 3.3.1-13 Amendment 97

RTS Instrumentation 3.3.1 (a)

A channel is OPERABLE when both of the following conditions are met:

1. The absolute difference between the as-found Trip Setpoint (TSP) and the previous as-left TSP is within the COT Acceptance Criteria. The COT Acceptance Criteria is defined as:

las-found TSP - previous as-left TSPI - COT uncertainty The COT uncertainty shall not include the calibration tolerance.

2. The as-left TSP is within the established calibration tolerance band about the nominal TSR The nominal TSP is the desired setting and shall not exceed the Limiting Safety System Setting (LSSS). The LSSS and the established calibration tolerance band are defined in accordance with the Ginna Instrument Setpoint Methodology. The channel is considered operable even ifthe as-left TSP is non-conservative with respect to the LSSS provided that the as-left TSP is within the established calibration tolerance band.

(b) With Control Rod Drive (CRD) System capable of rod withdrawal or all rods not fully inserted.

(c) THERMAL POWER< 6% RTP.

(d) UFSAR Table 7.2-3.

(e) Both Intermediate Range channels < 5E-11 amps.

(f) With CRD System incapable of withdrawal and all rods fully inserted. Inthis condition, the Source Range Neutron Flux function does not provide a reactor trip, only indication.

(g) THERMAL POWER 8.5% RTP.

(h) THERMAL POWER 30% RTP.

(i) THERMAL POWER Ž8.5% RTP and Reactor Coolant Flow-Low (Single Loop) trip Function blocked.

(i) THERMAL POWER Ž8.5% RTP and RCP Breaker Position (Single Loop) trip Function blocked.

(k) THERMAL POWER > 8% RTP, and either no circulating water pump breakers closed, or condenser vacuum _< 20".

(I) THERMAL POWER > 50% RTP, 1 of 2 circulating water pump breakers closed, and condenser vacuum > 20".

(m) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

R.E. Ginna Nuclear Power Plant 3.3.1-14 Amendment 97

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 1)

Overtemperature AT

-NOTE-The Overtemperature AT Function Limiting Safety System Setting is defined by:

Overtemperature AT < AT0 {K1 + K2 (P-P') - K3 (T-T') [(1 +-I1s) /(1 +T2s)] - f, (AI)}

Where:

AT is measured RCS AT, OF.

AT 0 is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec"1 .

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, OF.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure, psig.

K1 is the Overtemperature AT reactor trip setpoint, [*].

K2 is the Overtemperature AT reactor trip depressurization setpoint penalty coefficient, [*]/psi.

K3 is the Overtemperature AT reactor trip heatup setpoint penalty coefficient, [*]/OF.

t1 is the measured lead time constant, [*] seconds.

'r 2 is the measured lag time constant, [*] seconds.

f(AI) is a function of the indicated difference between the top and bottom detectors of the Power Range Neutron Flux channels where qt and qb are the percent power in the top and bottom halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

f,(A1) = [*] {[*] - (qt - qb)} when qt - qb < [*]% RTP fl(AI) = 0% of RTP when [*] % RTP < qt - qb < [*]% RTP f, (A1) = [*] {(qt - qb) - when qt - qb > [*]% RTP

• These values denoted with r] are specified in the COLR.

R.E. Ginna Nuclear Power Plant 3.3.1-15 Amendment 97

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 2)

Overpower AT

-NOTE-The Overpower AT Function Limiting Safety System Setting is defined by:

Overpower AT _ AT 0 {K4 - K5 (T-T') - K6 [(T3 sT) I (T3 s+1)] - f2 (A0)}

Where:

AT is measured RCS AT, OF.

AT0 is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec"1 .

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, OF.

K4 is the Overpower AT reactor trip setpoint, [*].

K5 is the Overpower AT reactor trip heatup setpoint penalty coefficient which is:

[*]/OF for T < 1' and;

[*]/OF for T > T'.

K6 is the Overpower AT reactor trip thermal time delay setpoint penalty which is:

[*]/OF for increasing T and;

[*]/OF for decreasing T.

• 3 is the measured impulse/lag time constant, [*] seconds.

f2(AI) = [1*

• These values denoted with [*] are specified in the COLR.

R.E. Ginna Nuclear Power Plant 3.3.1-16 Amendment 97

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2-1.

ACTIONS

- NOTE

-

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one channel or train referenced in Table 3.3.2-1 inoperable, for the channel or train.

B. As required by Required B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Action A.1 and referenced OPERABLE status.

by Table 3.3.2-1.

C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B not met.

D. As required by Required D.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Action A.1 and referenced OPERABLE status.

by Table 3.3.2-1.

E. As required by Required E.1 Restore train to OPERABLE 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action A.1 and referenced status.

by Table 3.3.2-1.

R.E. Ginna Nuclear Power Plant 3.3.2-1 Amendment"'97

ESFAS Instrumentation 3.3.2 CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 Action A.1 and referenced- -----------

by Table 3.3.2-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of the other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition D, E, or AND F not met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> H. As required by Required H.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Action A.1 and referenced OPERABLE status.

by Table 3.3.2-1.

As required by Required 1.1 Restore train to OPERABLE 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action A.1 and referenced status.

by Table 3.3.2-1.

J. As required by Required J.1 Action A.1 and referenced -------------

by Table 3.3.2-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of the other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> K. Required Action and K.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition H, I, or AND J not met.

K.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> R.E. Ginna Nuclear Power Plant 3.3.2-2 Amendment *97

ESFAS Instrumentation 3.3.2 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required L.1 Action A.1 and referenced -------------

by Table 3.3.2-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of the other channels.

Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> M. Required Action and M.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition L not AND met.

M.2 Reduce pressurizer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> pressure to < 2000 psig.

N. As r'equired by Required N.1 Declare associated Auxiliary Immediately Action A.1 and referenced Feedwater pump inoperable by Table 3.3.2-1. and enter applicable condition(s) of LCO 3.7.5, "Auxiliary Feedwater (AFW)

System."

SURVEILLANCE REQUIREMENTS

- NOTE -

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.2.2 Perform COT. 92 days SR 3.3.2.3 - NOTE -

Verification of relay setpoints not required.

Perform TADOT. 92 days R.E. Ginna Nuclear Power Plant 3.3.2-3 Amendment 97

ESFAS Instrumentation 3.3.2 SURVEILLANCE FREQUENCY SR--3.3-2-4------------------------

SR 3.3.2.4 - NOTE -

Verification of relay setpoints not required.

Perform TADOT. 24 months SR 3.3.2.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.2.6 Verify the Pressurizer Pressure-Low and Steam Line 24 months Pressure-Low Functions are not bypassed when pressurizer pressure > 2000 psig.

SR 3.3.2.7 Perform ACTUATION LOGIC TEST. 24 months R.E. Ginna Nuclear Power Plant 3.3.2-4 Amendment *97

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

1. Safety Injection

a. Manual 1,2,3,4 2 D,G SR 3.3.2.4 NA Initiation

b. Automatic 1,2,3.4 2 trains I,K SR 3.3.2.7 NA Actuation Logic and Actuation Relays

c. Containment 1,2,3,4 3 J,K SR 3.3.2.1 _<4.61 psig Pressure-High SR 3.3.2.2 SR 3.3.2.5

d. Pressurizer 1 , 2 ,3 (b) 3 L,M SR 3.3.2.1 _ 1729.8 I Pressure-Low SR 3.3.2.2 SR 3.3.2.5 psig SR 3.3.2.6

e. Steam Line 1 ,2 ,3 (b) 3 per steam line L,M SR 3.3.2.1 _>393.8 psig Pressure-Low SR 3.3.2.2 SR 3.3.2.5 SR 3.3.2.6 R.E. Ginna Nuclear Power Plant 3.3.2-5 Amendment 97

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS

• REQUIREMENTS SETTINGS(a)

2. Containment Spray

a. Manual Initiation Left 1,2,3,4 i H,K SR 3.3.2.4 NA pushbutton Right 1,2,3,4 I-t,K SR 3.3.2.4 NA pushbutton

b. Automatic 1,2,3,4 2 trains I,K SR 3.3.2.7 NA Actuation Logic and Actuation Relays I c. Containment 1,2,3,4 3 per set J,K SR 3.3.2.1 532.11 psig Pressure-High SR 3.3.2.2 (narrow High SR 3.3.2.5 range)

I _*29.6 psig (wide range)

3. Containment Isolation

a. Manual 1,2 ,3 ,4 ,(c) 2 *H.K SR 3.3.2.4 NA Initiation

b. Automatic 1,2,3,4 2 trains I,K SR 3.3.2.7 NA Actuation Logic and Actuation Relays

c. Safety .Refer to Function 1 (Safety Injection) for all automatic initiation Injection functions and requirements.

R.E. Ginna Nuclear Power Plant 3.3.2-6 Amendment 97

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

4. Steam Line Isolation

a. Manual I per loop D,G SR 3.3.2.4 NA 1 ,2Cd),3Cd)

Initiation

b. Automatic 2 trains E,G SR 3.3.2.7 NA Actuation Logic and Actuation Relays

c. Containment 1,2(d),30d) 3 FG SR 3.3.2.1 _<18.0 psig Pressure-High SR 3.3.2.2 High SR 3.3.2.5

d. High Steam F,G SR 3.3.2.1 < 1.30E6 I Flow 1,20),Pd) 2 per steam line SR 3.3.2.2 SR 3.3.2.5 Ibm/hr

@ 1005 psig Coincident Refer to Function I (Safety Injection) for all initiation functions and with Safety requirements.

Injection and Coincident 1,2(d),3d) 2 per loop F,G SR 3.3.2.1 > 544.0°F I with Tavg-Low SR 3.3.2.2 SR 3.3.2.5

e. High-High 1,2(d),3P) 2 per steam line F,G SR 3.3.2.1 :4.53E6 Steam Flow SR 3.3.2.2 Ibm/hr SR 3.3.2.5 @ 785 psig Coincident Refer to Function I (Safety Injection) for all initiation functions and with Safety requirements.

Injection R.E. Ginna Nuclear Power Plant 3.3.2-7 Amendment 97

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

5. Feedwater Isolation

a. Automatic 1,2(e),3(e) 2 trains E,G SR 3.3.2.7 NA Actuation.

Logic and Actuation Relays

b. SG Water 1,2(e),3(e) 3 per SG F,G SR 3.3.2.1 _*91.15%

Level-High SR 3.3.2.2 SR 3.3.2.5

c. Safety Refer to Function I (Safety Injection) for all initiation functions and Injection requirements.

R.E. Ginna Nuclear Power Plant 3.3.2-8 Amendment 97

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

6. Auxiliary Feedwater (AFW)

a. Manual Initiation AFW 1,2,3 1 per pump N SR 3.3.2.4 NA Standby AFW 1,2,3 1 per pump N SR 3.3.2.4 NA

b. Automatic 1,2,3 2 trains E,G SR 3.3.2.7 NA Actuation Logic and Actuation Relays

c. SG Water 1,2,3 3 per SG FG SR 3.3.2.1 > 13.88%

Level-Low Low SR 3.3.2.2 SR 3.3.2.5

d. Safety Refer to Function 1 (Safety Injection) for all initiation functions and Injection requirements.

(Motor driven pumps only)

e. Undervoltage - 1,2,3 2 per bus D.G SR 3.3.2.3 > 2597 V Bus 11A and SR 3.3.2.5 with < 3.6 11B (Turbine sec time driven pump delay only)

f. Trip of Both 1 2 per MFW B,C SR 3.3.2.4 NA Main pump Feedwater Pumps (Motor driven pumps only)

R.E. Ginna Nuclear Power Plant 3.3.2-9 Amendment 97

ESFAS Instrumentation 3.3.2 (a)

A channel is OPERABLE when both of the following conditions are met:

1. The absolute difference between the as-found Trip Setpoint (TSP) and the previous as-left TSP is within the COT Acceptance Criteria. The COT Acceptance Criteria is defined as:

las-found TSP - previous as-left TSPI < COT uncertainty The COT uncertainty shall not include the calibration tolerance.

2. The as-left TSP is within the established calibration tolerance band about the nominal TSPR The nominal TSP is the desired setting and shall not exceed the Limiting Safety System Setting (LSSS). The LSSS and the established calibration tolerance band are defined in accordance with the Ginna Instrument Setpoint Methodology. The channel is considered operable even if the as-left TSP is non-conservative with respect to the LSSS provided that the as-left TSP is within the established calibration tolerance band.

(b) Pressurizer Pressure > 2000 psig.

(c) During CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.

(d) Except when both MSIVs are dosed and de-activated.

(e) Except when all Main Feedwater Regulating and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

R.E. Ginna Nuclear Power Plant 3.3.2-10 Amendment 97

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves

. LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings

. > 2410 psig and < 2542 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures greater than the LTOP enable temperature specified in the PTLR.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS cold leg temperature Both pressurizer safety less than or equal to the valves inoperable. LTOP enable temperature specified in the PTLR.

R.E. Ginna Nuclear Power Plant 3.4.10-1 Amendment 97

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 -NOTE -

Required to be performed within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of entering MODE 4 from MODE 5 with all RCS cold leg temperatures greater than the LTOP enable temperature specified in the PTLR for the purpose of setting the pressurizer safety valves under ambient (hot) conditions only provided a preliminary cold setting was made prior to heatup.

Verify each pressurizer safety valve is OPERABLE in In accordance with accordance with the Inservice Testing Program. the Inservice Following testing, lift settings shall be within +/- 1%. Testing Program R.E. Ginna Nuclear Power Plant 3A4.10-2 Amendment 97

CSTs 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tanks (CSTs)

LCO 3.7.(6 The CSTs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST water volume not A.1 Verify by administrative 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> within limit, means OPERABILITY of backup water supply.

AND A.2 Restore CST water volume 7 days to within limit.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I SR 3.7.6.1 Verify the CST water volume is >_24,350 gal. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> R.E. Ginna Nuclear Power Plant 3.7.6-1 Amendment 97