ML042680047

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Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints
ML042680047
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/22/2004
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML042680047 (39)
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Text

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.0 SLs and SL Violations 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 2 1.17 for the WRB-1 correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 50800F, decreasing by 580 F per 10,000 MWD/MTU of burnup.

2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained

  • 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

R.E. Ginna Nuclear Power Plant 2.0-1 Amendment -85

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1I 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).

9B 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.1 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 8 5

RTS Instrumentation 3.3.1 CONDITION l REQUIRED ACTION l_COMPLETION TIME D. As required by Required D.A 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 ReduceTHERMALPOWER 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-1 I amps.

by Table 3.3.1-1.

OR

- 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 2 8% 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 8 5

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME 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 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 495

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 ReduceTHERMAL 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 ReduceTHERMAL 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 M or N not met.

R As required by Required R1 Action A.1 and referenced - ______ ___------

by Table 3.3.1-1. - NOTE-by TablThe 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.

Placechaneliti . 6 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 85

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION ICOMPLETION TIME Q. Required Action and 0.1 ReduceTHERMAL 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 ReduceTHERMALPOWER 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 8 5

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME T. As required by Required T.1 Action A.1 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 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 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 q5'

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.

R.E. Ginna Nuclear Power Plant 3.3.1-7 Amendment '8 5

RTS Instrumentation 3.3.1 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 /> 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 2 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 2 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 2 3%. power days (EFPD)

SR 3.3.1.4 Perform TADOT. 31 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 -NOTE-Not required to be performed until 7 days after THERMAL POWER is 2 50% RTP, but prior to exceeding 90% RTP following each refueling.

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

R.E. Ginna Nuclear Power Plant 3.3.1-8 Amendment 8 5

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY 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 -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 SR 3.3.1.9 ---

NOTE -

Setpoint verification is not required.

Perform TADOT. 92 days SR 3.3.1.10 --- - -

-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 '8 5

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE I

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 s 112.27%

SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.10 I b. Low 1(c), 2 4 DG SR 3.3.1.1 s 29.28%

SR 3.3.1.8 RTP SR 3.3.1.10

3. Intermediate Range 1(c), 2 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 F,G SR 3.3.1.1 (d) 2 (e)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10 3 (b), 4 (b), 5 (b) 2 H.1 SR 3.3.1.1 (d)

SR 3.3.1.7 SR 3.3.1.10 3 (f), 4 (f), 5 (f) 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 R.E. Ginna Nuclear Power Plant 3.3.1-1 0 Amendment 85

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)

6. Overpower AT 1.2 4 D,G SR 3.3.1.1 Refer to SR 3.3.1.3 Note 2 I SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10
7. Pressurizer Pressure I a. Low 1 (9) 4 K,L SR 3.3.1.1 Ž 1791.3 SR 3.3.1.7 psig SR 3.3.1.10 I b. High 1,2 3 D,G SR 3.3.1.1 s 2396.2 SR 3.3.1.7 psig SR 3.3.1.10 I 8. Pressurizer Water 1.2 3 D,G SR 3.3.1.1 s 96.47%

Level-High SR 3.3.1.7 SR 3.3.1.10

9. Reactor Coolant Flow-Low I a. Single Loop 1 (h) 3 per loop M,O SR 3.3.1.1 2 89.86%

SR 3.3.1.7 SR 3.3.1.10 I b. Two Loops 1°') 3 per loop K,L SR 3.3.1.1 2Ž89.86%

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 N,O SR 3.3.1.11 NA
b. Two Loops 1U) 1 per RCP K,L SR 3.3.1.11 NA R.E. Ginna Nuclear Power Plant 3.3. 1-1 1 Amendment 85 -

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)

11. Undervoltage- 1(9) 2 per bus K,L SR 3.3.1.9 (d)

Bus 11A and 11B SR 3.3.1.10 I 12. Underfrequency- 1 (9) 2 per bus KL SR 3.3.1.9 Ž57.5 HZ Bus 11A and 11B SR 3.3.1.10 I 13. Steam Generator 1, 2 3 perSG D,G SR 3.3.1.1 213.88%

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

14. Turbine Trip
a. Low Autostop 1(k)(l) 3 PRQ SR 3.3.1.10 (d)

Oil Pressure SR 3.3.1.12

b. Turbine Stop 1(kl)0 2 P.C SR 3.3.1.12 NA Valve Closure
15. Safety Injection (SI) 1,2 2 RV SR 3.3.1.11 NA Input from Engineered Safety Feature Actuation System (ESFAS)

R.E. Ginna Nuclear Power Plant 3.3.1 -1 2 Amendment 85

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 SETTINGSt a)

16. ReactorTripSystem Interlocks
a. Intermediate 2 (e) 2 SV SR 3.3.1.10 2 5E-11 Range SR 3.3.1.13 amp Neutron Flux, P-6 I b. Low Power 1(g) 4 (power range SYV SR 3.3.1.10 s 8.0% RTP Reactor Trips only) SR 3.3.1.13 Block, P-7 I c. Power Range 1 (h) 4 SV SR 3.3.1.10 < 49.0%

Neutron Flux, SR 3.3.1.13 RTP P-8 I d. Power Range 4 Sv SR 3.3.1.10 s 50.0%

Neutron Flux, SR 3.3.1.13 RTP p.9 l 1 (k) 4 SV SR 3.3.1.10 s 8.0% RTP SR 3.3.1.13 I e. Power Range 1(c), 2 4 Sv SR 3.3.1.10 2 6.0% RTP Neutron Flux, SR 3.3.1.13 P-1 0

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 WX SR 3.3.1.4 NA
18. Reactor Trip 1,2 l each per RTB Uv SR 3.3.1.4 NA Breaker 3 (b), 4 (b), 5 (b) 1 each per RTB WX SR 3.3.1.4 NA Undervoltage and Shunt Trip Mechanisms
19. Automatic Trip Logic 1,2 2 trains RV SR 3.3.1.5 NA 3 (b), 4(b), 5 (b) 2 trains WX SR 3.3.1.5 NA R.E. Ginna Nuclear Power Plant 3.3.1 -13 Amendment 8 5'

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 s 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 TSP. 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) 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. In this condition, the Source Range Neutron Flux function does not provide a reactor trip, only indication.

(g) THERMAL POWER 2Ž8.5% RTP.

(h) THERMAL POWER 2 50% RTP.

(i) THERMAL POWER 2 8.5% RTP and Reactor Coolant Flow-Low (Single Loop) trip Function blocked.

() THERMAL POWER Ž 8.5% 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 S 20".

(I) THERMAL POWER Ž 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 85

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

  • ATO {K1 + K2 (P-P') - K3 (T-T') [(1+'Is) / (1+r2 s)] - f(Al))

Where:

AT is measured RCS AT, "F.

ATO is the indicated AT at RTP, "F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, "F.

1' is the nominal Tavg at RTP, OF.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure, psig.

K, 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.

'r1 is the measured lead time constant, [*] seconds.

T2 isthe 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(AI)= 0 when qt - qb is s [*]% RTP f(Al) = [*] {(qt - qb) - [} when qt - qb is > [*]% RTP

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

R.E. Ginna Nuclear Power Plant 3.3.1 -15 Amendment 85-

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 s ATo {K4 - K5 (T-T') - K6 [(V3 sT) / (r3s+1)] - f(Al)1 Where:

AT is measured RCS AT, "F.

ATO is the indicated AT at RTP, "F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, "F.

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:

[*]/'F for T < T' and;

[*]/OF for T 2 T'.

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

[*'/OF for increasing T and;

[*]/OF for decreasing T.

T3 is the measured impulse/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(Al) = [* when qt - qb is < [*]% RTP f(AI) = [*] {(qt - qb) - [*]} when qt - qb is > [*]% RTP

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

R.E. Ginna Nuclear Power Plant 3.3.1-16 Amendment 8 5

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 Restoretrain 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 85

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.

G2 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.

I. 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 85

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 required by Required N.1 Declare associatedAuxiliary 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."

R.E. Ginna Nuclear Power Plant 3.3.2-3 Amendment 85

ESFAS Instrumentation 3.3.2 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 SR 3.3.2.4@5°°'~-NOTE- -OE 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 85

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 l,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 s4.61 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 2Ž1744.8 Pressure-Low SR 3.3.2.2 psig SR 3.3.2.5 SR 3.3.2.6
e. Steam Line 1,2 , 3 (b) 3 per steam line L,M SR 3.3.2.1 2Ž393.8 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 8 5

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 1 H,K SR 3.3.2.4 NA pushbutton
b. Automatic 1,2,3.4 2 trains IK SR 3.3.2.7 NA Actuation Logic and Actuation Relays
c. Containment 1.2,3.4 3 per set J,K SR 3.3.2.1 *31.11 psig Pressure-High SR 3.3.2.2 (narrow High SR 3.3.2.5 range)
  • 28.6 psig (wide range)
3. Containment Isolation I 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 I 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 8 5

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 1 per loop D,G SR 3.3.2.4 NA Initiation
b. Automatic 1 ,2(d),3(d) 2 trains EG SR 3.3.2.7 NA Actuation Logic and Actuation Relays l c. Containment 1 .2(d),3td) 3 FG SR 3.3.2.1 s 18.0 psig Pressure-High SR 3.3.2.2 High SR 3.3.2.5 l d. High Steam 1,2(d).3(d) 2 per steam line F,G SR 3.3.2.1 s 0.42E6 Flow SR 3.3.2.2 Ibm/hr SR 3.3.2.5 @ 1005 psig Coincident Refer to Function I (Safety Injection) for all initiation functions and with Safety requirements.

Injection and Coincident 1 ,2(d),3(d) 2 per loop E.G SR 3.3.2.1 2 544.980 F with Tg-Low SR 3.3.2.2 I SR 3.3.2.5

e. High-High 1,2(d),3(d) 2 per steam line F.G SR 3.3.2.1
  • 3.63E6 Steam Flow SR 3.3.2.2 Ibm/hr SR 3.3.2.5 @ 755 psig Coincident Refer to Function 1 (Safety Injection) for all initiation functions and with Safety requirements.

Injection R.E. Ginna Nuclear Power Plant 3.3.2-7 Amendment 85

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 EG SR 3.3.2.7 NA Actuation Logic and Actuation Relays I b. SG Water 1 .2 (e),

3 (e) 3 per SG F.G SR 3.3.2.1 S 91.15%

Level-High SR 3.3.2.2 SR 3.3.2.5

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

R.E. Ginna Nuclear Power Plant 3.3.2-8 Amendment 8 5

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 I 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 EG SR 3.3.2.7 NA Actuation Logic and Actuation Relays I c. SG Water 1,2,3 3 per SG FG SR 3.3.2.1 2 13.88%

Level-Low Low SR 3.3.2.2 SR 3.3.2.5

d. Safety Refer to Function I (Safety Injection) for all Initiation functions and Injection requirements.

(Motor driven pumps only)

I e. Undervoltage - 1,2,3 2 per bus D,G SR 3.3.2.3 2 2597 V Bus 11A and SR 3.3.2.5 with s3.6 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 85

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 TSP. 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 2 2000 psig.

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

(d) Except when both MSIVs are closed 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 3.3.2-1 0 Amendment 85

LOP DG Start Instrumentation 3.3.4 3.3 INSTRUMENTATION 3.3.4 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.4I Each 480 V safeguards bus shall have two OPERABLE channels of LOP DG Start Instrumentation.

APPLICABILITY: MODES 1, 2,3, and 4, When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources - MODES 5 and 6."

ACTIONS

-NOTE-Separate Condition entry is allowed for each 480 V safeguards bus.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more 480 V A.1 Place channel(s) in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> bus(es) with one channel inoperable.

B. Required Action and B.1 Enter applicable Immediately associated Completion Condition(s) and Required Time of Condition A not Action(s) for the associated met. DG made inoperable by LOP DG start OR instrumentation.

One or more 480 V bus(es) with two channels inoperable.

R.E. Ginna Nuclear Power Plant 3.3.4-1 Amendment 95'

LOP DG Start Instrumentation 3.3.4 SURVEILLANCE REQUIREMENTS

-NOTE-When a channel is placed in an inoperable status solely for the performance of required Surveillances, entry into the associated Conditions and Required Actions may be delayed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided the second channel maintains LOP DG start capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform TADOT. 31 days SR 3.3.4.2 Perform CHANNEL CALIBRATION with Limiting 24 months I Safety System Settings (LSSS)(a) for each 480 V bus as follows:

a. Loss of voltage LSSS 2 371.6 V and
  • 378.0 V with a time delay of 2 1.64 seconds and
  • 2.61 seconds.
b. Degraded voltage LSSS 2 419.6 V and
  • 424.4 V with a time delay of 2 30.7 seconds and

< 1589 seconds (@ 416.8 V) and 2 25.1 seconds and

  • 494.9 seconds (@ 368 V).

(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 CHANNEL CALIBRATION Acceptance Criteria. The CHANNEL CALIBRATION Acceptance Criteria is defined as:

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

2. The as-left TSP Is within the established calibration tolerance band about the nominal TSP. The nominal TSP is the desired setting and shall not exceed the 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.

R.E. Ginna Nuclear Power Plant 3.3.4-2 Amendment 85

Containment Ventilation Isolation Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Containment Ventilation Isolation Instrumentation LCO 3.3.5 i The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.

I APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitoring A.1 Restore the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> channel inoperable. channel to OPERABLE status.

B. B.1 Enter applicable Conditions Immediately

_ - ___ -_ and Required Actions of

- NOTE- LCO 3.6.3, "Containment Only applicable in MODE Isolation Boundaries," for 1, 2, 3, or4. containment mini-purge isolation valves made One or more Functions inoperable by isolation with one or more manual instrumentation.

or automatic actuation trains inoperable.

Both radiation monitoring channels inoperable.

OR Required Action and associated Completion Time of Condition A not met.

R.E. Ginna Nuclear Power Plant 3.3.5-1 Amendment 8 5

Containment Ventilation Isolation Instrumentation 3.3.5 CONDITION REQUIRED ACTION COMPLETION TIME C. C.1 Place and maintain Immediately

____--- _ containment purge and

- NOTE - exhaust valves in closed Only applicable during position.

CORE ALTERATIONS or movement of irradiated O fuel assemblies within containment.

-- containme C.2 Enter applicable Conditions Immediately and Required Actions of One or more Functions LCO 3.9.3, "Containment with one or more manual Penetrations," for or automatic actuation containment purge and trains inoperable. exhaust isolation valves made Inoperable by OR isolation instrumentation.

Both radiation monitoring channels inoperable.

OR Required Action and associated Completion Time for Condition A not met.

R.E. Ginna Nuclear Power Plant 3.3.5-2 Amendment 85

Containment Ventilation Isolation Instrumentation 3.3.5 SURVEILLANCE REQUIREMENTS

-NOTE-Refer to Table 3.3.5-1 to determine which SRs apply for each Containment Ventilation Isolation Function.

SURVEILLANCE FREQUENCY SR 3.3.5.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.5.2 Perform COT. 92 days SR 3.3.5.3 Perform ACTUATION LOGIC TEST. 24 months SR 3.3.5.4 Perform CHANNEL CALIBRATION. 24 months R.E. Ginna Nuclear Power Plant 3.3.5-3 Amendment -8 5

Containment Ventilation Isolation Instrumentation 3.3.5 Table 3.3.5-1 Containment Ventilation Isolation Instrumentation LIMITING APPLICABLE MODES SAFETY AND OTHER SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS REQUIREMENTS SETTINGS(a)

I 1. Automatic Actuation 2 trains SR 3.3.5.3 NA Logic and Actuation Relays

2. Containment Radiation I a. Gaseous 1 SR 3.3.5.1 (C)

SR 3.3.5.2 SR 3.3.5.4

b. Particulate I SR 3.3.5.1 (c)

I 1,2,3,4,(b)

SR 3.3.5.2 SR 3.3.5.4

3. Containment Isolation - Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a, for all Manual Initiation initiation functions and requirements.
4. Containment Spray - Refer to LCO 3.3.2, 'ESFAS Instrumentation," Function 2.a, for all Manual Initiation initiation functions and requirements.
5. Safety Injection Refer to LCO 3.3.2, 'ESFAS Instrumentation," Function 1,for all Initiation functions and requirements.

R.E. Ginna Nuclear Power Plant 3.3.5-4 Amendment '8 5

Containment Ventilation Isolation Instrumentation 3.3.5 (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 TSP. 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) During CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.

(c) Per Radiological Effluent Controls Program.

R.E. Ginna Nuclear Power Plant 3.3.5-5 Amendment :8 5

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem/yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance, waste processing, and refueling).

This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report shall be submitted on or before April 30 of each year.

5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring activities for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

R.E. Ginna Nuclear Power Plant 5.6-1 Amendment 85

Reporting Requirements 5.6 5.6.3 Radioactive Effluent Release Rerort The Radioactive Effluent Release Report covering the operation of the plant shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant. The material provided shall be consistent with the objectives outlined in the ODCM and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Monthly ODeratina Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

The following administrative requirements apply to the COLR:

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

2.1, 'Safety Limits (SLs)";

LCO 3.1.1, SHUTDOWN MARGIN (SDM)";

LCO 3.1.3, 'MODERATOR TEMPERATURE COEFFICIENT (MTC)-;

LCO 3.1.5, 'Shutdown Bank Insertion Limit";

LCO 3.1.6, 'Control Bank Insertion Limits';

LCO 3.2.1, "Heat Flux Hot Channel Factor (Fo(Z))";

LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor (FNH)Y; LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)';

LCO 3.3.1, "Reactor Protection System (RPS) Instrumentation";

LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1, "Boron Concentration."

R.E. Ginna Nuclear Power Plant 5.6-2 Amendment 8

Reporting Requirements 5.6

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985.

(Methodology for 2.1, LCO 3.1.1, LCO 3.1.3, LCO 3.1.5, LCO 3.1.6, LCO 3.2.1, LCO 3.2.2, LCO 3.2.3, and LCO 3.9.1.)

2. WCAP-1 3677-P-A, "10 CFR 50.46 Evaluation Model Report:

WCOBRA/TRAC Two-Loop Upper Plenum Injection Model Updates to Support ZIRLOTM Cladding Option," February 1994.

(Methodology for LCO 3.2.1.)

3. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974.

(Methodology for LCO 3.2.3.)

4. WCAP-1 261 0-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995.

(Methodology for LCO 3.2.1.)

5. WCAP 11397-P-A, "Revised Thermal Design Procedure,"

April 1989.

(Methodology for LCO 3.4.1 when using RTDP.)

6. WCAP-1 0054-P-A and WCAP-1 0081 -A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

(Methodology for LCO 3.2.1.)

7. WCAP-10924-P-A, Volume 1, Revision 1, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1:

Model Description and Validation Responses to NRC Questions," and Addenda 1,2,3, December 1988.

(Methodology for LCO 3.2.1.)

8. WCAP-10924-P-A, Volume 2, Revision 2, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 2:

Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addendum 1, December 1988.

(Methodology for LCO 3.2.1.)

9. WCAP-1 0924-P-A, Volume 1, Revision 1, Addendum 4, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1: Model Description and Validation, Addendum 4: Model Revisions," March 1991.

(Methodology for LCO 3.2.1.)

R.E. Ginna Nuclear Power Plant 5.6-3 Amendment 65

Reporting Requirements 5.6

10. WCAP-8745, "Design Basis for the Thermal Overpower Delta T and Thermal Overtemperature Delta T Trip Functions,"

March 1977.

(Methodology for LCO 3.3.1.)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

The following administrative requirements apply to the PTLR:

a. RCS pressure and temperature limits for heatup, cooldown, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

LCO 3.4.3, 'RCS Pressure and Temperature (P/T) Limits"

b. The power operated relief valve lift settings required to support the Low Temperature Overpressure Protection (LTOP) System, and the LTOP enable temperature shall be established and documented in the PTLR for the following:

LCO 3.4.6, "RCS Loops - MODE 4";

LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled';

LCO 3.4.10, 'Pressurizer Safety Valves"; and LCO 3.4.12, 'LTOP System."

c. The analytical methods used to determine the RCS pressure and temperature and LTOP limits shall be those previously reviewed and approved by the NRC in NRC letter, "R.E. Ginna - Acceptance for Referencing of Pressure Temperature Limits Report, Revision 2 (TAC No. M96529)," dated November 28, 1997. Specifically, the methodology is described in the following documents:

R.E. Ginna Nuclear Power Plant 5.6-4 Amendment 85'

Reporting Requirements 5.6

1. Letter from R.C. Mecredy, Rochester Gas and Electric Corporation (RG&E), to Document Control Desk, NRC, Attention: Guy S. Vissing, "Application for Facility Operating License, Revision to Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)

Administrative Controls Requirements," Attachment VI, September 29, 1997, as supplemented by letter from R.C.

Mecredy, RG&E, to Guy S. Vissing, NRC, "Corrections to Proposed Low Temperature Overpressure Protection System Technical Specification," October 8,1997.

2. WCAP-14040-NP-A, "Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," Sections 1 and 2, January, 1996.
d. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for revisions or supplement thereto.

R.E. Ginna Nuclear Power Plant 5.6-5 Amendment 8 5

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