Text

Technical Specification Pages Re Relaxed Axial Offset Control
	ML060480244
Person / Time
Site:	Ginna
Issue date:	02/15/2006
From:	Milano P; Plant Licensing Branch III-2
To:	;
References
	TAC MC6867
	Download: ML060480244 (29)
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FQ(Z) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 FQ(Z), as approximated by FQC(Z) and FQW(Z), shall be within the limits I specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

-- ___ A.1 ReduceTHERMALPOWER 15 minutes after

- NOTE - > 1% RTP for each 1% each FQC(Z)

Required Action A.4 shallFc()eedslmt be completed whenever FQC(Z) exceeds limit. determination this Condition is entered

.___ ----___ _ AND A. FQC(Z) not within limit.

A.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each Neutron Flux - High trip FQC(Z) setpoints > 1% for each 1% determination FQC(Z) exceeds limit.

AND A.3 Reduce Overpower AT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each I AND setpoints > 1% for each 1% FQc(Z)

FQC(Z) exceeds limit. determination A.4 Perform SR 3.2.1.1 and SR Prior to increasing 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 R.E. Ginna Nuclear Power Plant 3.2. 1-1 Amendment 94

FQ(Z) 3.2.1 CONDITION REQUIRED ACTION COMPLETION TIME

_ B.1 Reduce AFD limits 2 1% for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

- NOTE -

Required Action 8. shall each 1% FQW(Z) exceeds be completed whenever limit.

this Condition is entered.

____ _________---_ AND I B. FQW(Z) not within limits.

B.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux - High trip setpoints 2 1% for each 1%

that the maximum allowable power of the AFD limits is reduced.

AND B.3 Reduce Overpower AT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months setpoints 2 1% for each 1%

that the maximum allowable power of the AFD limits is reduced.

AND B.4 Perform SR 3.2.1.1 and SR Prior to increasing 3.2.1.2. THERMAL POWER above the maximum allowable power of the AFD limits C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I associated Completion Time not met.

R.E. Ginna Nuclear Power Plant 3.2.1-2 Amendment 94

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS

- NOTE-During power escalation at the beginning each cycle, THERMAL POWER may be increased of until an equilibrium power level has been achieved, at which a power distribution map is obtained.

SURVEILLANCE FREQUENCY l SR 3.2.1.1 Verify FQC(Z) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75%

RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which FQC(Z) was last verified AND 31 EFPD thereafter R.E. Ginna Nuclear Power Plant 3.2.1-3 Amendment 94

FQ(Z) 3.2.1 SURVEILLANCE FREQUENCY SR 3.2.1.2 - NOTE -

If measurements indicate that the maximum over z [FFC(Z) / K(Z)]

has increased since the previous evaluation of FQC(Z):

a. Increase FQW(Z) by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify FQW(Z) is within limits or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either

a. above is met or two successive flux maps indicate that the maximum over z [F. )C(Z) / K(Z) ]

has not increased.

Verify FQW(Z) is within limit. Once after each I refueling prior to THERMAL POWER exceeding 75%

RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which FQW(Z) was last verified AND I 31 EFPD thereafter R.E. Ginna Nuclear Power Plant 3.2.1-4 Amendment 94

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits spcified in the COLR.

- NOTE -

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

l APPLICABILITY: MODE 1 with THERMAL POWER 2 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. AFD not within limits. A.1 ReduceTHERMALPOWER to < 50% RTP.

30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE l FREQUENCY Verify AFD within limits for each OPERABLE excore 7 days I SR 3.2.3.1 channel.

R.E. Ginna Nuclear Power Plant 13.2.3-1 Amendment 94

QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

I LCO 3.2.4 The QPTR shall be < 1.02.

APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP.

ACTIONS CONDITION I REQUIRED ACTION ICOMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each I AND POWER 2 3% from RTP for QPTR each 1% of QPTR > 1.00. determination I A.2 Determine QPTR Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3 Perform SR 3.2.1.1, SR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 3.2.1.2 and SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND A.4 Reevaluate safety analyses Prior to increasing and confirm results remain THERMAL POWER valid for the duration of above the limit of operation under this Required Action A. 1 condition.

AND R.E. Ginna Nuclear Power Plant 13.2.4-1 Amendment 94

QPTR 3.2.4 CONDITION REQUIRED ACTION COMPLETION TIME A.5

- NOTE -

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required Action A.6 shall be completed whenever Required Action A.5 is performed Normalize excore detectors Prior to increasing to restore QPTR to within THERMAL POWER limit. above the limit of Required Action A.1 AND A.6

- NOTE -

Perform Required Action I A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1, SR Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 3.2.1.2, and SR 3.2.2.1. after achieving equilibrium conditions at RTP not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of Required Action A.1 l B. Required Action and B.1 ReduceTHERMALPOWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to

50% RTP.

Time of Condition A not met.

R.E. Ginna Nuclear Power Plant 3.2.4-2 Amendment 94

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I SR 3.2.4.1 - NOTE -

I 1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER I < 75% RTP, the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this I Surveillance.

Verify QPTR is within limit by calculation. 7 days SR 3.2.4.2 ----

- NOTE -

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER I > 75% RTP.

Perform SR 3.2.1.1, SR 3.2.1.2 and SR 3.2.2.1. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months R.E. Ginna Nuclear Power Plant :3.2.4-3 Amendment 94

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).

OR Two source range channels inoperable.

B. As required by Required B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not AND met.

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

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

R.E. Ginna Nuclear Power Plant 3.3.1-1 Amendment 94

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months E. As required by Required E.1 ReduceTHERMALPOWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to Ž 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

R.E. Ginna Nuclear Power Plant .3.3. 1-2 Amendment94

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter R.E. Ginna Nuclear Power Plant 3.3.1-3 Amendment 94

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months L. Required Action and L.1 ReduceTHERMALPOWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

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

by Table 3.3.1-1.

0. Required Action and 0.1 ReduceTHERMALPOWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion to < 50% 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months R.E. Ginna Nuclear Power Plant 3.3.1-4 Amendment 94

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

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

C)R Q.2.2 Reduce THERMAL POWER 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

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

S. As required by Required S.1 Verify interlock is in required 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function channel(s) inoperable.

R.E. Ginna Nuclear Power Plant :3 .3. 1-5 Amendment 94

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other train is OPERABLE.

2. One RTB may be bypassed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for maintenance on undervoltage or shunt trip mechanisms, provided the other train is OPERABLE.

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

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

AND U.2 IRestore trip mechanism to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

V. Required Action and V.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced mechanism to OPERABLE discovery of two by Table 3.3.1-1. status upon discoveryoftwo inoperable trip RTBs with inoperable trip mechanisms mechanisms.

AND R.E. Ginna Nuclear Power Plant 3.3.1-6 Amendment 94

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME W.2 Restore trip mechanism or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 ------------ ------

- NOTE -

Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 250% RTP.

Compare results of calorimetric heat balance 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Ž 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 94

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY 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.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reducing power < 6% RTP.

2. Not required for source range instrumentation until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 R.E. Ginna Nuclear Power Plant 3.3.1-8 Amendment 94

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.1O - NO-E -

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 94

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

a. High 1,2 4 D,G SR 3.3.1.1

112.27%

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

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(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,l SR 3.3.1.1 (d)

SR 3.3.1.7 SR 3.3.1.10 3(), 4(0, 5(f) I 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 ,t D,G SR 3.3.1.1 Refer to I SR 3.3.1.7 Note 2 SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1 -10 Amendment 94

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 1 (g) 4 K,L SR 3.3.1.1 2 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 s 96.47%

Level-High SR 3.3.1.7 SR 3.3.1.10

9. Reactor Coolant Flow-Low

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

b. Two Loops 3 per loop K,L SR 3.3.1.1 2 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 N,O SR 3.3.1.11 NA

b. Two Loops 10) I 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 11 B SR 3.3.1.10

12. Underfrequency- 1 (g) 2 per bus K,L SR 3.3.1.9 2 57.5 HZ Bus 11A and 11B SR 3.3.1.10 R.E. Ginna Nuclear Power Plant :3.3.1-1 1 Amendment 94

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 per SG D,G SR 3.3.1.1 2 13.88%

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

14. Turbine Trp

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

Oil Pressure SR 3.3.1.12

b. Turbine Stop 1(k)(1) 2 PRQ 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 94

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. Reactor Trip System Interlocks

a. Intermediate 2 (e) 2 Sy SR 3.3.1.10 Ž5E-11 Range SR 3.3.1.13 amp Neutron Flux, P-6

b. Low Power 1 (g) 4 (power range SV SR 3.3.1.10 5 8.0% RTP Reactor Trips only) SR 3.3.1.13 Block, P-7

c. Power Range 1 (h) 4 SV SR 3.3.1.10 < 49.0%

Neutron Flux, SR 3.3.1.13 RTP P-8

d. Power Range 1 (1) 4 Sv SR 3.3.1.10 < 50.0%

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

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-10

17. Reactor Trip 1,2 2 trains TV 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 1 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 R,V 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 94

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 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 Ž 8.5% RTP.

(h) THERMAL POWER Ž 50% RTP.

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

(j) THERMAL POWER 2 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 < 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 13.3.1 -14 Amendment 94

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+' 1s) / (1+t 2s)] - f1(AI)}

I Where:

AT is measured RCS AT, OF.

ATo is the indicated AT at RTP, 'F.

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.

T2 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.

f1 (Al) = [*] {[*] - (qt - qb)} when qt - qb S [*]% RTP f1(Al) = 0% of RTP when [*] % RTP < qt - qb s [*]% RTP f1 (Al) = [*] {(qt - qb) - [*]} when qt - 'lb > [*]% RTP

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

R.E. Ginna Nuclear Power Plant 3.3.1 -15 Amendment 94

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

ATo {K4 - K5 (T-T') - K6 [(t3sT) / (T3 s+1 )]- f2(Al)}

Where:

AT is measured RCS AT, IF.

ATo 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 < T' and;

[*]/OF for T 2 T'.

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

[*]/OF for increasing T and;

[*]/OF for decreasing T.

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

f 2 (AI)= [*]

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

R.E. Ginna Nuclear Power Plant 3.3.1-16 Amendment 94

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 Deleted 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.

5.6.3 Radioactive Effluent Release Report 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 Deleted R.E. Ginna Nuclear Power Plant 5.6-1 Amendment 94

Reporting Requirements 5.6 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 (FQ(Z))";

LCO 3.2.2, 'Nuclear Enthalpy Rise Hot Channel Factor (FNAH)n; 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."

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.)

R.E. Ginna Nuclear Power Plant 5.6-2 Amendment 9 4

Reporting Requirements 5.6

3. WCAP-1 0216.-P-A, Rev. 1A, "Relaxation of Constant Axial Control / FQ Surveillance Technical Specification," February 1994.

(Methodology for LCO 3.2.1 and LCO 3.2.3.)

4. WCAP-12610-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995.

(Methodology for LCO 3.2.1.)

5. WCAP 11 397-P-A, "Revised Thermal Design Procedure,"

April 1989.

(Methodology for LCO 3.4.1 when using RTDP.)

6. WCAP-1 )054-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, Addendurn 4: Model Revisions," March 1991.

(Methodology for LCO 3.2.1.)

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.

R.E. Ginna Nuclear Power Plant 5.6-3 Amendment 94

Reporting Requirements 5.6 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (P LR)

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, ARCS 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:

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 Coolclown Limit Curves,' Sections 1 and 2, January, 1996.

R.E. Ginna Nuclear Power Plant 5.6-4 Amendment 94

Reporting Requirements 5.6

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 9 4

v t e Letter Sequence Other
TAC:MC6867, Delete SR Frequencies Based on Inoperable Alarms (Open)
Initiation Request, Request Acceptance, Acceptance Administration Questions 11 August 2005 Answers Results Approval... Other: ML060190605, ML060480244, ML061240036, ML061240563, ML061440090
MONTHYEAR2005-09-19 [Table View]

ML060480244

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