Text

Technical Specifications Pages Re Relaxed Axial Offset Control (RAOC) & Surveillance Methodologies
	ML060590549
Person / Time
Site:	Beaver Valley
Issue date:	02/27/2006
From:	; Plant Licensing Branch III-2
To:	;
References
	TAC MC5904, TAC MC5905
	Download: ML060590549 (19)
	v • d • e

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.1.3.4 3/4.1.3.5 3/4.1.3.6 Rod Drop Time..............................

Shutdown Rod Insertion Limit................

Control Rod Insertion Limits.................

PAGE 3/4 3/4 3/4 1-22 1-23 1-23a 3/4.2 POWER 3/4.2.1 3/4.2.2 3 /4.2. 3 3/4.2.4 3/4.2.5 DISTRIBUTION LIMITS, AXIAL FLUX DIFFERENCE.

HEAT FLUX HOT CHANNEL FACTOR................

NUCLEAR ENTHALPY HOT CHANNEL FACTOR.........

QUADRANT POWER TILT RATIO...................

DNB PARAMETERS..............................

3/4 3/4 3/4 3/4 3/4 2-1 2-2 2-8 2-10 2-12 I

3/4.3 INSTRUM.

3/4.3.1 3/4.3.2 ENTATION REACTOR TRIP SYSTEM INSTRUMENTATION.........

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................

MONITORING INSTRUMENTATION Radiation Monitoring........................

Remote Shutdown Instrumentation.............

Accident Monitoring Instrumentation.........

3/4 3-1 3/4 3-14 3/4.3.3 3/4.3.3.1 3/4.3.3.5 3/4.3.3.8 3/4 3/4 3/4 3-33 3-44 3-50 BEAVER VALLEY -

UNIT 1 IV Amendment No. 274

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 'AFD)

LIMITING CONDITION FOR OPERATION 3.2.1 The AFD in % flux difference units shall be maintained within the limits(l) specified in the COLR.

APPLICABILITY:

MODE 1 with THEF2AL POWER 2 50% RTP(2).

ACTION:

With AFD not within limits, reduce THERMAL POWER to < 50% of RTP within 30 minutes.

SURVEILLANCE REQUIREMENTS 4.2.1.1 Verify AFD within limits for each OPERABLE excore channel at least once per 7 days.

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

(2) See Special Test Exception 3.10.2 I

I BEAVER VALLEY -

UNIT 1 3 /4 2-1 Amendment No.274

POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ(Z)

LIMITING CONDITION FOR OPERATION 3.2.2 FQ(Z), as approximated by Fg(Z) and F6(Z), shall be within the limits specified in the COLR.

APPLICABILITY:

Mode 1.

ACTION:

a.

With F6(Z) not within 'Limit~'):

1.

Reduce THERMAL POWER 2 1% RTP for each 1% FQ(Z)

C exceeds the limit: within 15 minutes after each F6(Z) determination; and

2.

Reduce the Power Range Neutron Flux--High Trip c

Setpoints Ž 1% for each 1% FQ(Z) exceeds the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each F6(Z) determination; and

3.

Reduce the Overpower AT Trip Setpoints 2 1% for each c

1% F6(Z) exceeds the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each c

FQ(Z) determination; and

4.

Perform Surveillance Requirements 4.2.2.2 and 4.2.2.3 prior to increasing THERMAL POWER above the limit of Action a.l.

5.

Otherwise, be in MODE 2 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With F6(Z) not within limits (2):

1.

Reduce AFD limits > 1% for each 1% FJ(Z) exceeds limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and (1) Action a.4 shall be completed whenever Action a is entered.

(2) Action b.4 shall be completed whenever Action b is entered.

BEAVER VALLEY -

UNIT 1 3/4 2 -2 Amendment No.274

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (continued)

2.

Reduce the Power Range Neutron Flux-High Trip Setpoints 2 1% for each 1% that the maximum allowable power of the AFD limits is reduced within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3.

Reduce the Overpower AT Trip Setpoints 2 1% for each 1% that the maximum allowable power of the AFD limits is reduced within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

4.

Perform Surveillance Requirements 4.2.2.2 and 4.2.2.3 prior to increasing THERMAL POWER above the maximum allowable power of the AFD limits.

5.

Otherwise, be in MODE 2 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

C 4.2.2.2 FQ(Z) shall be verified to be within the limit according to the following schedule (3):

a.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP; and

b.

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 > 10% RTP, the THERMAL POWER at which C

FQ(Z) was last verified; and C.

At least once per 31 Effective Full Power Days thereafter.

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

BEAVER VALLEY -

UNIT 1 3 /4 2 -3 Amendment: No. 274

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (continued) 4.2.2.3 FQc(Z) shall be verified to be within the limit (4) according to the following schedule (3):

a.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP; and

b.

Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ELfter achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which w

FQ(Z) was last verified; and

c.

At least once per 31 Effective Full Power Days, thereafter.

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

C (4) If measurements indicate that the maximum over z of IF6(Z)/K(Z)]

has increased since the previous evaluation F6(Z):

a.

Increase F6(Z) by the greater of a factor of 1.02 or by an w

appropriate factor specified in the COLR and reverify FQ(Z) is within limits, or

b.

Repeat Surveillance Requirement 4.2.2.3 once per 7

Effective Full Power Days until Note (4)a above is met or two successive flux maps indicate that the maximum over z C

of [ FQ(Z) /K (Z) I has not increased.

BEAVER VALLEY -

UNIT 1 3,14 2-4 (next page is 3/4 2-8)

Amendment No. 274 I

POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR -

Fi LIMITING CONDITION FOR OPERATION 3.2.3 FRH shall be limited by the following relationship:

FXH < CFAH [1 + PFAH (1-P)]

where:

CFAH =

FXH limit at RATED THERMAL POWER provided in the CORE OPERATING LIMITS REPCRT, PFAH =

The Power Factor multiplier for FRH provided in the CORE OPERATING LIMITS

REPORT, and THERMAL POWER

=

RATED THERMAL POWER APPLICABILITY:

MODE 1.

ACTION:

With FXH exceeding its limits:

a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to < 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

Demonstrate thru in-core mapping that FXH is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit: or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER, subsequent POWER OPERATION may proceed provided tha:

FXH is demonstrated through in-core mapping to be within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL power, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95% or greater RATED THERMAL POWER.

BEAVER VALLEY -

UNIT 1 3./4 2-8 Amendment: No.274

POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT PATIO (OPTR)

LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall be less than or equal to 1.02.

APPLICABILITY:

MODE 1 greater than 50 percent of RATED THERMAL POWER. (1)

ACTION:

With the QPTR not within the limit:

a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , reduce THERMAL POWER greater than or equal to 3 percent from ELATED THERMAL POWER (RTP) for each 1 percent of QPTR greater than 1.00, and

b.

Within 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, perform Surveillance Requirement 4.2.4 and reduce THERMAL POWER greater than or equal to 3 percent from RTP for each 1 percent of QPTR greater than 1.00, and

c.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and once per 7 days thereafter, perform Surveillance Requirements 4.2.2.2, 4.2.2.3, and 4.2.3.1, and

d.

Prior to increasing THERMAL POWER above the limit of ACTION a or b above, re-evaluate the safety analyses and confirm the results remain valid for the duration of operation under this condition, and

e.

After ACTION d above is completed and prior to increasing THERMAL POWER above the limit of ACTION a or b above, normalize the excore detectors to show a QPTR less than or equal to 1.02, and

f.

After ACTION e above is completed and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching RTP or within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit of ACTION a or b above, perform Surveillance Requirements 4.2.2.2, 4.2.2.3, and 4.2.3.1.

g.

Otherwise, reduce THERMAL POWER to less than cr equal to 50 percent RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(1) See Special Test Exception 3.10.2.

BEAVER VALLEY -

UNIT 1 3,'4 2-10 Amendlment. No.- 274

TABLE 4.3-1 (Continued)

NOTATION (1)

If not performed in previous 31 days.

(2)

Heat balance only, above 15 percent of RATED THERMAL POWER.

(3)

At least once every 31 Effective Full Power 'Days (EFPD) compare incore to excore axial imbalance above 50 percent of RATED THERMAL POWEF.

Recalibrate if absolute difference greater than or equal to 3 percent.

(4)

(Not Used)

(5)

Each train tested every other month.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-10.

(8)

Below P-6, not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into MODE 3.

(9)

(Not Used)

(10)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).

(11)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12)

Local manual shunt trip prior to placing breaker in service.

(13)

Automatic undervoltage trip.

(14)

With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(15)

Surveillance Requirements need not be performed on alternate detectors until connected and required for OPERABILITY.

BEAVER VALLEY -

UNIT 1 3,14 3 -13 Amendment No.274

ADMINISTRATIVE CONTROLS 6.9.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

- - - - NOTE - - - - - - - - -

A single submittal may be made for a multi-unit station.

The submittal should combine those sections that are co:mmon to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year 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 unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I Section IV.B.1.

6.9.4 DELETED 6.9.5 CORE OPERATING LIMITS REPORT (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 COL.R for the following:

2.1.1 Reactor Core Safety Limits 3.1.3.5 Shutdown Rod Insertion Limits 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference-Relaxed Axial Offset Control 3.2.2 Heat Flux Hot Channel Factor-FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Fact:or-F AH 3.2.5 DNB Parameters 3.3.1.1 Reactor Trip System Instrumentation -

Overtemperature and Overpower AT Setpoint Parameter Values BEAVER VALLEY -

UNIT 1 6-1 8 Amendment No. 274

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

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:

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).

WCAP-8745-P-A, Design Bases for the Thermal Ove:ftemperature AT and Thermal Overpower AT trip functions, September 1986.

WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5

(Revision 1),

"Code Qualification Document for Best Estimate LOCA Analysis,"

March 1988 (Westinghouse Proprietary).

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-HydrELulic Safety Analysis," October 19S9.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).

WCAP-15025-P-A, "Modified WRB-2 Correlation, IVRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.

As described in reference documents listed above, when an initial assumed power level of 102% of rated thermal power is specified in a previously approved method, 100.6% of rated thermal power may be used when input for reactor thermal power measurement of feedwater flow is by the leading edge flow meter (LEFM).

Caldon, Inc.

Engineering Report-80P, "Improving Thermal Power Accuracy and PlELnt Safety While Increasing Operating Power Level Using the LEFM"TM System," Revisicn 0, March 1997.

BEAVER VALLEY -

UNIT 1 6-1 9 Amendment: No. 274

3/4.2 POWER DISTRIBUTION LIMITS!

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)

LIMITING CONDITION FOR OPERATION 3.2.1 The AFD in % flux difference units shall be maintained within the limits(l) specified in the COLR.

APPLICABILITY:

MODE 1 with THERMAL POWER 2 50% RTP().

ACTION:

With AFD not within limits, reduce THERMAL POWER to < 50% of RTP within 30 minutes.

SURVEILLANCE REQUIREMENTS 4.2.1.1 Verify AFD within limits for each OPERABLE excore channel at least once per 7 days.

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

(2)

See Special Test Exception 3.10.2.

BEAVER VALLEY -

UNIT 2

-/4 2-1 (Next page is 3/4 2-4)

Amendment No-155 I

POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-FQL(

LIMITING CONDITION FOR OPERATION 3.2.2 FQ(Z), as approximated by FQ(Z) and FQ(Z), shall be within the limits specified in the COLF..

APPLICABILITY:

MODE 1 ACTION:

a.

With F6(Z) not within :Limit(1):

1.

Reduce THERMAL POWER 2 1% RTP for each 1% F6(Z) exceeds the limit within 15 minutes after each Fg(Z) determination; and

2.

Reduce the Power Range Neutron Flux--High Trip C

Setpoints 2 1% for each 1% FQ(Z) exceeds the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each F6(Z) determination; and

3.

Reduce the Overpower AT Trip Setpoints 2 :% for each 1% F6(Z) exceeds the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each F6(Z) determination; and

4.

Perform Surveillance Requirements 4.2.2.2 and 4.2.2.3 prior to increasing THERMAL POWER above the limit of Action a.1.

5.

Otherwise, be in MODE 2 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With F6(Z) not within limits (2):

1.

Reduce AFD limits 2 1% for each 1% FV(Z) exceeds limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and (1) Action a.4 shall be completed whenever Action a is en:ered.

(2) Action b.4 shall be completed whenever Action b is entered.

BEAVER VALLEY -

UNIT 2

-3/4 2-4 Amendment No. 155

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

2.

Reduce the Power Range Neutron Flux--High Trip Setpoints 2 1% for each 1% that the maximum allowable power of the AFD limits is reduced within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3.

Reduce the Overpower AT Trip Setpoints > :L% for each 1% that the maximum allowable power of the AFD limits is reduced within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

4.

Perform Surveilla.nce Requirements 4.2.2.2 and 4.2.2.3 prior to increasing THERMAL POWER above t he maximum allowable power of the AFD limits.

5.

Otherwise, be in MODE 2 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F6(Z) shall be verified to be within the limit according to the following schedule (3):

a.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP; and

b.

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 C

F6(Z) was last verified; and

c.

At least once per 31 Effective Full Power Days thereafter.

(3)

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

BEAVER VALLEY -

UNIT 2 3 /4 2-5 Amendment No. 155

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) w 4.2.2.3 FQ(Z) shall be verified to be within the limit(9) according to the following schedule (3):

a.

Once after each refueling prior to THERMAL POWER exceeding 75% RTP; and

b.

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 F6(Z) was last verified; and C.

At least once per 31 Effective Full Power Days, thereafter.

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

C (4) If measurements indicate that the maximum over z of IIFQ(Z)/K(Z)]

has increased since the previous evaluation F6(Z):

a.

Increase Fw(Z) by the greater of a factor of 1.02 or by an w

appropriate factor specified in the COLR and reverify FQ(Z) is within limits, or

b.

Repeat Surveillance Requirement 4.2.2.3 once per 7

Effective Full Power Days until Note (4)a above is met or two successive flux maps indicate that the maximum over z C

of [FQ(Z)/K(Z)] has not increased.

BEAVER VALLEY -

UNIT 2 3 /4 2 -6 Amendment No.155

POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR -

F2H LIMITING CONDITION FOR OPERATION 3.2.3 FNH shall be limited by the following relationship:

FNH < CFAH [1 + PFAH (l-P)]

where:

CFAH

=

The FN limit at RATED THERMAL POWER provided in the CORE OPERATING LIMITS

REPORT, PFAH =

The Power Factor multiplier for FNH provided in the CORE OPERATING LIMITS

REPORT, and THERMAL POWER P

=

RATED THERMAL POWER APPLICABILITY:

MODE 1 ACTION:

With FNH exceeding its limit:

a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to < 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

Demonstrate through in-core mapping that FNH is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 5 percent of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER, subsequent POWER OPERATION may proceed provided that FNH is demonstrated through in-core mapping to be within its limit at a nominal 50 percent of RATED THERMAL POWER prior to exceeding this THERMAL power, at a nominal 75 percent of RATED THERMAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95 percent or greater RATED THERMAL POWER.

BEAVER VALLEY -

UNIT 2

3/4 2-7 Amendment: No.155

POWER DISTRIBUTION LIMITS OUADRANT POWER TILT RATIO (OPTR)

LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall be less than or equal to 1.02.

APPLICABILITY: MODE 1 greater than 50 percent of RATED THERMAL POWER. (1)

ACTION:

With the QPTR not within the limit:

a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , reduce THERMAL POWER greater than or equal to 3 percent from RATED THERMAL POWER (RTP) for each 1 percent of QPTR greater than 1.00, and

b.

Within 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 thereaf ter, perform Surveillance Requirement 4.2.4 and reduce THERMAL POWER greater than or equal to 3 percent from RTP for each 1 percent of QPTR greater than 1.00, and

c.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and once per 7 days thereafter, perform Surveillance Requirements 4.2.2.2, 4.2.2.3, and 4.2.3.1, and

d.

Prior to increasing THERMAL POWER above the limit of ACTION a or b above, re-evaluate the safety analyses and confirm the results remain valid for the duration of operation under this condition, and

e.

After ACTION d above :Ls completed and prior to increasing THERMAL POWER above the limit of ACTION a or b above, normalize the excore detectors to show a QPTR less than or equal to 1.02, and

f.

After ACTION e above is completed and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching RTP or within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER above the limit: of ACTION a or b above, perform Surveillance Requirements 4.2.2.2, 4.2.2.3, and 4.2.3.1.

g.

Otherwise, reduce THERMAL POWER to less than or equal to 50 percent RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(1) See Special Test Exception -3.10.2.

BEAVER VALLEY -

UNIT 2 3/4 2-9 Amendment No.155

TABLE 4.3-1 (Continued)

TABLE NOTATION (1)

If not performed in previous 31 days.

(2)

Heat balance only, above 15 percent of RATED THERMAL POWER.

(3)

At least once every.31 Effective Full Power Days (EFPD) compare incore to excore axial imbalance above 50 percent of RATED THERMAL POWER.

Recalibrate if absolute difference greater than or equal :o 3 percent.

(4)

(Not Used).

(5)

Each train tested every other month on a STAGGERED TEST BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-10.

(8)

Below P-6, not required to be performed for source range instrumentation prior to entering MODE 3 from MC)DE 2 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into MODE 3.

(9)

(Not Used)

(10)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip c:rcuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).

(11)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12)

Local manual shunt trip prior to placing breaker in service.

(13)

Automatic undervoltage trip.

(14)

With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(15)

Surveillance Requirements need not be performed on alternate detectors until connected and required for OPERABILITY.

BEAVER VALLEY -

UNIT 2 3/4 3-13 Amendment No.155

]

ADMINISTRATIVE CONTROLS REPORTING REOUIREMENTS (Continueds 6.9.4 DELETED 6.9.5 CORE OPERATING LIMITS REPORT (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:

2.1.1 Reactor Core Safety Limits 3.1.3.5 Shutdown Rod Insertion Limits 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference-Relaxed Axial Offset Control 3.2.2 Heat Flux Hot Channel Factor-FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor-FNAH 3.2.5 DNB Parameter 3.3.1.1 Reactor Trip System Instrumentation -

Overtemperature and Overpower AT setpoint parameter values

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:

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (Westinghouse Proprietary).

BEAVER VALLEY -

UNIT 2 6-19 Amendment No.155

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (ContinuedjL WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.

WCAP-12945-P-A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1),

"Code Qualification Document for Best Estimate LOCA Analysis,"

March 1998 (Westinghouse Proprietary).

WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).

As described in reference documents listed above, when an initial assumed power level of 102% of rated thermal power is specified in a previously approved method, 100.6% of rated thermal power may be used when input for reactor thermal power measurement of feedwater flow is by the leading edge flow meter (LEFM).

Caldon, Inc.

Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMV System," Revision 0, March 1997.

Caldon, Inc.

Engineering Report-160P, "Supplement to Topical Report ER-80P::

Basis for a Power Upra-e With the LEFM1 System," Revision 0, May 2000.

BEAVER VALLEY -

UNIT 2 6-2 0 Amendment: No.155

v t e Letter Sequence Other
TAC:MC5904, (Approved, Closed) TAC:MC5905, (Approved, Closed)
Initiation Acceptance... Supplement Administration Questions 6 July 2005 Answers 11 February 2005 Results Approval Other: ML060590549
MONTHYEAR2006-02-27 [Table View]

ML060590549

Text

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