ML19347F683
| ML19347F683 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 05/13/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319A872 | List: |
| References | |
| NUDOCS 8105260020 | |
| Download: ML19347F683 (14) | |
Text
F n
[(
+
S UNITED STATES
}
NUCLEAR REGULATORY COMMISSION r,
j wAswinatom o.c.20sss
~
- .../
INDIANA AND MICHICAN ELECTRIC CCMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLAE UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. DPR-74 1
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated May 1,1981 as supplemented by letter dated May 7,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccmmission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
810526o O SO
2.
Accordingly, the license is amended by changes ~to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-74 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amend.nent No. 31, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
70R THE NUCLEAR REGULATORY COMMISSION t
'e
.' a Operating Reactors.B anch No. 1 Division of Licens) g
Attachment:
Changes to the Technical Specificatipns Date of Issuance:
g y 3,3 1981
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3 3/42-3*
3/4 2-4 3/4 2-4 3/4 2-17 3/4 2-17 3/4 2-18
,'3/4.2-18 3/4 2-19 3/4 2-19 3/4 3-7 3/4 3-7*
3/4 3-8 3/4 3-8 3 3/4 2-1 B 3/4.2-l*
B 3/4 2-2 8 3/4 2-2
- No change, provided for convenience 4
4 e
k
3/4.2 POWER DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE (AFD)
LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within a
+5% target band (flux difference units) about the target flux difference.
t APPLICABILITY: MODE 1 ABOVE 50% RATED THERMAL POWER
- ACTION:
3 a.
With the indicated AXIAL FLUX DIFFERENCE outside of the +5% target band about the target flux difference and with THERMAL P6WER:
i 1.
Above 81% of RATED THERMAL POWER, within 15 minutes:
a)
Either restore the indicated AFD to within the target band limits, or b)
Reduce THERMAL POWER to less than 81% of RATED THERMAL POWER.
2.
Between 50% and 81% of RATED THERMAL POWER:
a)
POWER OPERATION may continue provided:
1)
The indicated AFD has not been outside of the +5% target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation culiiulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
-l 2)
The indicated AFD is within the limits shown on Figure
'l 3.2-1.
Otherwise, reduce THERMAL POWER to less than l
50% of RATED THERMAL P0 DER within 30 minutes and reduce l
the Power Range Neutron Flux-High Trip Setpoints to <
55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b)
Surveillance testing of the Power. Range Neutron Flux Channels may be performed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1.
A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> operation may be accumulated with the AFD outside of the target band during this testing without penalty deviation.
- See Special Test Exception 3.10.2 D. C. COOK - UNIT 2 3/4 2-1 Amendment No. 31 4
~
POWER DISTRIBUTION LIMITS ACTION:
(Continued) c)
Surveillance testing of the APDMS may be performed pursuant to Specification 4.3.3.7.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1.
A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of operation may be accumulated with the AFD outside of the target band during this testing without penalty devi-ation.
b.
THERMAL POWER shall not be increased above 81% of RATIO THERMAL POWER l' unless the indicated AFD is within the +5% target bano and ACTION 2.a) 1), above has been satisfied.
c.
THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of the +5% taroet band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the' previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
a.
Monitoring the indicated AFD for each OPERABLE excore channel:
1.
At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status.
l l
b.
Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each l
OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX l
DIFFERENCE Monitor Alarm is inoperable.
The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.
i l
D. C. COOK - UNIT 2 3/4 2-2 Amendment No. 31
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) '
The indicated AFD shall be considered outside of its +5% target 4.2.1.2 or 2 of 3 OPERABLE excore channels a're indicating band when at least 2 of 4 the AFD to be outside the target band. Penalty deviation outside of the
+5% target band shall be accumulated on a time basis of:
One minute penalty deviation for each one minute of POWER a.
OPERATION outside of the target band at THEFJGL POWER levels equal to or above 50% of RATED THERMAL POWER, and
" One-half minute penalty deviation for each one minute of POWER b,
OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.
The target flux difference of each OPERABLE excore channel 4.1.1. 3 shall b'e determined by measurement at least once per 92 Effective Full "ower Days. The provisions of Specification 4.0.4 are not applicable.
The target flux difference shall La updated at least once per 4. 2.1.4 31 EffectiYe Full Power Days by either determining the target flux difference pursuant to 4,2.1.3 above or by linear interpolation between the most.recently measured value and 0 percent at the end of the cycle i
life; The provisions of Specification 4,0.4 are not applicable.
\\
I I
I i
I D. C. CLOK. UNIT 2 3/42-3 Amendment He.10 L
- c::
W 120 c:.is w=o He<=a
==<
- u. = 5 o==
- b$
100 H
( -9, 81 )
( 9,81) 80 f
n-UNACCEPTABLEE- /
'. juNACCEPTABLE.
OPERATION F/
' t OP5 RAT!ON
[
60 i
g
_ /; ACCEPTABLE 55iOPERATIONg
?
(-2 5, 50)
- (25,50) 40
- i 20 1
0 50
-40
-30
-20
-10 0
10 20 30 40 50 FLUX DIFFERENCE (All %
FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THr9 MAL POWER D. C. COOK - UrtIT 2 3/4 2 4 Amendment No. 31
POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following
~
relationship:
[F (Z)]* = dI*993 EKI2Il j
(R )(P ) (.103) (1 + o3)(1.07) j L
Where:
a.
F (Z) is the normalized axial power distribution from thimble 3
j at core elevation Z.
b.
PL is the fraction of RATED THERMAL POWER.
c.
K(Z) is the function obtained from Figure 3.2-2 for a given core height location,
~
d.
I1, for thimble j, is determined from at least n=6 in-core flux 4maps covering the full configuration of permissible rod patterns above 91% of RATED THERMAL POWER in accordance with:
n d
id
.]
i Where:
Meas F
R)=
gg 9
[Fjj(Z)] max and [F43 (Z)] Max is the maximum value of the norm 511 zed axial distribution at elevation Z from thimble j in map i which has a measured peaking factor without. uncertainties or densification eas l
allowance of F D. C. COOK - UNIT 2 3/4 2-17 Amendment No. 31
POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued) is the standard deviation associated with thimble j, expressed as a o4 fraction or percentage of R, and is derived from n flux maps d
from the relationship below, or 0.02 (2%) whichever is greater.
ej=[hi1(R3-R43)2]/2 R
3 The factor 1.07 is comprised of 1.02 and 1.05 to account for the axial power distribution instrumentation accuracy and the measure-using the movable detector ment uncertainty associated with Fg system respectively.
(
The factor 1.03 is the engineering uncertainty factor.
APPLICABILITY: MODE 1 above 91% OF RATED THERMAL POWER.
ACTION:
With a F (Z) factor exceeding [F (Z)]3 by < 4 percent, reduce a.
j j
i THERMAL POWER one percent for every percent by which the F (Z) j factor exceeds its limit within 15 minutes and within the next or reduce THERMAL POWER f6 91d,(or) factor to within its limit two hours either reduce the F Z less of RATED THERMAL POWER.
With a F (Z) factor exceeding [F (Z)]s by > 4 percent, reduce b.
j j
THERMAL POWER to 91% or less of RATED THERMAL POWER within 15
+
minutes.
- The APDMS nay be out of service when surveillance for determining power distribution maps is being performed.
(
D. C. COOK - L' NIT 2 3/4 2-18 Amendment.No. 31 i
n
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMEATS F)(Z) shall be determined to be within its limit by:
4.2.6.1 a.
Either using the APDMS to monitor the thimbles required per Specifica-tion 3.3.3.6 at the following frequencies.
1.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and 2.
Immediately and at intervals of 10, 30, 60, 90, 120, 240 and 480 minutes following:
a)
Increasing the THERMAL POWER above 91% of RATED THERMAL POWER, or b)
Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.
b.
Or using the movable incore detectors at the following fre-j quencies when the APDMS is inoperable:
1.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and ll 2.
At intervals of 30, 60, 90, 120, 240 and 480 minutes following:
a b
a)
Increasing the THERMAL POWER above 91% of RATED THERMAL
]
POWER, or l
b)
Movement of control bank "D" more than an accumulated total of 5 steps in any one direction.
4.2.6.2 When the movable incore detectors are used to monitor F)(Z), at least l
2 thimbles shall be monitored and an F)(Z) accuracy equivalent to that obtained j
from the APDMS shall be maintained.
l l
l}
D. C. COOK - UNIT 2 3/4 2-19 Amendment No. 31
TABLE 3.3-1 (Continued)'
ACTION 8 - With the number of OPERABLE channels one less than the Total Numbers of Channels and with the THERMAL POWER level above P-7 place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may continue until. performance of the next required CHANNEL FUNCTIONAL TEST.
ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel associated with an operating loop 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 per Specification
- 4. 3.1.- l. l.
ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Operation below P-8 may continue pursuant to ACTION 11.
ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 12 - With the numb'er of channels "PERABLE one less than required i
by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the 1
reactor trip breakers.
REACTOR TRIP SYSTEM INTERLOCKS l-l DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intemediate Range P-6 prevents or defeats Neutron Flux Channels < 6 x 10-j) the manual block of amps.
source range reactor trip.
1 i
D. C. COOK - UNIT 2
,.t 3-7 1
I i
N,."
TABLE 3.3-1 (Continued)
DESIG"ATION CONbITIONANDSETPOINT FUNCTION P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels : 11% of RATED the automatic block of THERMAL POWER 'cc 1 of 2 Turbine reactor trip on:
Low impulse chamber pressure channels flow in more than one
> 66 psia.
primary coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.
P-8 With 2 of 4 Power Range Neutron P-8 prevents or defeats THERMAL POWER.-
the automatic block of Flux channels > 51% of RATED reactor trip on low coolant flow in a single loop.
P-10 With 3 of 4 Power range neutron P-10 prevents or defeats flux channels. < 9% of RATED the manual bleek of:
Power THERMAL POWER.
range low setpoint reactor, trip, Intermediate
- range reactor trip, and intermediate range rod stops.
Provides input to P-7.
i l
l D. C. COOK - UNIT 2 3/4 3-8 Amendment No. 31 1
3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integ-rity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by:
(a) maintaining the calculated DNBR in the core at or above design during nonnal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature andIn cladding mechanical properties to within assumed design criteria.
addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200*F a
is not excee'ded.
The definitions of certain hot channel and peaking factors as used in these specifications are as follows:
F (Z)
Heat Flux Hot Channel Factor, is defined as the maximum local g
heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances on fuel pellets and rods.
F)H Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the
~
highest integrated power to the average rod power.
Radial Peaking Factor, is defined as the ratio of peak
- Y(Z) power density to average power density in the hori: ental F
i plane at core elevation Z.
]
3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)
The limits on AXIAL FLUX DIFFERENCE assure that the F Z) upper bound envelope of 1.99 times the nomalized axial peaking fa(ctor is
{
exceeded during either nomal operation or in the event of xenon redis-4
- ribution following power changes.
t' Target flux difference is determined at equilibrium xenon conditions.
The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their nomal position for steady state operation at high power levels. ' The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup con-ditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level.
The periodic updating of the target flux difference value is necessary to reflect core burnup censiderations.
D.C. COOK - UNIT 2 B 3/4 2-1 Amendment No. 70,17 1
~
1
)
r 3/4.2 POWER DISTRIBUTION LIMITS
'ASES i
Although it is intended that the plant will be operated with the AXIAL I
FLUX DIFFERENCE within the +5% target band about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels.
This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time f
duration of the deviation is limited. Accordingly, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation l
limit cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels between 50% and 81% of RATED THERMAL POWER.
For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.
Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and pro-vides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the target band and the THERMAL POWER is l
greater than 81% of RATED THERMAL POWER.
During operation at THERMAL POWER l
levels between 50% and 81% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectivt,1y.
l Figure B 3/4 2-1 shows a typical monthly target band.
l l t
a l
8 3/4 2-2 Amendment No. 31 D. C. Cook - Unit 2
[:
---