ML20059C459
| ML20059C459 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/23/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059C461 | List: |
| References | |
| NUDOCS 9009050067 | |
| Download: ML20059C459 (13) | |
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' UNITED STATES g.
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. NUCLEAR REGULATORY COMMISSION:
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UNION ELECTRIC COMPANY-
'CALLAWAY-PLANT, UNIT 1 DOCKET NO. STN 50-483-Y AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No. 56 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Commission) has found.that:
A.
The application-for amendment filed by Union Electric Company-(UE, the licensee) dated March 6, 1990 complies with the standards =
and requirements of-the Atomic Energy Act of 1954,_as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by 1
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 comon 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 Comission's regulations and all applicable requirements have-been-satisfied.
2.
Accordingly, the license-is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-t graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to j
read as follows i
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9009050067 900s23 PDR ADOCK 050004G3 l'
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I (2)~ Technical Specifications and Environmental Protection Plan The Technical Specifications contained'in Appendix A, as revised-through Amendment.No.56, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical: Specifications'and the Environmental'-
Protection Plan.
3.
This license amendment is effective immediately to be implemented upon startup from the 1990 refueling outage. The licensee will imediately
= inform the Comission, in writing, of the implementation date.
FOR THE NUCLEAR REGULATORY COMMISSION W
ohn H. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
- Specifications Date of~ issuance: August 23, 1990
b ATTACHMENT TO LICENSE AMENDMENT N0.56~
OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain margina~ 'ines indicating the area aof change. Corresponding overleaf pages are provicea to maintain document completeness.
REMOVE INSERT 2-4 2-4 B 2-4 B 2-4 3/4 3-2 3/4 3-2 3/4 3-7 3/4 3-7 3/4 3-9 3/4 3-9 I
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SAFETY' LIMITS A,ND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1-The Reactor Trip System Instrumentation and Interlocks Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.,
APPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
a.
With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the.value shown in the Allowable Value.
column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1'until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R-+ S < TA Where:
Z=
The value from Column 2 of Table 2.2-1 for the affected channel, R=
The "as measured" value (in percent span) of rack error for the.
affected channel, S=
Eitherthe"asmeasured"value(inpercentspan)ofthesensor error, or. the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.
I CALLAWAY - UNIT 1 2-3
TABLE 2.2.<
- REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS'-
nF TOTAL SENSOR ERROR
{
FUNCTIONAL UNIT ALLOWANCE (TA)
Z_
,(S1 TRIP SETPOINT ALLOWABLE VALUE-1.
Manual. Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux E
a.
High'Setpoint 7.5 4.56 0
<109% of RTP*
<l12.3% of RTP*
b.
Low Setpoint 8.3 4.56-0 125% of RTP*
<28.3% of RTP*
1 3% of RTP* with 6
3.
Power Range, Neutron Flux, 2.4 0.5 0,
14% of RTP* with High Positive Rate a time constant a time constant.-
>2 seconds
>2 seconds 4.
Deleted 5.
Intermediate Range, 17.0 8.41 0
<25% of RTP*
<35.3% of RTP*
Neutron Flux 7
1 6 x 10s cps 6.
Source Range, Neutron Flux 17.0 s.01 0 110s cps 1
7.
Overtemperature AT 9.3
(
7 1.83 See Note 1 See Note 2
+1.24***
8.
Overpower AT 5.7 1.46 1.8 See Note 3 See Note 4 9.
Pressurizer Pressure-Low
- 5. 0 2.21 2.0
>l885 psig
>1874 psig 1 00 psig 24 10.
Pressurizer Pressure-High 7.5 4.96 1.0 12385 psig g
11.
Pressurizer Water Level-8.0 2.18-2.0
<92% of instrument
<93.8% of instrument-High span span 12.
Reactor Coolant Flow-Low 2.5 1.38 0.6
>90% of loop
>88.8% of loop E
Einimum measured Minimum measured fl ow**
flow **
.M g
- RTP = RATED THERMAL POWER
- Minimum Measured Flow = 95,660 gpm g
- Two Allowances (temperature and pressure, respectively).
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y 2.'2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the' Reactor trips' are set for each functional unit.
The Trip
.Setpoints have been selected to ensure that the core and' Reactor Coolant System are prevented from exceeding their Safety Limits during normal operation and design basis anticipated operational occurrences and to assist the Engineered Safety Features Actuation System in mitigating the consequences of accidents.
The:Setpoint for a. Reactor. Trip System or interlock function is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.
To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allow-able Values for the Reactor Trip Setpoints have been specified in Table 2.2-1.'
Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is-found to exceed the Allowable Value.
The methodology of this option utilizes the "ss measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncer-tainties of the instrumentation to measure'the process variable and the uncer-
.tainties in calibrating the instrumentatica.
In Equation 2.2-1, Z + R + S 1
the interactive effects of the errors in the rack and the sensor, and the "1 TA, as l'
' measured" values of the errors are considered.
Z, as specified in Table 2.2-1, L
in percent span, is the statistical summation of errors-assumed in the analysis
. excluding those associated with the sensor and rack drift and the accuracy of
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their measurement. TA or Total Allowance is-the difference, in percent span, between the. Trip Setpoint and the value used in the analysis for Reactor trip.
F L
l-R or Rack Error is the "as measured" deviation, in percent span, for the affected channel from the specified Trip Setpoint.
S or Sensor Error is either the "as measured" deviation of the sensor from its calibration point or the value specified:in Table 2.2-1, in percent span, from the analysis assumptions.
I:
~For functions which have multiple input values, due to more than one parameter l
providing input to the function, multiple values for S are noted which are l
applicable to the primary. input channels.
(See Westinghouse statistical set-point study for protection systems provided for justification).
Use of Equa-tion 2.2-1 allows for a sensor drift factor, an increased rack drift factor.
and provides a threshold value for REPORTABLE EVENTS.
The m'ethodology to derive the Trip Setpoints is based upon combining all of 7'
the. uncertainties in the channels.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channe1' uncertainties.
Sensors and other instrumentation utilized in these channels are expected to be capable of operat-ing within the allowances of these uncertainty magnitudes.
Rack drift in excess of the Allowable Value' exhibits the behavior that the rack has not met its allowance.
Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected.
Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of atore serious problems and should warrant further investigation.
CALLAWAY - UNIT 1 B 2-3 Amendment No. 15
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v LIMITING SAFETY SYSTEM SETTINGS-i BASES REACTORTRIPSYSTEM~INSTRUMENTATIONSETPOINTS(Continued).
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or. calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trlp System functional. diversity. The func--
tional capability at the specified trip setting is required for those antici-patory or diverse Reactor trips for which no direct credit was assumed in the safety analfsis to enhance the overall reliability of the Reactor Trip.
System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated.
This prevents the reactivity insertion that would-otherwise result from exce:sive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
The Reactor Trip System inclu' des manual Reactor trip capability.
l Power Range, Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip setting..The Low Setpoint trip provides protection during subcritical and low power operations to mitigate the consequences of a power excursion beginning from low power, and the High Setpoint trip provides protection during power
. operations to mitigate the consequences of a reactivity excursion-from all j'
power levels, o
L 1he Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THER@L POWER) and is automatically reinstated below the P-10 Setpoint.
Power Range, Neutron Flux, High Positive Rate l
The Power Range' Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a control rod drive housing.
Specifically, this trip complements' the Power Range Neutron Flux High and Low
-trips to ensure that the criteria are met for rod ejection-from mid-power.
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CALLAWAY - UNIT 1 B 2-4 Amendment No.56 i
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13/4 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEN INSTRUMENTATION
- i LIMll!NG CONDil10N FOR OPERATION 3.3.1 As a minimum, the Reactor Trip' System instrumentation channels and interlocks of Table 3.3-1.shall be OPERABLE with RESPONSE TIMES as shown in Table-3.3-2.
APPLICABILITY:. As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS i
l 4;3.1.1 Each Reactor Trip System instrumentation channel and-interlock and the automatic trip logic shall be demonstrated OPERA 8LE by the performance of
'i the Reactor Trip, System Instrumentation Surveillance Requirements specified in Table 4.3-1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at
-least once per 36' months and one channel. per function such that all channels E
.are tested at least once every N-times'18 mo'nths where N is-the total number of redundant channels in'a specific-Reactor trip function as shown in the
" Total No.'of Channels" column of. Table 3.3-1.
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Call AWAY - UNil' 1 3/4 3-1 1
l TABLE 3I3-1 h
REACTOR TRIP SYSTEM INSTRUMENTATION 5-g MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICA8LE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE
-MODES ACTION E
q 1.
1 2
1, 2 1
2 1
2-3*, 4*, 5*
10-g 2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2#
b.
Low Setpoint 4
2 3'
1###, 2 2r 3.
Power Range, Neutron Flux 4
2 3
1, 2 2#
High Positive Rate 4.
Deleted R
s y
5.
Intermediate Range, Neutron Flux 2
1 2
1###, 2 3-6.
Source Range, Neutron-Flux a.
Startup '
2-1 -28#**
1 4 b.
Shutdown 2
1 2
3**, 4, 5 5
7.
Overtemperature AT E
Four Loop Operation 4
2 3
1, 2.
6#
R
- g 8.
Overpower AT f
Four Loop Operation
-4 2
3 1, 2 6# -
E 9.
Pressurizer Pressure-Low 4
2 3
1 6#
10.
Pressurizer Pressure-High 4
2 3
1, 2 6#
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REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 5~
~
s FUNCTIONAL UNIT RESPONSE TIME i
E 1.
Manual Reactor Trip N.A.
~
--4 2.
Power Range, Neutron Flux 5 0.5 second*
m 3.
Power Range, Neutron Flux, High Positive Rate M.A.
4.
Deleted w
5.
Intermediate Range, Neutron Flux N.A.
w 6.
Source Range, Neutron Flux N.A.
7.
Overtemperature AT
$ 6.0 seconds
- 8.
Overpower AT 1 6.0 seconds
- S.
Pressurizer Pressure-Low
~
$ 2.0 seconds 6"
10.
Pressurizer Pressure-High 5 2.0 seconds S
8-11.
Pressurizer Water Level-High N.A.
@n l
g
- Neutron detectors are exempt from respense time testing. Response time of the neutron flux signal portion of the' channel-shall be MEE3ured from detector output or input to'first electronic Component.in channel.
om I
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REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME
%F 12.
Reactor Coolant Flow-i.ow E
Single Loop (Above P-8) 1 1.0 second-3 a.
b.
Two Loops (Above P-7 and below P-8) i 1.0 second 2g 13.
Steam Generator Water Level Low-Low a.
Steam Generator Water Level Low-Low (Adverse Containment Environment) 1 2.0 seconds (1) b.
Steam Generator Water Level Low-Low (Normal Containment Environment) 1 2.0 seconds (i) c.
Vessel AT (Power-1, Power-2) 1 6.0 seconds (1) w d.
Containment Pressure -
in Environmental Allowance Modifier 1 2.0 seconds (1) 14.
Undervoltage-Reactor Coolant Pumps 1 1.5 seconds
- 15. Underfrequency-Reactor Coolant Pumps 1 0.6 seconds
- 16. Turbine Trip k
a.
Low Fluid Oil Pressure N.A.
b.
Turbine Stop Valve Closure N.A.
g 17.
Safety Injection Input from ESF N.A.
h 18.
Reactor Trip System Interlocks
.N.A.
19.
Reactor Trip Breakers N. A.~
- 20. Automatic Trip ~ and Interlock Logic N.A.
1 (1) Does not include Trip. Time Delays.
Response-times noted above._ include the transmitters, 7300 f-process protection cabinets, solid state protection. cabinets, and actuation devices only.
This reflects the response times necessary for THERMAL POWER in excess of 20% RATED THERMAL POWER.
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.4 TABLE 4.3 -
U REACTORTRIPSYSTEMINhTRUMENTATIONSURVEILLANCEREQUIRENENTS
-g s
' TRIP ANALOG ACTUATING NDOES FOR-CHANNEL DEVICE
'WHICH i
E CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE' i
U FUNCTIONAL UNIT
- CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED _
o-a 1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(16)
N.A.
1, 2, 3*, 4*,_5' t
2.
Power Range, Neutron Flux l
a.
High Setpoint-S D(2, 4),
Q(14)
N.A.
N.A.
.1, 2 M(3,4),
Q(4,6),
R(4,5) b.
Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
1M, 2 ;
R 3..
Power Range, Neutron Flux, M.A.
-R(4)-
Q(14)
N.A.
N.A.
1, 2
[
High Positive Rate 4.
Deleted S.
Intermedlate Range,_
S R(4. 5)
S/U(1)
N. A. -
N.A.
1M, 2 ~
Neutron Flux 7
6.
Source Range, Neutron Flux S~
R(4,-5,12)--
S/U(1),Q(9,14)
N.A.
N.A.
^ 2N, 3, 4, 5 7.
Overtemperature AT S
R(13)
Q(14)
N.A.
~N.A.
1, 2 N.A.
N.A..
1, 2
{
8.
Overpower AT S
R Q(14) h 9.
Pressurizer Pressure-Low S-R Q(14)
- N.A.
N.A.
1 E
16.
Pressurizer Pressure-High_
S R
_ Q(14)
N.A.
N.A.
1, 2 11.
Pressurizer Water Level-High S
R Q(14)
N.A.
N.A.
1 12.
Reactor Coolant Flow-Low
-S R
Q(14)
- N.A.
N.A.
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N TABLE 4.3-I"(Continued) g
- REACTOR TRIP SYSTEM INSTRUMEfiTATION SURVEILLANCE REQUIREMENTS r-E TRIP
~ MODES
- ANALOG ACTUATING R
CHANNEL-DEVICE
'FOR WlICH'-
i CHANNEL
-CHANNEL OPERATIONAL OPERATIONAL
-ACTUATION-SURVEILLANCE d
2 FUNCTIONAL ~ UNIT C!lECK CALIBRATION-TEST-TEST
. LOGIC TEST IS REQUIRED-c
- 13. Steam Generator Water-Level Low-Low a.
Steam Generator Water ~
S R
Q (14,15)
N.A.
N. A..
1, 2 -
Level Low-Low (Adverse Containment Environment) b.
Steam Generator Water
'S R
Q (14,15)
N.A.
N.A.
1, 2'-
o2 Level Low-Low (Normal ContainmentEnvironment) w c.
Vessel AT (Power-1 S
R Q (14,15)
N.A.
N.A.
1, 2 Power-2) d.
Containment Pressure-S R
Q (14,15)'
N.A.
M.A.
1,~2-Environmental Allowance Modifier
[
- 14. Undervoltage - Reactor
.N.A.
'R M.A.
Q (14,15)
N.A.
1 g
Coolant Pumps a
k
- 15. Underfrequency - Reactor N.A.
R N.A.
Q (14)
N.A.
1 Coolant Pumps 2
P
- 16. Turbine Trip
~~
a.
Low Fluid Oil' Pressure N.A.
R-N. A. --
S/U (1,10)
N.A.
I b
b.
Turbine Stop Valve N.A.
R N.A..
S/U (1,10).
N.A.
- I Closure I
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