ML20101Q326
| ML20101Q326 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/09/1992 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20101Q324 | List: |
| References | |
| NUDOCS 9207140241 | |
| Download: ML20101Q326 (11) | |
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ATTACHMENT PROPOSED TECHN1 CAL SPECIFICATION AND RESPECTIVE SAFETY ANALYSCS t
.IN THE MATTER OF AMENDING LICENSE NO. NFP-6 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE. UNIT TWO DOCKET No. 50-368 l
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DESCRfPTION OF PROPOSED CHANGES The proposed Technica. Specl(ications (TS) changes revise TS Table 2.2-1 Reactor Protective Instrumentation Trip Setpoint 1.1mits and TS Table 3.3-4 Engineered Safety Feature /.ctuation System Instrumentation Trip Values as follows:
- 1) TS Table 2.2-1 a) change Containment Pressure - !!!gh Trip Setpoint from
$ 18.4 psia to read $ 18.3 psia.
s b) change Containment Pressure - High Allowable Value from
$ 19.024 psia to read $ 18.490 psia,
- 2) TS Table 3.3 a) change Safety Injection (SIAS) Containment Pressure - liigh Trip Setpoint from $ 18.4 psia to read 5 18.3 psia, b) change Safety injection (SIAS) Containment Pressure - High Allowarte Vatue from $ 19.024 psia to read $ 18.490 psia, c) change Containment Spray (CSAS) Containment Pressure-t High-High Allowable Value from $ 23.624 psia to read 3 23.490 pela, d) change Containment Isolation (CIAS) Containment Pressure -
High Trip Setpoint from $ 18.4 psia to read $ 18.3 psia, c) change Containment Isolation (CIAS) Containment Pressure -
High Allowable Value from $ 19.024 pala to read $ 18.490-
- psia, f) change Containment Cooling (CCAS) Containment Pressure -
High Trip Value from $ 18.4 psia to read 5 18.3 psia, and g) change Containment Cooling (CCAS) Containment' Pressure.-
High Allowable Value from $ 19.024 psia to read 3 18.490 psia.
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IIACKGROUND The four (4) transmitters for narrow range containment building pressure provide input signals to the Reactor Protection Syst.cm (RPS) and Engineered
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Safety Feature Actuation System (ESFAS) port ions of the Plant Protective System (PPS), and are used in the gene rat irm of the following trips and actuations:
1)
RPS liigh Containment Pressure Trip, 2)
Initiation of the Safety injection Actuot. ion Signal (SI AS) portion
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of ESFAS on liigh Containment Proshare, 3)
Initiation of the Containtnent Isolation Actuation Signel (CIAS) portion of ESFAS on liigh Containnent Pressure, 4)
Initiation of the Containment Cooling Actuation Signal (CCAS) portion of ESPAS on liigh Containtnent Pressure, and 5)
Initiation of the Containment Spray Actuation Signal (CSAS) port. ion of ESPAS on High-liigh Containment Pressure.
The narrow range containment pressure transmitters are also used as one of the inputs necessary for ensur.ing conpliance with TS 3.6.1.4 requirements for containment building pressure, tnmperature, and humidity as determined from TS Figure 3.6-1 Containment Internal Pressure vs.
Containment Average Air Temperature.
In addition to the four (4) narrow range containment building pressure transmitters, the ANO-2 containment building is also equipped with two (2)
NRC Reg Guide 1.97 wide range (0 to 210 psia) containment building pressure 4
transmitters,
,a The existing narrow ra: go containment building pressure transmitters require
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replacement due to transmitter obsolescence, spare parts unavailability, and end of environmenM1 ; qualified life.
The existing Rosemount 1153 series A range code 6 pressure transmitters will be replaced with Rosemount 1153 series D range code 5 pressure transmitters.
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p DISC.VSSION OF CilANGES
- The existing Rosemount 1153 series A range code 6 narrow rar.ge containment building pressure transmitters have a calibrated range of 0-70 psia.
Using the Rosemount 1153 series D range code 6 pressure t rnnsmit.ters with a 0-70 psia range would have resulted in a large apparent reduction in operating margin-with regard to TS related RPS and ESFAS liigh and liigh-liigh contain-ment building pressure trip / actuation setpoints.
This reduction in operat-ing margin with regard t.o the TS setpoints was attributed to au Ir e ase in instrument loop crrors caused by the use of currently accepted loop error methodology and calculation assumptions.
The statistical method of the square root of the sum of squares was used to determine the random error on a component level and for the loop.
Non-random errors were combined alge-braically with the random error term-to establish total error. Although ANO has not committed to strict comp 1 mce with the requirements of ISA-S67.04-1988 ' "Setpoints for Nuclear hafet -Related Instrumentation Used in Nuclear Power Plants," these guidt Y were considered in calculating the loop- _ errors, : periodic ** arrors E), and allowable - values associated with the narrow range containment building pressure transmitters.
. As _ part of_a coordinated = effort to reduce instrument uncertainty, it was determined that - the calculated loop error magt.udes for the replacement pressure transmitters could be reduced by using a smaller calibrated range span and by using a lower range code.
As a -result, the replacement Rosemount transmitters (1153 series D) will use a range code 5 instead of a range code 6, and will be calibrated for a 0-27 psia range inst.ead of a 0-70 psin range.
- This smaller range presents no conflict for the existing liigh or liigh-lligh b
setpoints af ter subtracting the calculated errors from the actual pressure limits. The narrow range containment building pressure transmitters are not used for integrated leak rate testing _ (ILRT) and, _ therefore are. not required to read containment building pressure at the test pressure for-the ILRT..The 0-27. psia range remains above al1 associated setpoints and higher pressure _ monitoring (in excess of 27 psia) of the. containment building pressure is still available by way of the two (2)--NRC Reg Guide 1.97 wide range containment buiIding pressure transmitters.
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In order to account for the slightly larger loop o-ror magnitC es calculated I
for the replacement containment building pressure t.ansmitters (the I
Rosemount 1153 series D range code 5) as compared to the existing transmit-ters' (the Rosemount 1153 series A range code 6), it is necessary to reduce the TS setpoints listed in TS Table 2.2-1 and TS Table 3.3-4 for the following setpoints:
1)
RPS Trip on liigh Containment Pressure, 2)
ESFAS actuation of Sl AS on liigh Containment Pressure, 3)
ESFAS actuation of CI AS on liigh Containment Pressure, and 4)
ESFAS actuation of CCAS on liigh Containment Pressure.
In addition, the Allowable Values listed in TS Table 2.2-1 and TS Table
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3.3-4 will be revised to reflect the effects of the new calculated s
instrument loop errors for the replacement transmitters and the PTE for the
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following signals:
1)
RPS Trip on liigh Containmcat Pressure 2)
ESFAS actuation of SIAS on liigh Containment Pressure, 3)
ESFAS actuation of CIAS on liigh Containment Pressure, 4)
ESFAS actuation of CCliS on liigh Containment Pressure, and 5)
ESFAS actuation of CSAS on liigh-liigh Containment Pressure.
The measurement channel information and actions listed in TS Table 3.3-1 Reactor Protective Instrumentation and TS Table 3.3-3 Engineered Safety Feature Actuation System Instrumentation are not af fected by this change.
In addition, the response times listed in TS Table 3.3-2 Reactor Protective Instrumentation Response Times and TS Table 3.3-5 Engineered Safety Features Response Times will remain unchanged as the response timns for the new transmitters are equal to the response times for the existing transmitters.
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r DETERMINATION'0F SIGNIFICANT-liAZARDS An evaluation of the proposed change has been performed in accordance with 10CFR50.91(a)(1) - regarding no significant-hazards considerations using the standards in.10CFR50.92(ch A discussion of these standards as they relate to this. amendment request follows:
Critorionf1
_ Does Not-Involve a Significent Incree.se in the Probability or Consequences of an Accident Previously Evaluated The_ containment bu'11 ding pressure parameter is used to mitigate the effects of _ an accident that causes _a release of energy into the containment building such as a secondary line break (Main Steam line or Main Feedwater line) orLa 6
-primary loss of coolant (LOCA).
The purpose of the _ containment building narrow - range pressure transmitters is to provide an input signal to _ the Containment Pressuro - liigh trip bistable in the RPS and to_ the Containment Pressure
. lligh and High-liigh trip histables in the ESFAS.
The generation of the RPS~ trip function and the ESFAS functions (SlhS, CIAS, CCAS,and CSAS) is dependent upon-the setpoint values for the liigh and/or liigh-High contain-ment building pressure bistables.
The setpoints are revised to account for the slightly larger calculated instrument - loop errors associated with the replacement transmitters.
Currently accepted loop error methodology and calculation assumptions'were used and resu ted in thnl larger instrument loop errors.
In addition, the Allowable Values associated with these functions
-are being revised to account for the offect of the loop arrors upon the PTE cand the lowered - setpoints.
The reduction of the sotpoint values maintains the analytical. limits esed in determining the existing trip / actuation val-ueS.
Therefore, this chango does M -involve a significant increase in the proba-bility or consequences of an accident previously evaluated.
Criterion 2 - Does Not Create the Possibility of a New or Different Kind of Accident from Any Previously Evaluated
' This ' change deals with; changing-the Containment-Pressuro High and High-High
= setpoints and allowablo values for-the associated functions of - the - RPS and ESFAt' due to the replacement _ of the existing containment building pressure transmitters.
No modifications to the - instrument. loop configurations will be mado, :and no additional olectrical or physical interfaces with equipment y
whose malfunction or-' failure could initiate - an accident will be created.
l The purpose of.the instrument loops to prov!de input to the systems used to l
mitigato the consequences of previously evaluated accidents is unchanged.
-The existing evaluations - and failure analyses in _ the. ANO-2 SAR are un-
-changed.
Therefore,' this chango does M create the possibility of a new or different kind Lof accident from any provf ously evaluated.
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Criterion 3 - -Does Not-Involve a Significant Reduction in the Margin of-L Safety
'The safety f unctions of the RPS and ESFAS setpoints associated with contain-
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ment. building pressure are not ' nitr red as a result of the setpoint and allowable value changes.
The setpoints and allowable values are revised to j
account. for slightly larger calculated instruwent loop errors associated with the replacement transmitters. Currently accepted loop error methodolo-gy and calculation assumptions were used and resulted in the inrger instru-men t.- loop er rors.
The-existing analytical limits used in determining the trip / actuation values are raintained with thn new setpoint values.
The measuremont-channel information and actions listed in TS Table 3.3-1 Reactor Protective Instrumentation and-TS Table 3.3-3 Engineered Safety Feature Actuation System Instrumentation are tot a f fe< ~ 3d by this change.
In addition, the response times listed Jn TS Table 3.3-2. Reactor Protective
- Instrumentation Response Times and TS Table 3.3-5 Engineered Safety Features R6sponse Times will remain unchanged as the response times for the new pressure transmitters are equal to the response times for the existing pressure transmitters.
Therefore,. this ' change does nol involve a rignificant reduction in the margin of safety.
Based-upon the reasoning presented above and the previous discussion of the amendment request, Entergy Operations has determined that the requested change does agi involve a significant hazards consideration.
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PROPOSED TECH:4ICAL SPECIFICATION CHANGES
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TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TRIP SEfPOINT ALLOWABLI VALUES FUNCTIONAL UNIT 1.
Manual Reactor Trip Not Applicable Not Applicable 2.
Linear Power Level - High a.
Four Reactor Coolant Pumps 5 110% of nTED THERMAL POWER 5 110.712% of RATED TEERMAL POWER Operating b.
Three Reactor Coolant Pumps Operating c.
Two Reactor Coolant Pumps Operating - Same Loop l
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Two Reactor Coolant Pumps Operating - Opposite Loops 3.
Logarithmic Power Level -
50.75% of RATED THERMAL POWER 5 0.819% of RATED THERMAL POWER High (1) 4.
Pressurizer Pressure - High 6 2362 psia 5 2370.887 psia l
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Pressurizer Pressure - Low 2 1766 psia (2) 2 1712.757 psia (2) l 6.
Containment Pressure - High 5 18.3 psia 5 18.490 psia 7.
Steam Generator Pressure - Low 2 751 psia (3) 2 729.613 psis (3) 8.
Steam Generator Level - Low 2 23% (4) 2 22.111 (4) blank pending NRC approval of safety analyses for operation with less than four
- These values left reactor coolant pumps operating.
2-5 Amendment No. f. 24, 65 ARKANSAS - UNIT 2
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~ TABLE 3'.3-4 ENGINEERED SAW.TY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES-i
. i ALLOWABLE..
BINCTIONAL UNIT TRIP SETPOINT~
VALUES 1.
SAFETY INJECTION (SIAS).
a.- Manual:.(Trip Btittons)
Not Applicable
~ Not igplicable l-.
b.
Containment' Pressure - High 5 18.3 psia 5 18.490 psia c.
Pressurizer Pressure -Low 21766 psia (1) 21712.757 prfri (1) 2.
CONTAINMENT' SPRAY (CSAS) l a.-
Manual:(Trip Buttens)
Not Applicable Not Applicable j
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b.
Containment Pressure -- High-High 5 22.3 psia' 5 23.490 psia l
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CONTAINMENT ISOLATION.(CIAS) a.
Manual (Trip Buttons)
Not' Applicable Not Applicable b.
Containment Pressure - High-5 18.3 psia 5 18.490 psia l
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ARKANSAS - UNIT 2 3/4 3-16 Amendment No. ZA
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TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE TRIP VALUE VALUES EUNCTIONAL UNIT 4.
MAIN STREAM AND FEEDWATER ISOLATION (MSIS)
Manual (Trip Buttons)
Not Applicable Not Applicable a.
I b.
Steam Generator Pressure - Low 2 751 psia (2) 2 729.613 psia (2) 5.
CONTAINMENT COOLING (CCAS) a.
Manual (Trip Buttons)
Not Applicable Not applicable b.
Co.2tainment Pressure - Higt 5 18.3 psia 5 18.490 psia Pressurizer Pressure - Low 2 1766 psia (1) 21712.757 psia (1) c.
6.
RECIRCULATION (RAS)
Manual (Trip Buttons)
Not Applicable Not Applicable a.
b.
Refueling Water Tank - Low 54,400 2,370 gallons between 51,050 and 56,600 (equivalent to 6.0 0.5%
gallons (cquivalent to indicated level)
'etween 5.111% and 6.889*
indiceted level) l 7.
LOSS OF POWER 4.16 kv Emergency Bus Undervoltage s.
3120 volts (4) 3120 volts (4)
(Loss of Voltage) b.
460 volt Emergency Bus Undervoltage 423 2 2.0 volts 423 4.0 volts with an 8.0 I 0.5 with an 8.0 0.8 (Degraded Voltage) second time delay second time delay 3/4 3-17 Amendment No. 24 ARKANSAS - UNIT 2
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