ML20149J142
| ML20149J142 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/11/1988 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20149J077 | List: |
| References | |
| NUDOCS 8802220281 | |
| Download: ML20149J142 (6) | |
Text
7 ATTACHMENT A
Revise the Technical Specifications as follows:
Remove Page Insert Page 2-5 2-5 3/4 3-27 3/4 3-27 8802220201 080211 PDR ADOCK 05000412 P
7 TABLE 2.2-1 (Continued) m REACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT ALLOWANCE (TA)
Z S
TRIP SETPOINT ALLOWABLE VALUE 13.
Steam Generator Water
/ n-&
44 -te 1.67 f narrow of narrow k il5 10.17 range instrument range instrument Level-tow-Low c$
span-each steam span-each steam generator generator
=
14.
4 Steam /Feedwater Flow 20.0 2.66 See Note 6 < 40% of full
< 43.1% of full Mismatch steam flow at RTP* steam flow at RTP*
g,
{
b.
Coincident with Steam 25.0 2.18 1.67
> 25% of narrow
> 23.2% of narrow C
Generator Water Level range instrument iange instrument
~
{
Low span span
- 15. Undervoltage - Reactor 27.7 1.39 0
>75% of BUS
>73% of BUS Voltage h,7 Coolant Pumps Voltage cach bus 2 cach bus
]k 16.
Underfrequency-Reactor 10.0 0.20 0
>57.5 Hz-each bus
>57.4 Hz-each bus Coolant Pumps 17.
Turbine Trip a.
Emergency Trip Header N.A.
N.A.
N.A.
>1000 psig
>958 psig Low Fressure b.
Turbine Stop Valve N.A.
M.A.
N.A.
->1% open
>1% open Closure 18.
Safety Injection Input N.A.
N.A.
N.A.
M.A N.A.
from ESF 19.
Reactor Coolant Pump N.A.
N.A.
N.A.
M.A.
N.A.
Breaker Position Trip 20.
Reactor Trip Breakers M.A.
M.A.
N.A.
M.A.
N.A.
9
~,.
TABLE 3.3-4 (Continued)
E ENCINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR TRIP f FUNCTIONAL UNIT ALLOWANCE (TA)
Z DRIFT (5)
SETPOINT ALLOWABLE VALUE 7.
AUkILIARY FEEDWATER (Continued)
E b.
Steam Generator Water Z
Level -Low-Low 11.57e}
" 10.7 %
' II.S 10 12
~
1.
Start Turbine 45-5 14-16 1.67
> M-5%)of
> 14-M f Driven Pump rrow range harrow range instrument instrument span span
- 11. 5 10 It II. S~ s to.7 7, h M-5%
m f
14-M f y
2.
Start Motor M-5 14-18 1.67 range narrow range Driven Pumps u
1.
instrument instrument
{wa span span e
w
_ 4, c.
Undervoltage - RCP (Start 27.7 1.39 0.0
> 75% of nominal > 73% or nominal Turbine Driven Pump) 6us voltage bus voltage n
Q-.
d.
Safety Injection See Item 1. above for all Safety Injection Trip Setpoints
~
g (Start Motor-Driven Pumps) and Allowable Values.
e.
Turbine Driven Pump 5.0 2.0 0
Discharge Discharge Discharge Pressure Low pressure pressure with Steam Valve Open
> 150 psig with > 145 psig with (Start Motor-Driven Pumps) steam inlet steam inlet valves open valves open f.
Trip of Main Feedwater M.A.
N.A.
N.A.
N.A N.A.
Pumps (Start Motor-Driven Pumps)
ATTACHMENT B
Proposed Unit 2 Te'chnical Specification Change No. 2A-9 Safety Analysis Description of amendment request:
The proposed amendment would revise the steam generator water level low-low reactor trip setpoint in Table 2.2-1 "Reactor Trip System Instrumentation Trip Setpoints" and the steam generator water level low-low auxiliary feedwater actuation setpoint in Table 3.3-4 "Engineered Safety Features Actuation System Instrumentation Trip Setpoints" of the Unit 2
Technical. Specifications from 1 15.5% narrow range level span to 1 11.5%
narrow range level span.
This change. removes a
4%
environmental allowance that was added in to the steam generator low-low level sa.tpoint calculation to account for radiation effects on the steam ;e.erator level transmitters.
The values for "Allowable Value",
"Tot,1 Allowance",
and "Z"
for these setpoints in Tables 2.2-1 and 3.3-4 were also revised accordingly.
The steam generator low-low level reactor trip and auxiliary feedwater actuation protection is assumed in the following accidents as discussed in section 15.2 of the Unit 2 FSAR.
Loss of External Electrical Load / Turbine Trip Loss of Non-emergency AC Power to the Station Auxiliaries Loss of Normal Feedwater Flow Feedwater System Pipe Breaks None of these events result in fuel failures that would produce accident radiation levels comparable to a LOCA.
Therefore the 4% of uncertainty added in for transmitter radiation effects should not be included into the environmental error assumed for this instrument channel.
This allows the steam generator low-low level setpoint to be reduced as described below.
The Unit 2 Reactor Trip and Engineered Safety Features setpoints were calculated using the standard Westinghouse methodology as presented in Westinghouse WCAP-ll366.
The required setpoints are obtained by adding the specific Channel Statistical Allowance (for channel inaccuracies) to the safety analysis limit.
The safety analysis limit for steam generator low-low water level is 0% of narrow range level span as provided in Table 15.0-4 of the Unit 2 FSAR.
The Channel Statistical Allowance for the steam generator low-low level protection channel included a
12%
environmental allowance of which 4%
accounted for transmitter radiation effects.
Removing the 4% uncertainty for radiation effects revises the overall Channel Statistical Allowance for this protection channel from 15.3%
to 11.3%.
The revised setpoint of 1 11.5% therefore meets the safety analysis limit with the required channel accuracies included and a 0.2 % additional margin.
The steam generator water level low coincident with steam flow /feedwater flow mismatch and the steam generator water level high-high protection setpoints do not include a 4% allowance for transmitter radiation effects in their setpoint calculation and therefore require no change.
F
. ~ ATTACHMENT B Pago 2 The revised setpoints for steam generator level low-low reactor trip and auxiliary feedwater actuation are consistent with the values assumed in the Unit 2
FSAR -safety analysis and approved setpoint methodology, as revised by this evaluation, for Unit 2
and is therefore considered safe.
References BV-2 FSAR Tables 15.0-4 and 15.0-6 and Section 15.2 Letter 2NRC-7-013, "Setpoint Methodology for Protection Systems",
dated January 26, 1987 WCAP-11419 Westinghouse Methodology for Protection System - Beaver Valley Unit 1 WCAP-11366 Westinghouse Methodology for Protection System - Beaver Valley Unit 2 Engineering Memorandum No. EM-62925 "Steam Generator Level Channel Shifting" Letter DMW-D-6165, "4% Uncertainty For Transmitter Radiation Effects" dated December 23, 1987 Engineering Memorandum No. EM-79068 "Steam Generator Level Channel Shifts - EM 62925 Follow-up" f
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ATTACHMENT C
No Significant Eazard Evaluation Proposed Technical Specification Change Unit No. 2 - Change No. 2A-9 Basis for Proposed No Significant Hazards Consideration Determination:
The Commission has provided standards for determining whether a
significant hazards consideration exists (10 CFR 50.92(c)).
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a
significant reduction in a margin of safety.
The proposed change does not involve a
significant hazards consideration because:
1.
This change does not effect the capability of the Reactor Trip System to ensure that the reactor core and Reactor Coolant System are prevented from exceeding their safety limit ar.d the car oility of the Engineered Safety Features Actuation System to mitigate the consequences of any postulated accidents.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed change does not reflect any equipment or plant design change.
Thus no adverse safety considerations are introduced by the change.
Therefore, the probability of an accident or a malfunction of a different type than previously evaluated would not be created.
3.
This change will not affect the assumptions or consequences of any safety analysis presented in the FSAR.
The revised steam generator low-low level setpoint will continue to ensure that this protection channel setpoint meets the values assumed in the safety analysis when all channel inaccuracies have been t
considered.
Based on the above considerations, it is proposed to characterize the change as involving no significant hazards consideration.
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