ML20085A968
| ML20085A968 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/31/1995 |
| From: | Polich T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20085A978 | List: |
| References | |
| NUDOCS 9506140311 | |
| Download: ML20085A968 (24) | |
Text
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4 UNITED STATES NUCLEAR REGULATORY COMMISSION j
WASHINGTON D.C. 20606-0001 s...../
TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445
. AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-87 1.
The Nuclear Regulatory Commission (the'Comission) has found that:
A.
The application for amendment by Texas Utilities Ele tric Company (TU Electric, the licensee) dated February 14,1994_TXX-94046),
complies with the standards and requirements of the Awmic 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; Theie is reasonable assurance:
(i) that the activities authorized C.
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will ba conducted in compliance with the Comission's regulations; D.
The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.
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. NPF-87 is hereby amended to read as follows:
9506140311 950531 DR ADOCK 05000445 PDR
2.
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environtpental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION TimothyJ.Pollich,ProjectManager
/c Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Atte.chment:
Changes to the Technical Specifications Date of Issuance: May 31, 1995-
4 f r tro a
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-, t UNITED STATES l
3' S-NUCLEAR REGULATORY COMMISSION
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wasniwarow, o.c. nosse-cooi s,...../
4; TEXAS UTILITIES ELECTRIC COMPANY j
COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446
]
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment'No.27 License No. NPF-89 l
1.
The Nuclear Regulatory Comission (the Commission).has found that:
i t
A.
The application for amendment by Texas Utilities Electric Company (TV Electric,.the licensee) dated February 14, 1994 (TXX-94046),
j complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and t
regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as l
amended, the provisions of the Act, and the rules and regulations of the Commission-i C.
There is reasonable assurance:
(1) 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 license 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.
1 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. NPF-89 is hereby amended to read as follows:
l e
- s.
e (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.27, and the Environmental Protection Plan t
contained in Appendix B, are hereby incorporated into this license.
TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Po ich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 31, 1995
-1
~
ATTACHMENT TO LICENSE AMENDMENT NOS. 41 AND 27 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 2-4 2-4 2-5 2-5 2-6 2-6 l
2-7 2-7 2-8 2-8 2-11 2-11 B 2-3 8 2-3 3/4 3-13 3/4 3-13 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29
'/4 3-30 3/4 3-30 8 3/4 3-1 B 3/4 3-1 B 3/4 3-2 8 3/4 3-2 I
(
670 i
660 N' ------~~ " '!
UNACCEPTABLE P =2385 PSIG I
OPERATION l
650 l --- -.
l l
640 P=2235 PSIG l
l j
630 4
P=1985 PSIG i
.C
~ 620
\\
p i
i 610 N
i P=1845 PSIG i
g O
i g
600 590
=
580 j
ACCEPTABLE i
i.
i i
OPERATION i
i i
570 l
560 i
i i.
550 0
20 40 60 80 100 120 PERCENT OF RATED THERMAL POWER FIGURE 2.1-lb UNIT 2 REACTOR CORE SAFETY LIMITS COMANCHE PEAK - UNITS 1 AND 2 2-3 Unit 1 - Amendment No. 14
i SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock 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 applicableACTIONstatementrequirementofSpecification3.3.1untill column of Table 2.2-1, declare the channel inoperable and apply the the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
CDMANCHE PEAK - UNITS 1 AND 2 2-4 Unit 1 - Amendment No. 41 l
Unit 2 - Amendment No. 27 i
l TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 1.
Manual Reactor Trip N.A.
N.A 2.
Power Range, Neutron Flux a.
High Setpoint
$109% of RTP*
$111.7% of RTP*
b.
Low Setpoint
$25% of RTP*
$27.7 of RTP*
3.
Power Range, Neutron Flux, s5% of RTP* with -
56.3% of RTP* with High Positive Rate a time constant a time constant 22 seconds 22 seconds 4.
Not Use6 5.
Intermediate Range,
$25% of RTP*
s31.5 of RTP*
Neutron Flux 5
5 6.
Sourca Range, Neutron Flux s10 cps
$1.4 x 10 cps 7.
Overtemperature N-16 See Note 1 See Note 2 RTP = RATED THERMAL POWER COMANCHE PEAK - UNIT 1 AND 2 2-5 Unit 1 - Amendment No. 4,l',21,39,41 Unit 2 - Amendment No. h 45,27
..,_..-_ _ ____. _ _ _ _._~. _ _
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS l
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALQE f
8.
Overpower N-16 sil2% of RTP*
$114.5% of RTP*
9.
Pressurizer Pressure-Low
- a. Unit 1 21880 psig 21863.6 psig
- b. Unit 2 21880 psig 21865.2 psig 10.
Pressurizer Pressure-High
- a. Unit 1
$2385 psig
$2400.8 psig
- b. Unit 2 s2385 psig s2401.4 psig 11.
Pressurizer Water Level-High s92% of instrument
$93.9% of instrument span span 12.
Reactor Coolant Flow-Low
- a. Unit 1 290% of loop 288.6% of loop design flow **
design flow **
- b. Unit 2 290% of loop 288.8% of loop minimum measured minimum measured fl ow***
flow ***
RTP - RATED THERMAL POWER Loop design flow - 99,050 gpm
- Loop minimum measured flow - 98,500 gpm i
COMANCHE PEAK - UNIT 1 AND 2 2-6 Unit 1 - Amendment No. MrM,41
. Unit 2 - Amendment No. 7,27
.m.
m m
m
.m
j TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE
- 13. Steam Generator Water Level - Low-Low a.
Unit 1 225.0% of narrow 223.1% of narrow range instrument range instrument span span b.
Unit 2 235.4% of narrow 233.4% of narrow range instrument range instrument span span
- 14. Undervoltage - Reactor Coolant Pumps 24830 volts-24753 volts-each bus each bus 15.
Underfrequency - Reactor Coolant Pumps 257.2 Hz 257.06 Hz
- 16. Turbine Trip a.
Low Trip System Pressure 259 psig 246.6 psig i
b.
Turbine Stop Valve 21% open 21% open Closure 17.
Safety Injection Input N.A.
N.A.
from ESF 1
i COMANCHE PEAK - UNIT 1 AND 2 2-7 Unit 1 - Amendment No. 2,11,22,41 Unit 2 - Amendment No. 8,27
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 18.
Reactor Trip System Interlocks 4
a.
Intermediate Range 1 x 10"' amps 26 x 10 ' amps Neutron Flux, P-6 b.
Low Power Reactor Trips Block, P-7
- 1) P-10 input 10% of RTP*
s12.7% of RTP*
- 2) P-13 input 10% RTP* Turbine s12.7% RTP* Turbine First Stage Pres-First Stage Pressure sure Equivalent Equivalent c.
Power Range Neutron 48% of RTP*
s50.7% of RTP*
Flux, P-8 d.
Power Range Neutron
$50% of RTP*
$52.7% of RTP*
Flux, P-9 e.
Power Range Neutron 10% of RTP* -
27.3% of RTP*
Flux, P-10
- 19. ' Reactor Trip Breakers N.A.
N.A.
- 20. Automatic Trip and Interlock N.A.
N.A.
Logic
- RTP = RATED THERMAL POWER COMANCHE PEAK - UNIT I AND 2 2-8 Unit 1 - Amendment No.41 Unit 2 - Amendment No.27 n,..
..,- - n
..-. _ v
. TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
M NOTE 1:
(Continued)
For Unit 2 (i) for q - q, between -52% and +5.5%, f (aq) = 0, where q RATED, THERMAL ~ POWER in the top and bo,ttom halves of the, and q, are percent core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (ii) for each percent that the magnitude of q - q, exceeds -525, the N-16 Trip Setpoint shall. be automatically reduced by 2.15% of its value at RATED-THERMAL POWER, and (iii) for each percent that the magnitude of q - q, exceeds +5.5%, the M-16 Trip Setpoint shall be automatically reduced by 2.17% of its value at RATED THERMAL POWER.
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.51%
of span for Unit 1 or 2.85% of span for Unit 2.
l i
COMANCHE PEAK - UNIT 1 AND 2 2-11 Unit 1 - Amendment No. 44r24,41 Unit 2 - Amendment No. 7,27
_.. _ _.,-. _ _ _ = ___
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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 beea selected to ensure that the core and Reactor Coolant System are prevented from exceeding their safety limits during normal operation and i
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 left" setpoint is l
within the band allowed for calibration accuracy and instrument drift.
To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which setpoints can be measured and calibrated, Allowable Values for the Reactor Trip Setpoints have been spacified 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.
l The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensors and other instrumentation utilized in these channels are expected to be capable of operating 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 more serious problems and should warrant further investigation.
i i
i COMANCHE PEAK - UNITS 1 AND 2 B 2-3 Unit 1 - Amendment No.41 Unit 2 - Amendment No.27
LIMITING SAFETY SYSTEM SETTINGS f
BASES
-REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS (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 Trip 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 i
safety analysis 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 insertion of positive reactivity that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
Manual Reactor Trio The Reactor Trip System includes manual Reactor trip capability.
Power Rance. 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 suberitical 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 power levels.
The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Rance. Neutron Flux. Hioh Rates 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.
COMANCHE PEAK - UNITS 1 AND 2 B 2-4 Unit 1 - Amendment No. 44,39 Unit 2 - Amendment No.25
~
INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-2 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-3.
APPLICABILITY: As shown in Table 3.3-2.
ACTION:
a.
With an ESFAS Instrumentation or Interlock Trip Setpoint trip less i
conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-3, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-3, declare the channel inoperable and apply the applicable l
ACTION statement requirements of Table 3.3-2 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
c.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-13 Unit 1 - Amendment No. 41 Unit 2 - Amendment No. 27
INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.*
n 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 are tested at least once per N times 18 months whe.? N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" column of Table 3.3-2.
i
- This surveillance test interval is extended to 24 months for Unit 2, to remain in effect until the completion of the second refueling outage for Unit 2, for the following functions and initiation signals:
Safety Injection (ECCS), Phase "A" Isolation, Auxiliary Feedwater and Emergency Diesel Generator Operation on Containment Pressure--High--1, Pressurizer Pressure--Low, and Steam Line Pressure--Low; Containment Spray Pump on Containment Pressure High--1; and Those functions with response times which are initiated by Loss of Power (6.9kV and 480V Safeguards System Undervoltage).
CDMANCHE PEAK - UNITS 1 AND 2 3/4 3-14 Unit 1 - Amendment No. 31 Unit 2 - Amendment No.17
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 1.
Safety Injection-(ECCS, Reactor Trip, Feedwater Isolation, Control Room Emergency Recirculation, Emergency Diesel Generator Operation, Contain-ment Vent Isolation, Station Service Water, Phase A Isolation, Auxiliary Feedwater-Notor Driven Pump, Turbine Trip, Component Cooling Water, Essential Ventilation Systems, and Containment Spray Pump).
I a.
Manual Initiation N.A.
N.A.
b.
Automatic Actuation Logic N.A.
N.A and Actuation Relays c.
Containment Pressure--High 1
$3.2 psig s3.8 psig d.
Pressurizer Pressure--Low 21820 psig 21803.6 psig e.
Steam Line Pressure--Low i
- 1) Unit 1 2605 psig*
2593.5 psig*
- 2) Unit 2 2605 psig*
2578.4 psig*
+
2.
Manual Initiation N.A.
N.A b.
Automatic Actuation Logic N.A.
N.A and Actuation Relays c.
Containment Pressure--High-3 s18.2 psig s18.8 psig l
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-25 Unit I - Amendment No. 44,41 Unit 2 - Amendment No.27
. m....
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m.
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TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VAlbE 3.
Containment Isolation a.
Phase "A" Isolation j
l
- 1) Manual Initiation N.A.
N.A
- 2) Automatic Actuation Logic N.A.
N.A and Actuation Relays
- 3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
b.
Phase "B" Isolation
- 1) Manual Initiation See Item 2.a above. Phase "B" isolation is manu' ally initiated when containment spray function is manually initiated.
- 2) Automatic Actuation Logic N.A.
N.A and Actuation Relays
- 3) Containment Pressure--
s18.2 psig s18.8 psig High-3 c.
Containment Vent Isolation
- 1) Manual Initiation See Items 3.a.1 and 2.a above. Containment Vent Isolation is manually initiated when Phase "A" isolation function or containment spray function is manually initiated.
- 2) Automatic Actuation Logic N.A.
N.A and Actuation Relays
- 3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-26 Unit 1 - Amendment No.41 Unit 2 - Amendment No.27
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 4.
Steam Line Isolation a.
Manual Initiation N.A.
N.A b.
Automatic Actuation Logic N.A.
N.A and Actuation Relays c.
Containment Pressure--High-2 s6.2 psig s6.8 psig d.
Steam Line Pressure--Low
- 1) Unit 1 2605 psig*
2593.5 psig*
- 2) Unit 2 2605 psig*
2578.4 psig*
e.
Steam Line Pressure -
Negative Rate--High
$100 psi **
sl78.7 psi **
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-27 Unit 1 - Amendment No.14,41 Unit 2 - Amendment No. 27
\\
4 TABLE 3 3-3 (Cortinued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 5.
Turbine Trip and Feedwater Isolation a.
Automatic Actuation Logic N.A.
N.A and Actuation Relays b.
Steam Generator Water Level--High-High
- 1) Unit 1
$82.4% of
$84.3% of narrow narrow range range instrument instrument span span.
- 2) Unit 2 581.5% of s83.5% of narrow narrow range range instrument instrument span
- span, c.
Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
i 1
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-28 Unit I - Amendment No. h14,41 Unit 2 - Amendment No.27
~ - -
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 6.
Automatic Actuation Logic N.A.
N.A and Actuation Relays b.
Steam Generator Water Level--Low-Low
- 1) Unit 1 225.0% of 223.1% of narrow narrow range range instrument instrument span.
span.
- 2) Unit 2 135.4% of 233.4% of narrow narrow range range instrument instrument span.
span.
c.
Safety Injection - Start See Item 1. above for all Safety Injection Trip Setpoints and Motor Driven Pumps Allowable Values.
d.
Loss-of-Offsite Power N.A.
N.A e.
Trip of All Main Feedwater N.A.
N.A Pumps 7.
Automatic Initiation of ECCS Switchover to Containment Sump a.
Automatic Actuation Logic N.A.
N.A and Actuation Relays I
b.
RWST Level--Low-Low
- 1) Unit 1 240.0% of 238.9% of span span
- 2) Unit 2 240.0% of 239.1% of span span Coincident With See Item 1. above for all Safety Injection Trip Setpoints and Safety Injection Allowable Values.
COMANCHE PEAK - UNITS 1 AND 2 3/4 3-29 Unit 1 - Amendment No. 2rl4,41 Unit 2 - Amendment No.27
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS-FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 8.
Loss of Power (6.9 kV & 480 V Safeguards System Undervoltage) a.
6.9 kV Preferred Offsite 25004 V 55900 V Source Undervoltage 24900 V b.
6.9 kV Alternate Offsite 25004 V
$5900 V Source Undervoltage 24900 V c.
6.9 kV Bus Undervoltage 22037 V 21935 V
$3450 V d.
6.9 kV Degraded Voltage 26054 V 25933 V e.
480 V Degraded Voltage 2439 V 2435 V f.
480 V Low Grid 2447 V 2443 Y Undervoltage 9.
Control Room Emergency Recirculation a.
Manual Initiation M.A.
N.A b.
Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and i
Allowable Values.
10.
Engineered Safety Features Actuation System Interlocks a.
Pressurizer Pressure, P-11
- 1) Unit I s1960 psig
$1975.2 psig
- 2) Unit 2 s1960 psig 51976.4 psig-b.
Reactor Trip, P-4 N.A.
N.A
~
11.
Solid State Safeguards Sequencer N.A.
N.A (SSSS)
COMANCHE PEAK - UN!TS 1 AND 2 3/4 3-30 Unit 1 - Amendment No.14,41 Unit 2 ~- Amendment No. 27
- ,--.-m m
--.. ~
7 3/4.3 INSTRUMENTATION r
i BASES j
3/4.3.1 and 3/4.3.2 REACTOR TRIP' SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION I
SYSTEM INSTRUMENTATION l
The OPERABILITY of the Reactor Trip System and the Engineered Safety
)
Features Actuation System instrumentation and interlocks ensures that: (1) the j
associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance consistent with main-taining an appropriate level of reliability of the reactor protection and engi-i neered safety features instrumentation, and (3) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reli-ability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The inte-grated operation of each of these systems is consistent with the assumptions.used in the safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System", WCAP-10271 Supplement 2, " Evaluation of Surveillance Frequencies and Out of Service 4
Times for the Engineered Safety Features Actuation System" and supplements to these reports as approved by the NRC and documented in the SER (letters to Westinghouse Owners Group (WOG) dated February 21, 1985, February 22, 1989, and April 30, 1990).
The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-3 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as left" Setpoint is within the band l
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-1 able Values for the Setpoints have been specified in Table 3.3-3.
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 accom-modate this error.
COMANCHE PEAK - UNITS 1 AND 2 B 3/4 3-1 Unit 1 - Amendment No. M,41 Unit 2 - Amendment No. 27
INSTRUMENTATION BASES REACTOR TRIP SYSTEM and' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) l I
The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.
Inherent to the determination of the j
Trip Setpoints are the magnitudes of these channel uncertainties.
Sensor and rack instrumentation utilized in these channels are expected to be capable of l
operating 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 more i
serious problems and should warrant further investigation.
The measurement of response time specified in the Technical Requirements Manual at the specified frequencies provides assurance that the Reactor trip i
and the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response _ times indicated as not i
applicable.
Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either:
(1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response time.
i The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being i
exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents events, and transients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident:
(1) ECCS-pumps start and automatic valves position, (2) Reactor trip, (3) feedwater isolation, (4) startup of the emergency diesel generators, (5) containment spray L
pumps start and automatic valves position (6) containment isolation, (7) steam line isolation, (8) turbine trip, (9) auxiliary feedwater pumps start and automatic valves position, (10) station service water pumps start and automatic valves position, (11) Control Room Emergency Recirculation starts, and (12) i essential ventilation systems (safety chilled water, electrical area fans, i
. primary plant ventilation ESF exhaust fans, battery room exhaust fans, and UPS e
ventilation) start.
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f COMANCHE PEAK - UNITS 1 AND 2 B 3/4 3-2 Unit 1 - Amendment No. H,41 Unit 2 - Amendment No.27 i
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