ML20065J609
| ML20065J609 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  (NPF-87-A-002, NPF-87-A-2) |
| Issue date: | 11/06/1990 |
| From: | Linville J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065J614 | List: |
| References | |
| NUDOCS 9011140066 | |
| Download: ML20065J609 (9) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
,5 W ASHildG ton, D. C. 20665 j
TEXAS UTILITIES ELECTRIC COMPANY. ET Al,.*
i COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 l
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 2 License No. NPF-87 l
c q
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Texas utilities Electric Company i
(TU Electric) acting for itself and as agent for Texas Municipal Power Agency (licensees) dated May 18, 1990, as supplemented by letter dated July 9,1990, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act). and j
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; 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 Comission's regulations and all applicable. requirements have
{
been satisfied.
I l
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- The current owners of the Comanche' Peak Steam Electric Station are:
Texas Utilities Electric Company and Texas Municipal Power Agency.- Transfer of I
ownership from Texas Municipal Power Agency to Texas Utilities Electric Company was previously authorized by Amendment No. 9 to' Construction Permit CPPR-126 on August 25, 1988 to take place in 10 installments as. set forth~in'
.the Agreement attached to the application for Amendment dated March 4, 1988.
At the completion thereof, Texas Municipal Power Agency will no longer retain i
r any ownership interest.
1 9011140066 901106 PDR ADOCK 05000445 Fs PDC
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2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amenuJd to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 2, 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 Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGulf. TORY COMMISSION ames C. Linville, Acting Director I
Project-Directorate IV-2 Division of. Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation-
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Attachment:
l Changes to the Technical l
Specifications l
i Date of Issuance:
November 6, 1990 t
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1
ATTACHMENT TO LICENSE AMENDMENT NO. 2 1
FACILITY OPERATING LICENSE NO. WPF DOCKET NO. 50-445 i
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
i The corresponding overleaf pages are also provided to maintain document completeness.
l REMOVE INSERT 2-4 2-4 2-5 2-5 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 4
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SAFETY LIMITS AND LIMITING SAFETY SY'. TEM SETTINGS t
L2 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 2.2-1.4 APPLICABILITY:
As shown for each channel in Table 3.3-1.
l 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 5 TA Where:
Z = The valve from Column Z of Table 2.2-1 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, j
S = Either the "as measured" value (in percent span) of the sensor l
error, or the value from Column S (Sensor Error) of Table 2.2-1 l
for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 2.2-1 for-the affected channel.
i i
COMANCHE PEAK - UNIT 1 2 t
TABLE 2.2-1 no-J REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS M
E TOTAL SENSOR ALLOWANCE ERROR g
FUNCTIONAL UNIT (TA)
Z (5)
TRIP SETPOINT ALLOWABLE VALUE 1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
M.A.
C g
2.
Power Range, Neutron Flux
'a.
High Setpoint
- 7. 5 4.56 1.25 5109% of RTP*
$111.7% of RTP*
l b.
Low Setpoint 8.3 4.56 1.25 125% of RTP*
$27.7% of RTP*
3.
Power Range, Neutron Flux,
- 1. 6 0.5 0
$5% of RTP* with
<6.3% of RTP* with High'Poritive Rate a time constant a time constant 12 seconds 12 seconds N
4.
Power Range, Neutron Flux,
- 1. 6 0.5 0
$5% of RTP* with 16.3% of RTP* with High Ne. native Rate a time constant a time constant 22 seconds 32 seconds 5.
Intermediate Range, 17.0 8.41 0
$25% of RTP*
131.5% of RTP*
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0
$105 cps
$1.4 x 10s cp3 II) 7.
Overtemperature N-16 5.8 3.65 1.2+0.8 See Note 1 See Note _2 112% of RTP*
1115.1% of RTP*
1 8.
Overpower N 4.0 1.93 0
9.
Pressurizer Pressure-Low 4.4 0.71 2.0 11880 psig 21863.6 psig 10.
Pressurizer Pressure-High 7.5 5.01
- 1. 0
'$2385 psig
$2400.8 psig 5
'i
- RTP = RATED THERMAL POWER
~
(1).1.2% span.for delta-T (RTDs) and 0.8% for pressurizer pressure.
z m'
~
e
o TABLE 2.2-1 (Continued) c,
.o J
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
2i TOTAL-SENSOR ALLOWANCE.
ERROR
.g FUNCTIONAL UNIT-(TA)
Z_
(S)
TRIP SETPOINT ALLOWABLE VALUE 11.
.L.essurizer Water Leve: *irigh 8.0 2.18 2.0
$92% of instr <4ent
$93.9% of instrument span span c_
I i5
~12.
Reactor Coolant Flow-Low 2.5-1.18 0.6
>90% of loop
>88.6% of loop a
design flow **
3esign flow **
I-13.
Steam Generator Water 25.0 22.08 "2. 0
>25.0% of narrow
>23.1% of narrow level - Low-Low range instrument range instrument:-
span span t
. 14.
Undervoltage - Reactor-7.7 0
0
>4830 volts-
>4753 volts-Coolant Pumps each bus each bus 7
.4.'4 0
0
>57.2 Hz-
>57.1 Hz m
15.
Underfrequency - Reactor Coolant ~ Pumps 16.
Turbine Trip a.
Low Trip-System Pressure N.A.
N.A.
N.A.
>59 psig
->46.6 psig:
b.
Turbine Stop Valve N.A.
N.A.
N.A.
>1% open.
>1% open Closure 17.
Safety Injection' Input
.N.A.
N.A.
N.A.
N.A.
N.A.
'from ESF-E E
- Loop des'ign flow =~95,700 gpm.
E-
'i.
5
'N:
(
. =. -.
-=
TABLE 2.2-1 (Continued) no.$
REACTOR TRIP SYSTEM JNSTRUMENTATION TRIP.SETPOINTS M
5 TOTAL SENSOR
- {
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)-
TRIP SETPOINT ALLOWABLE VALUE 18.
Reactor Trip System Interlocks c--
5 a.
Intermediate' Range N.A.
N.A.
N.A.
I x 10 10 amps
>6 x 10 11 amps Neutron Flux, P-6 b.
. Low Power Reactor Trips Block, P _.
1): P-10 input f.*. A.
N.A.
N.A.
10% of RTP*
<12.7% of RTP*
2)- P-13 input N.A.
N.A.
N.A.
10% RTP* Turbi:ae
<12.7% RTP* Turbine rp First-Stage Pres-First Stage Pressure cn
.:sure Equivalent Equivalent:
c.
Power Range' Neutron.
N. A.
N.A.
N.A.
. 48% of RTP.*
-<50.7% of RTP*
-Flux, P-8
~
~
-d.
Power Range Neutron N.A.
N.A.
N.A.
<50% of RTP*
<52.7% of RTP*
Flux, P-9 e.
Power Range Neutron N.A.
N.A.
N.A.
10% of RTP*
>7.3% of RTP*-
- Flux, ' P -
~ f
.19.
Reactor Trip-Breakers;
'N.A.
N.A.
N.A.
N. A. -
.N.A.
-20.
Automatic-Trip and: Interlock - N. A.-
N. A..
N.A.
N. A.'
N.A.
- Logic-
-- *RTP =' RATED THERNAL: POWER-
..q
~ - -. - -
.m-.
-4
..m
.i..
s1
c, -
TABLE 3.3-3 (Continued)
.S.
~
3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 2m SENSOR A
. FUNCTIONAL UNIT.
ALLOWANCE (TA)
Z_
(S)
TRIP SETPOINT ALLOWABLE VALUE TOTAL ERROR R
[ -.
4.
' Steam Line Isolation i'i
- -4 a.
Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
s b.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N. A.
and Actuation Relays-c.
Containment Pressure--High-2 2.7 0.71-
- 1. 7 -
'16.2 psig 16.8 psig.
d.
Steam Line Pressure--Low 17.3 15.01 2.0
. m
. >605 psig*
>593.5 psig*
1 e.
Steam'Line Pressure -
8.0
- 0. 5 0
$100 psi **
$ 178.7 psi **
4
. Negative Rate--High-w
- 5. -
Turbine, Trip and-Feedwater Isolation F
a.
. Automatic-Actuation.l.ogic N.A.
.N.A.
.N.A.
N. A.~
N.A.
and' Actuation Relays-b.
Steam Generator. Water
- 7. 6 4.78:
2.0
<82.4% of
<84.3% of narrow Level--High-High iiarrow range range instrument instrument
. span.
span.
. y M.
c.
Safety Injection.
See Item'1.'above for all Safety Injection Trip Setpoints and g-TAllowable Values.
M
'i 5
.~
_ _ -.... - ~ _, - - -....
TABLE 3.3-3 (Continued) ng ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E
m-SENSOR
..,g TOTAL ERROR R
FUNCTIONAL UNIT ALLOWANCE (TA) Z (S)
TRIP SETPOINT ALLOWABLE VALUE h
6.
Auxiliary Feedwater s'i a.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
H and Actuation-' Relays b.
Steam Generator Water 25.0 22.08
- 2. 0
> 25.0% of
> 23.1% of narrow Level--Low-Low iiarrow range -
range instrument-instrument span.
span.
w
~
l}-
c.
- Safety Injection - Start See Item 1. above for all Safety Injection Trip Setpoints and Motor. Driven: Pumps E
. Allowable Values.
m e
d.
-Loss-of-Offsite Power N.A.
N.A.
N.A.
N.A.
N.A.
e.
Trip of All' Main Feedwater N.A.
N.A.
N.A.
N.A.
N.A.
Pumps
~7.
Automatic Initiation of.ECCS Switchover to Containment: Sump a.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
- and Actuation Relays-b.
RWST Level--Low-Low 2.5 0.71
-1.25
> 40.0% of
> 38.9% of span..
span
- Coincident With-See' Item:1..above for all Safety Injection Trip Setpoints and jg Safety Injection-AllowableiValues.
5 2
8.
Loss of Power (6.9 kV-& 480 V E
y Safeguards System Undervoltagey 5-6'.9'kV Preferred Offsite~
N.A.
N.A.
N.A.
> 5004 V'
< 5900.V a.
Source.Undervoltage~
> 4900 V
.m e
4
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.y
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