ML20079P044
| ML20079P044 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 10/18/1991 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P047 | List: |
| References | |
| NUDOCS 9111120170 | |
| Download: ML20079P044 (7) | |
Text
.
I e
b3 RIGO o
UNITED STATES l'h m ' h NUCLEAR REGULATORY COMMISSION g.V
- g wAssinoton, p. c. rossa 4
- % *.... /
TEXAS UTILITIES ELECTRIC COMPANY, ET AL.*
COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY SPERATING LICENSE Amendment No. 4 License Nc. NPF-87 1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TU Electric) acting for itself and as agent for Texas Municipal Power Agency (licensees) dated June 28, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 regulatiens of the Commission; C.
There is reasonable assurance:
(i) 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.
- The current owners of the Comanche Peak Steam Electric Station are:
Texas Utilities Electric Company and Texas Municipal Power Agency.
Transfer of ownership from Texas Hunicipal 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 Agrecment attached to the application for Amendment dated March 4, 1988.
At the completion tt ereof, Texas Municipal Power Agency will no longer retain any owaership intert;st.
9111120170 911018 i
PDR ADOCK 05000445 I
p PDR
9 Y.
].
p'. -
2.
Arcordingly, the license is amended by changes to the Technical Specifi-citi 1s as indicated in the attechment to this license emendment and Parsgrcph 2.C.(2) of Facility Operating License No. NPF-87 is hereby s g.
- f.
amended to read as follows:
~~
- r '
{ '
t Technical Specifications MN The Technical Specifications contained in Appendix A, as revised y
i
.8 through Amendment No.
4, and the Environmental Protection Plan f. O,
~I,rd
~,
C ';/
contained in Appendir, S. both of which are attached hereto, are l
.Y hereby incorporated % ine license.
The licensee shall operate t9 facility in accordance with the Technical Specifications and the 1
Ens lironmental Protection Plan.
t 3.
The license amendment is effective as of its date of istuance to be implemented within 60 aays of date of issuance.
y q'[
FOR THE NUCLEAR REGULATORY COMM1SSION GCI M
Suzanne C. Black, Director Project Directorate IV-2 co Division of Reactor Projects - IIT'IV/V Office of Nuclear Reactor Regulat' ion
Attachment:
Changes to the Technical Spectfications Date of Is:-uance:
October 18, 1991 o
s W
' n.
- t t. _
- - - - - - - - - - - - ~ - - - - - - ~ - - - - - ~ - - - ~ ~ ~ ~ - -
,1 i
ATTACHMENT TO LICENSE AMENOMENT NO. 4 FACILITY OPERATING LICENSL NO. NPF-87 DOCKET,NO. 50-545 Revi$e 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.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 4-30 3/4 4-30 3/4 5-4 3/4 5-4 l-L l
l l
I
600
~
750 760 740 N
~~~'
720 700
~C 9
l E
650 b60 i
0 l
h 640 e
620 -
g O
600 Sto 560 l
I 540
$20 500 6
60 100 140 180 220 260 300 340 RCS TEMPER ATURE, DEG F FIGURE 1.4-4.
PORV SETPOINTS FOR OVERPRESSURE MITIGATION APPLICABLE UP TO 16 EFPY COMANCHE pears - UNIT 1 1/4 4-29
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION S'/ STEM SURVEILLANCE REQUIREMENTS I:
4.4.8.3.1 Each PORV shall be demonstrated OPERABLE by:
a.
Performance of an ANALOG CHANNEL OPERATIONAL lEST on the PORV actuation channel, but exclading valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereaf tei when the PORV is required OPERABLE; b.
Performance of a CHANNEL CALIBRATION on the PORV actuation channel S
at least once per 18 months; and Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> c.
when the PORV is being used for overpressure protection.
4.4.8.3.2 Ea;h RHR suction relief valve shall be demonstrated OPERABLE whon
(
the RHR suction relief valves are being used for cold overpressure protection as follows:
a.
For RHR suction rellet valve 87088 by verif int,.. least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that RHR Suction Isolation Valve (RRSIV) 8702B and 87018 f_
are open.
b.
For RHR suction relief valve 8708A by verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that RRSIV 8701A und 8702A are open.
c.
Testing pursuant to Specificatico 4.0.5.
4.4.8.3.3 The RCS vent (s) shall be verified to be open at least once per 12 houtu* when the vent (s) is being used for overpressure protection.
- Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least one per 31 days.
COMANCHE PEAK - UNIT 1 3/4 4-30 Amendment No.
4
~----- - - - - - - -
~ ~ ~
-~
~.
. - ~. - -
.O
~ EMERGENCY CORE COOLING SYSTEMS
-3/4.5.2 ECCS SUBSYSTEMS - T,yg > 350*F LIMITING CONDITION FOR OPERATION F
3.5.2 Two independent Emergency Core Cooling System (ECCS) subs.ystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging pump, b.
One OPERABLE safety injection pump,
- c. -
One OPERABLE RHR haat exchanger, d.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and automatically opening the containment sump suction 7alves during the recirculation
-phase of operation.
~APPIICABILITY:
MODES 1, 2, and 3*.
ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
In the event.the ECCS is actuated and injects water into the Reactor
-Coolant System,:a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances-o' the actuation and the total accumulated actuation cycles to date.
The current value of.the usage factor for each-affected Safety Injection nozzle shall be provided in this Special Report wher.ever its value exceeds 0.70.
- The provisions of Spe:ifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the centrifugal charging pumps-and the safety injection pumps declared inoperable pursuant to Specification 3.5.3 provided the centrifugal
-charging pumps and the safety injection pumps are restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs
- exceeding 375*F, whichever comes first.
COMANCHE PEAK - UNIT 1 3/4 5-3
1 g
EMERGENCY CORE COOLING SYSTEMS 1
SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with oower to the valve operators removed:
Valve Number Valve Function Valve Position 8802 A & B SI Pump to Hot Legs Closed 8808 A, L. C, D Accum. Discharge Open*
8809 A & B RHR to Cold legs Open 8835 SI Pump to Cold Legs Open 8840 RHR To Hot Legs Closed B806 SI Pump Suction from RWST Open 8813
$1 Pump Mini-Flow Valve Open b.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured ta position, is in its correct position.
c.
By a visual inspection which veri.*ies thet no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual.nspection-shall be performed; 1)-
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY,-and 2).
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1 1)
Verifying interlock action of the RHR system frcn the Reactor Coolant System to ensure that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 442 psig the interlocks prevent the valves from being opened.
COMANCHE PEAK - UNIT 1 3/4 5-4 Amendment No. 4