ML20078E443
| ML20078E443 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/02/1994 |
| From: | Polich T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078E446 | List: |
| References | |
| NUDOCS 9411140053 | |
| Download: ML20078E443 (15) | |
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iE Uf:^ rD STATES H,J NUCLEAR REC _ ATORY COh*: lSSION g ss /
WASHH.G TON, D.C. 205 % -0001 TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated September 19, 1994, 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 regulations 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 i
been satisfied.
j 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 an. ended to read as follows:
9411140053 941102 i
PDR ADOCK 05000445 i
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. 2.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, 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, to be implemented within 30 days of its date of issuance.
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: November 2, 1994
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E UNITED STATES UCLEAR REGULATORY COMMISSION yk
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W ASHINGTON, D.C. 2055W1 TEXAS UTILITIES ELECTRIC COMPANY
{_0MANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No. NPF-89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilitics Electric Company (TV Electric, the licensee) dated September 19, 1994, 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 regulations 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.
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:
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. f (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.18, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
TV 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 of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION mff '
Timothy J. Pol ch, 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:
November 2, 1994 l
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i ATTACHMENT TO LICENSE AMENDMENT NOS. 32 AND 18 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 1
DOCKET NOS. 50-445 AND 50-446
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' Replace the following pages of the Appendix A Technical Specifications with j
the-attached pages. The revised pages are identified by-Amendment numbe. and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided. to maintain document completeness.
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REMOVE INSERT 3/4 5-5 3/4 5-5 3/4 6-11 3/4 6-11 l
3/4 6-12 3/4 6-12 3/4 6-14 3/4 6-14 3/4 7-4 3/4 7-4 3/4 7-13 3/4 7-13 I
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4 3
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 2)
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
e.
At least once per 18 months *, by:
l 1)
Verifying that each automatic valve in the flow path actuates to its correct position on Safety Injection actuation test signals, and 2)
Verifying that each of the following pumps start automatically upon receipt of a Safety injection actuation test signal:
a)
Centrifugal charging pumps, b)
Safety injection pumps, and c)
RHR pumps.
f.
By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 2 2370 psid, 2)
Safety injection pump 2 1440 psid, and 3)
RHR pump
> 170 psid.
g.
By verifying the correct position of each mechanical position stop for the following ECCS throttle valves:
1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)
At least once per 18 months:
CCP/S1 System Valve Number SI System Valve Number SI-8810A SI-8822A SI-8816A SI-8810B SI-8822B SI-8816B SI-8810C SI-8822C SI-8816C SI-88100 SI-88220 SI-88160
- The surveillance test interval is extended to 24 months for Train A, Unit 2, to remain in effect until the completion of the second refueling outage for Unit 2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 5-5 Unit 1 - Amendment No. H, 32 Unit 2 - Amendment No. U,18 t
T EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) h.
By performing a flow balance test, during shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
1)
For centrifugal charg1ng pump lines, with a single pump i
running:
a)
The. sum of the injection line f?ow rates, excluding the highest flow rate, is greater than or equal to 245 gpm, l
and b)
The total pump flow rate is less than or equal' to 560 gpm.
2)
For safety injection pump lines, with a single pump running:
~
a)
The sum of the cold leg injection line flow rates, excluding the highest flow rate, is greater than or equal l
to 400 gpm, and b)
The total pump flow rate is less than or equal to 675 gpm.
3)
For RHR pump lines, with a single pump running, the sum of the cold leg injection line flow rates is greater than or equal to 4652 gpm.
1.
Prior to entering MODE 3 and following any maintenance or operations activity which drains portions of the system by venting the ECCS pump casing and accessible discharge piping high points.
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t COMANCHE PEAK - UNITS 1 AND 2 3/4 5-6 Unit 1 - Amendment No. 7
+
[pNTAINMENT SYSTEMS 1
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the RWST and manually transferring suction to the containment sump.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one Containment Spray System inoperable, restore the inoperable Containment Spray System 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 />; restore the inoperable Containment Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.
By verifying that in the test mode each train provides a total dis-charge flow through the test header of greater than or equal to 6600 gpm at 245 psid with the pump eductor line open when tested pursuant to Specification 4.0.5; c.
At least once per 18 months, by:
l 1)
Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Spray Actuation test signal, and 2)
Verifying that each spray pump starts automatically on a Containment Spray Actuation test signal and on a Safety injection test signal.
i d.
At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
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COMANCHE PEAK - UNITS 1 AND 2 3/4 6-11 Unit 1 - Amendment No. +2,32 Unit 2 - Amendment f.s.18
1 CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The Spray Additive System shall be OPERABLE with:
a.
A spray additive tank indicating a level of between 91% and 94% of between 28% and 30% by weight Na0H solution, and b.
Four spray additive eductors each capable of adding Na0H solution from the chemical additive tank to a Containment Spray System pump fl ow.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With the Spray Additive System inoperable, restore the system 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 />; restore the Spray Additive System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l SURVEILLANCE REQUIREMENTS j
4.6.2.2 The Spray Additive System shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, j
a.
power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.
At least once per 6 months by:
1)
Verifying the indicated solution level in the tank, and j
2)
Verifying the concentration of the Na0H solution by chemical analysis.
)
i At least once per 18 months, by verifying that each automatic valve l
c.
in the flow path actuates to its correct position on a Containment Spray Actuation test signal; and d.
At least once per 5 years by verifying:
1)
The flow path through the Spray Additive supply line, and 2)
RWST test water flow rates of between 50 gpm and 100 gpm through the eductor test loop of each train of the Spray Additive System.
COMANCHE PEAK - UNITS 1 AND 2 3/4 6-12 Unit 1 - Amendment No. 32 Unit 2 - Amendment No. 18 1
CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves shall be OPERABLE.'
APPLICABILITY: MODES 1, 2, 3, and 4.,
ACTION:
- With one or more of the containment isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
a.
Restore the inoperable valve (s) 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 b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVE1LLANCE RE0VIREMENTS 4.6.3.1 The containment isolation valves shall be demonstrated OPERABLE prior l
to returning the valve to service after maintenance, repair or replacement i
work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time.
- The requirements of Specification 3.6.3 do not apply for those valves covered by Specifications 3.7.1.1, 3.7.1.5, 3.7.1.6, and 3.7.1.7.
]
- CAUTION: The inoperable isolation valve (s) may be part of a system (s).
Isolating the affected penetration (s) may affect the use of the system (s).
Consider the technical specification requirements on the affected system (s) and act acccrdingly.
COMANCHE PEAK - UNITS 1 AND 2 3/4 6-13
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE at least once per 18 months by:
a.
Verifying that on a Phase "A" Isolation test signal, each Phase "A" r
isolation valve actuates to its isolation position *;
b.
Verifying that on a Phase "B" Isolation test siEnal, each Phase "B" isolation valve actuates to its isolation position; and i
c.
Verifying that on a Containment Ventilation Isolation. test signal, each pressure relief discharge valve actuates to its isolation-position.
4.6.3.3 The isolation time of each power-operated or automatic valve shall be determined to be within' its limit when tested pursuant to Specification 4.0.5.
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- The surveillance test interval is extended to 24 months for testing the closure of valve 2-8160 on a Phase "A" isolation test signal (Train A, Unit 2), to remain in effect until the completion of the second refueling outage for Unit 2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 6-14 Unit 1 - Amendment No. 31,32
' nit 2 - Amendment No.17,18 U
4 w
r PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from two OPERABLE steam supplies.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With one auxiliary feedwater pump or associated flow path inoper-able, restore the required auxiliary feedwater pump or associated flow path 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.
With two auxiliary feedwater pumps or associated flow paths inoper-able, be in at least HOT STANDBY witin 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 />.
c.
With three auxiliary feedwater pumps or associated flow paths inop-
)
erable, immediately initiate corrective action to restore at least one auxiliary feedwater pump or associated flow path to OPERABLE status as soon as possible.
d.
With only one OPERABLE steam supply system capable of providing power to the turbine-driven auxiliary feedwater pump, restore the required OPERABLE steam supplies within 7 days or be in at least HOT i
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 />.
SURVEILLANCE RE0VIREMENTS 4.7.1.2 Each auxiliary feedwater pump and associated flew path shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1)
Verifying that each motor-driven pump develops a differential pressure of greater than or equal to 1372 psid at a flow of greater than or equal to 430 gpm; COMANCHE PEAK - UNITS 1 AND 2 3/4 7-3
PLANT SYSTEMS SURVE1LLANCE RE0VIREMENTS (Continued) 2)_
Verifying that the steam turbine-driven pump develops a
-differential pressure of greater than or equal to 1450 psid at a test flow of greater than or equal to 860 gpm when the secondary steam supply pressure is greater than 532 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; 3)
Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and 4)
Verifying that each auxiliary feedwater flow control and isolation valve in the flow path is in the fully open position whenever the Auxiliary Feedwater System is in standby for auxiliary feedwater automatic initiation or when above 10% RATED THERMAL POWER.
b.
At least once per 18 months by:
l 1)
Verifying that each automatic valve in the flow path actuates-to its correct position upon receipt of an Auxiliary feedwater Actuation test signal, and 2)
Verifying that each auxiliary feedwater pump starts as designed I
automatically upon receipt of an Auxiliary feedwater Actuation test signal *,
The provisions of Specification 4.0.4 are not i
applicable to the turbine driven auxiliary feedwater pump for i
entry into MODE 3.
- The surveillance test interval is extended to 24 months for testing the start of the Unit 2, Train A Motor Driven Auxiliary Feedwater Pump upon receipt of an Auxiliary feedwater Actuation test signal, to remain in effect until the completion of the second refueling outage for Unit 2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 7-4 Unit 1 - Amendment No. 31,32 Unit 2 - Amendment No. 17,18 s
I PLANT SYSTEMS i
3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
j With only one component cooling water loop OPERABLE, restore at least two l
loops 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEllLANCE RE0VIREMENTS 4.7.3 Each component cooling water loop shall be demonstrated OPERABLE:
At least once per_31 days by verifying that each valve (manual, a.
power-operated, or automatic) servicing safety-related equipment I
that is not locked, sealed, or otherwise secured in position is in I
its correct position; and b.
At least once per 18 months *, by verifying that:
l 1)
Each automatic valve servicing safety-related equipment I
actuates to its correct position on its associated engineered safety feature actuation signal, and 2)
Each Component Cooling Water System pump starts automatically
{
on a safety injection test signal.
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- The surveillance test interval is extended to 24 months for Train A, Unit 2, to remain in effect until the completion of the second refueling outage for Unit 2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 7-13 Unit 1 - Amendment No. 21,32 Unit 2 - Amendment No.17,'18
l PLANT SYSTEMS 3/4.7.4 STATION SERVICE WATER SYSTEM OPERATING LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent station service water loops per unit and the cross-connect between the Station Service Water Systems of each unit shall be OPERABLE.
APPLICABILITY: Units 3 and 2 in MODES 1, 2, 3, and 4.
ACTION:
L With only one station service water loop in a unit OPERABLE, restore a.
at least two loops per unit 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 for the unit (s) with the inoperable station service water loop be in at least HDT 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one or more of the cross-connects inoperable, within 7 days restore the cross-connect (s) to OPERABLE status. Otherwise 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEltLANCE REQUIREMENTS 4.7.4.3.3 Each station service water loop shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.
At least once per 18 months
- during shutdown, by verifying that each l
station service water pump starts automatically on a Safety Jnjection test signal.
4.7.4.1.2 At least once per 92 days the cross-connects shall be demonstrated OPERABLE by cycling the cross-connect valves in the flow path or verifying that these valves are locked open.
- The surveillance test interval is extended to 24 months for Train A, Unit 2, to remain in effect until the completion of the second refueling outage for Unit 2.
CDMANCHE PEAK - UNITS 3 AND 2 3/4 7-14 Unit 1 - Amendment No. 44,31 Unit 2 - Amendment No.17 e
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