ML20137L403
| ML20137L403 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/03/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137L409 | List: |
| References | |
| NUDOCS 9704070218 | |
| Download: ML20137L403 (16) | |
Text
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I f **h 1 UNITED STATES p
NUCLEAR REGULATORY COMMISSION l
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I wassworou, o.c. -
l DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated January 3,1997, as supplemented by letter dated March 20, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as
]
set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized i
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 set i
forth in 10 CFR Chapter I; D.
The issuance of this 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.
9704070218 970403 PDR ADOCK 05000413 P
. t 2.
Accordingly, the license is hereby amended by page 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-35 is hereby amended to read as follows:
(2)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 158, which are attached hereto, are hereby incorporated into this license. Duke i
Power Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and sball be implemented before startup from the next refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
/.
L H bert N. Berkow, Director oject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment.
Technical Specification Changes Date of Issuance: April 3, 1997 l
1
8]JACHMENT T0 LICENSE AMENDMENT NO.158 EAO LITY 0 PIRATING LICENSE NO. NPF-35 POCKET NO. 50-413 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 3-15 3/4 3-15 3/4 3-29 3/4 3-29 3/4 3-40 3/4 3-40 3/4 3-44 3/4 3-44 B 3/4 3-3 B 3/4 3-3 i
l
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 1. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered Exhaust Operation, Emergency Diesel Generator Operation, Component Cooling Water, Turbine Trip, and Nuclear Service Water Operation) a.
Manual Initiation 2
1 2
1, 2, 3, 4 18 b.
Automatic Actuation 2
1 2
1, 2, 3, 4 14 Logic and Actuation Relays c.
Containment 3
2 2
1, 2, 3 15 Pressure-High d.
Pressurizer 4
2 3
1, 2, 3#
19 Pressure-Low CATAWBA - UNIT 1 3/4 3-15 Amendment No. 158
. TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION TRIP SETPOINTS" FUNCTIONAL UNIT TRIP SETPOINT-ALLOWABLE VALUE 4
- 1. Safety Injection (Reactor Trip,
.. Phase."A" Isolation, Feedwater Isolation, Control Room Area
-Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus
~ Ventilation Operatio1, Auxiliary Building F'lltered Exhaust Operation, Emergency i
Diesel Generator Operation, Component Cooling Water, Turbine Trip,'and Nuclear Service Water Operation) a.
Manual Initiation M.A.
N.A.
I b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays c.
Containment Pressure-High s 1.2 psig s 1.4 psig d.
Pressurizer Pressure-Low 2 1845 psig 2 1839 psig
- 2. Containment Spray a.
Manual Initiation N.A.
N.A.
b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays c.
Containment Pressure-High-High s 3 psig s 3.2 psig.
' CATAWBA - UNIT 1 3/4 3-29 Amendment - No.- 158 i
TABLE 3.3-5 t
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATION SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 4.
Steam Line Pressure-Low Steam Line Isolation s 10 5.
Containment Pressure-High-High a.
Containment-Spray 5 45 b..
Phase "B" Isolation s 65(3)/76"3 Nuclear Service Water Operation N.A.
c.
Steam Line Isolation 5 10 d.
Containment Air Return and Hydrogen s 600 Skimmer Operation 6.
Steam Line Pressure - Negative Rate-High Steam Line Isolation s 10 j
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4 I
CATAWBA - UNIT 1 3/4 3-40 Amendment No.158
TABLE 4.3 '
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION-SURVEILLANCE REQUIRENENTS s
TRIP-ANALOG ACTUATING MODES L
CHANNEL.
DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL' OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IESI JESI IS REQUIRED
- 1. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary i
?
Feedwater-Motor-Driven Pump, Purge and Exhaust Isolation, Annulus Ventilation Operation,
' Auxiliary Building Filtered Exhaust Operation, Emergency Diesel Generators Operation, Component Cooling Water, Turbine Trip,-and Nuclear Service Water Operation) 4 a.
Manual Initiation M.A.
N.A.
N.A.
R N.A.
N.A N.A.
1, 2, 3, 4' b.
Automatic Actua-N.A.
N.A.
N.A.
N.A.
N(1)
N(1)
Q.
1, 2, 3, 4 f
tion Logic and Actuation Relays
=i c.
Containment S
R Q
N.A.
N.A..
N.A W.A.
1, 2, 3 i
Pressure-High t
I d.
Pressurizer S
R Q
N.A.
N.A.
. M.A N.A.
1, 2, 3 -
Pressure-Low i
l 1
CATAWBA - UNIT I 3/4 3-44 Amendment No.158 P
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INSTRUMENTATION 1
~ BASES j
-REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
J
[
. The' Engineered Safety Features Actuation-System interlocks perform the
'l j
following functions:
'P-4:
Reactor tripped - Actuates Turbine trip, closes main feedwater valves-1 on T-below Setpoint, prevents the opening of the main feedwater valv7e which were closed by a Safety Injection or High Steam-Generator Water Level-signal, allows safety' injection block so that components can be reset or tripped..
y Reactor not trip ~ ed - prevents manual block of Safety Injection.
p
~
.P-ll Defeats the manual block of Safety Injection actuat' ion on low pres-4
'surizer pressure and defeats steam line isolation on negative steam
-l line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.
P-12 On decreasing reactor coolant loop temperature, P-12 automatically.
' blocks steam dump and allows manual bypass of steam dump block for l
the cooldown valves only. On increasing reactor coolant loop temper-ature, P-12 automatically defeats the manual bypass of the steam dump block.
P-14
.On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater control valve modulation.
L Surve111ances for the Reactor Trip Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985.
j 3/4.3.3 MONITORING INSTRUMENTATION j
j-3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS i
The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:
(1) the associated action will be initiated when the 1
radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained,'and (3) suffi-cien: iredundancy is maintained to permit a channel to be out-of-service for i
testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits.are being exceeded. The radiation monitors send
- actuation. signals to initiate alarms or automatic isolation action and actuation.of Emergency Exhaust or Ventilation Systems.
Some of the final F
actuations are dependent on plant condition in addition to the actuation signals'from the radiation monitors.
s CATAWBA'- UNIT 1 B 3/4 3-3 Amendment No.158 a
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t UNITED STATES i
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20006 4 001
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1
\\
PIEDMONT MUNICIPAL POWER AGENCY.
DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 i
License No. NPF-52 l.
The Nuclear Regulatory Commission (the Commission) has found that:
j i
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No I and Piedmont Municipal Power Agency (licensees), dated January 3,1997, as supplemented by letter dated March 20, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, 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 set forth in 10 CFR Chapter I; D.
The issuance of this 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 hen satisfied.
i 4
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t i
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2.
Accordingly, the license is hereby amended by page 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-52 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.150
, which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented before.startup from the current refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION x
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II
)
Office of Nuclear Reactor Regulation
]
l Attachment.
Technical Specification Changes Date of Issuance: April 3,1997 i
i
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4 i
i
ATTACHMENT TO LICENSE AMENDMENT NO.
150 FACILITY OPERATING LICENSE NO. NPF-52 i
DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
i Remove Insert 3/4 3-15 3/4 3-15 3/4 3-29 3/4 3-29 3/4 3-40 3/4 3-40 4
3/4 3-44 3/4 3-44 B 3/4 3-3 8 3/4 3-3 i
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y 4
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TABLE 3.3 i ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtMENTATION MININUM TOTAL NO.
CHANNELS CHANNELS APPLICA8LE-FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION l'. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered Exhaust Operation, Emergency Diesel Generator operation, Component Cooling Water,
+
Turbine Trip, and Nuclear Service Water Operation) a.
Manual Initiation 2
1 2
1,2,3,4 18 b.
Automatic Attuation 2
1 2
1, 2, 3,;4
- 14 Logic and Actuation Relays c.
Containment 3
2 2
1,2,3 15.
Pressure-High d.
Pressurizer-4 2
3 1,'2, 3#
19 Pressure-Low i
l 1
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CATAWBA - UNIT 2 3/4'3-15 Amendment No. 150 b
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TABLE 3.3-4 i
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS -
e FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE
-1. Safety Injection (Reactor Trip,
-Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, I
Purge & Exhaust Isolation, Annulus Ventilation. Operation, Auxiliary Building Filtered
~!
Exhaust Operation, Emergency
. Diesel Generator Operation, Component Cooling Water, i
Turbine Trip, and Nuclear Service Water Operation)
J a.
Manual Initiation N.A.
N.A.
l b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays c.
Containment Pressure-High s 1.2 psig s 1.4 psig d.
Pressurizer Pressure-Low 2 1845 psig 2 1839 psig l-
- 2. Containment Spray t
a.
Manual Initiation N.A.
N.A.
b.
Automatic Actuation Logic N.A.
N.A.
i and Actuation Relays i
c.
Containment Pressure-High-High s 3 psig 5 3.2 psig 1
CATAWBA - UNIT 2 3/4 3-29 Amendment No..150 i
.i u
... _.... _. ~. _. -,. _ _ _..... -... _...
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS j
J 4.
Steam Line Pressure-Low Steam Line Isolation s 10
)
5.
Containment Pressure-High-High j
a.
Containment Spray 5 45 b.
Phase "B" Isolation s 65(3)/76")
Nuclear Service Water Operation N.A.
I c.
Steam Line Isolation s 10 d.
Containment Air Return and Hydrogen s 600 Skimmer Operation 6.
Steam Line Pressure - Negative Rate-High Steam Line Isolation s 10 CATAWBA UNIT 2 3/4 3-40 Amendment No. 150
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER-SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IllI IISI IS REQUIRED
- 1. Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Purge and Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered Exhaust Operation, Emergency Diesel Generators Operation, Component Cooling Water, Turbine Trip,.and Nuclear Service Water Operation) a.
Manual Initiation N.A.
N.A.
N.A.
R N.A.
M.A.
N.A.
1, 2, 3, 4 b.
Automatic Actua-N.A.
N.A.
N.A.
N.A.
.N(1)
N(1)
Q 1, 2, 3, 4 tion Logic and Actuation Relays c.
Containment S
R Q
N.A.
N.A.
N.A.
N.A.
1, 2, 3 Pressure-High d.
Pressurizer S
R Q
N.A.
N.A.
N.A.
N.A.
1, 2, 3 Pressure-Low i
l l
l l
i l
l CATAWBA - UNIT 2 3/4 3-44 Amendment No. 150 l
f INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
The Engineered Safety Features Actuation System interlocks perform the following' functions:
P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves t
on T below Setpoint, prevdnts the opening of the main feedwater
- valve? which were closed by a Safety Injection or High Steam Generator Water' Level signal, allows safety injection block so that components can be reset or tripped.
Reactor not tripped - prevents manual block of Safety Injection.
i P-11 Defeats the manual block of Safety Injection actuation on low pres-1 surizer pressure and defeats steam line isolation on negative steam l
i line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.
j P-12 On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump block for the cooldown' valves only. On increasing reactor coolant loop temper-l ature, P-12 automatically defeats the manual bypass of the steam dump block.
P-14 On increasing steam generator level, P-14 automatically trips all feedwater isolation valves, pumps and turbine and inhibits feedwater control valve modulation.
Surveillances for the Reactor Trip Bypass Breakers are included in response to the NRC's Generic Letter 85-09, dated May 23, 1985.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.I RADIATION MONITORING FOR PLANT OPERATIONS I
The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:.(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint -(2).the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of-service for
. testing or maintenance. The radiation monitors for plant operations sense radiation levels in-selected plant systems and locations and determine whether o
or not predetermined limits are being exceeded. The radiation monitors send actuation signals to initiate alarms or automatic isolation action and actuation.of Emergency Exhaust or Ventilation Systems. Some of the final
'actuations are dependent on plant condition in addition to the actuation signals from the radiation monitors.
t h'
CATAWBA - UNIT 2 B 3/4 3-3 Amendment No. 150 c-w
., e.
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,