ML20107L039
| ML20107L039 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/23/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20107L041 | List: |
| References | |
| NUDOCS 9604290140 | |
| Download: ML20107L039 (11) | |
Text
s
',,pung
~
4 1
UNITED STATES g
g j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 o% *****/
i DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INCm DOCKET N0. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143 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 Di:ke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated January 11, 1996, as supplemented by letter dated April 2, 1996, 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 l
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.
9604290140 960423 PDR ADOCK 05000413 P
pop t
. =.
4
=
1 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:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.143
, and the Environmental Protection Plan i
contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
/
/
Her ert N. Berkow, Director Pr ject Directorate II-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 23, 1996 4
k a
p2 4to UNITED STATES y *-
4 s
j NUCLEAR REGULATORY COMMISSION l
WASHINGTON. D.C. mm01
.....f*
~
DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 E110MONT MUNICIPAL POWER AGENCY 1
DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 137 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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.1 and Piedmont Municipal Power Agency (licensees), dated January 11, 1996, as supplemented by letter dated April 2,1996, 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 poblic; 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.
I
. 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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 137, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hert rt N. Berkow, Director Pro;ect Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes i
Date of Issuance: April 23,1996 l
i 1
l l
l 1
ATTACHMENT TO LICENSE AMENDMENT NO.143 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. NPF-52 j
DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with i
the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
I Remove Paaes Insert Paaes 3/4 6-6 3/4 6-6 3/4 6-7 3/4 6-7 3/4 6-27 3/4 6-27 3/4 6-29 3/4 6-29 3/4 6-35 3/4 6-35 3/4 6-37 3/4 6-37 i
i 1
e
TABLE 3.6-1 (Continued)
SECONDARY CONTAIMENT BYPASS LEAKAGE PATHS 5
PENETRATION TEST NUMBER SERVICE RELEASE LOCATION JRf C
M323 Component Cooling to Component Cooling Drain Sump Auxiliary Building Type C m
a-M240 Nuclear Service Water to Reactor Coolant Pump and Lower Cont.
m Vent. Units Auxiliary Building Type C M230 Nuclear Service Water From Reactor Coolant Pump and Lower Cont.
Vent. Units Auxiliary Building Type C w
M385 Nuclear Service Water to Upper s
Containment Ventilation Units In Turbine Building Type C M308 #
Nuclear Service Water to Upper g
Containment Ventilation Units Out Turbine Building Type C M213 Incore Instrumentation Room Purge In Auxiliary Building Type C EE M140 Incore Instrumentation Room Purge Out Auxiliary Building Type C M456 Upper Compartment Purge Inlet Auxiliary Building-Type C M432 Upper Compartment Purge Inlet Auxiliary Building Type C E E.
M357 Lower Compartment Purge Inlet Auxiliary Building Type C M368 Containment Purge Exhaust Auxiliary Building Type C S
M433 Containment Purge Exhaust Auxiliary Building Type C M434 Lower Compartment Purge Inlet Auxiliary Building Type C m._.
L m
e TABLE 3.6-1 (Continued) g SECONDARY CONTAllmENT BYPASS LEAKAGE PATHS
-4 E
PENETRATION TEST E
NUMBER SERVICE RELEASE LOCATION JRE g
M386 Containment Air Release Auxiliary Building Type C b
M204 Containment Air Addition Auxiliary Building Type C e-M316 Int. Fire Protection Header -
Auxiliary Building Type C
~
Hose Racks M337 Demineralized Water Auxiliary Building Type C M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C M215 Breathing Air Auxiliary Building Type C M329 Reactor Coolant Pump Motor Oil Fill Auxiliary Building Type C M361 Int. Fire Protection Header -
Auxiliary Building Type C Sprinklers s&
M119 Containment Purge Exhaust Auxiliary Building Type C M331 Nitrogen Supply to Cold Leg Auxiliary Building Type C Accumulators en y2 M322 Safety Injection Test Line Auxiliary Building Type C Q
M454 UHI Test Line Auxiliary Building Type C )
Note 1 M328*
Component Cooling to Reactor Auxiliary Building Type C
((
Vessel Support and RCP Coolers en 50
- Not applicable for Unit 1 until after the first refueling outage.
- Not applicable for Unit I after refueling outage IE0C9. Not applicable for Unit 2 after refueling outage 2E0C8. l Note 1:
Upon capping of penetrations associated with deletion of UHI, this specification is no longer applicable.
~
m_
TABLE 3.6-2a (Continued) 9g CONTAllmENT ISOLATION VALVES z5 MAXIltM VALVE NUMBER FUNCTION ISOLATI0K TIME (s) i 2.
Phase "B" Isolation (Continued) 1 RN-4378 Supply to NC Pumps and LCVU Supply Outside Containment Isolation s 60 w=
RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation s 60 m
RN-487A Return from NC Pumps and LCVU Return Outside Containment Isolation s 60 RN-4048 Supply to Upper Containment Supply Ventilation Units Containment s 10 Isolation (Outside)
RN-429A ##
Return from Upper Containment Ventilation Units Containment Isolation s 10 l
(Inside)
RN-432B ##
Return from Upper Containment Ventilation Units Containment Isolation s 10
~l (Outside) s" VI-77B Instrument Air Containment Outside Isolation s 10
?
SM-1 #
Main Steam ID Isolation MA SM-3 #
Main Steam IC Isolation NA SM-5 #
Main Steam IB Isolation NA SM-7 #
Main Steam 1A Isolation NA r
SM-9 #
Main Steam ID Isolation Bypass Ctrl.
NA FF SM-10 #
Main Steam IC Isolation Bypass Ctrl.
NA SM-11 #
Main Steam 1B Isolation Bypass Ctrl.
NA 4
SM-12 #
Main Steam lA Isolation Bypass Ctrl.
NA SV-19 #
Main Steam 1A PORV NA fE SV-13 #
Main Steam 18 PORV NA SV-7 #
Main Steam IC PORV NA C%
SV-1 #
Main Steam ID PORV NA l
l WL-867A**
Containment Vent Unit Drains Inside Containment Isolation s 10 WL-869B**
Containment Vent Unit Drains Outside Containment Isolation s 10 EE
=
3:
i
TABLE 3.6-2a (Continued)
UNIT 1 CONTAINMENT ISOLATION VALVES 5
MAXIMUM i
VALVE NUMBER FUNCTION ISOLATION TIME (s)
C 3.
Manual (Continued) m SM-103#
Main Steam IC NA sa SM-Il9#
Main Steam IC NA m
SM-141#
Main Steam IC NA l
SA-4#
Main Steam IC NA SM-19#
Main Steam ID NA SM-70#*
Main Steam 10 NA SM-102#
Main Steam ID NA l
SM-Il8#
Main Steam ID NA 1
SM-140#
Main Steam 10 NA l
R WE-20*
Cont Bldg Supply Isol NA WE-22*
Cont Bldg Supply Isol NA
?
WE-56*
Cont Bldg Supply Isol NA FW-4*
Refueling Water NA NV-862#*
Pressurizer Auxiliary Spray ND Outside Containment NA WLA-21#*
Steam Generator Drain Pump Discharge Outside Containment Isolation NA WLA-24#*
Steam Generator Drain Pump Discharge Outside Containment Isolation NA EE TABLE NOTATIONS Q
- May be opened on an intermittent basis under administrative control.
EE
- Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.
([a
- Not subject to Type C leakage tests.
- Not applicable to Unit 1 after refueling outage IEOC9.
__Es
?%
NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times.
See Specification 3/4 3.2 for system actuation response times.
6
TABLE 3.6-2b (Continued) n UNIT 2 CONTAINMENT ISOLATION VALVES 5
MAXIMUM i
VALVE NUMBER FUNCTION ISOLATION TIME (s) c 2.
Phase "B" Isolation (Continued)
RN-437B Supply to NC Puaps and LCVU Supply Outside Containment Isolation s 60 p-RN-484A Return from NC Pumps and LCVU Return Inside Containment Isolation s 60 m
RN-487A Return from NC Pumps and LCVU Return Outside Containment Isolation s 60 RN-404B Supply to Upper Containment Supply Ventilation Units Containment s 10 Isolation (Outside)
RN-429A ##
Return from Upper Containment Ventilation Units Containment Isolation s 10 l
l (Inside)
RN-4328 ##
Return from Upper Containment Ventilation Units Containment Isolation s 10 l
(Outside)
VI-778 Instrument Air Containment Outside Isolation s 10 M
SM-1 #
Main Steam 2D Isolation NA SM-3 #
Main Steam 2C Isolation NA SM-5 #
Main Steam 2B Isolation NA SM-7 #
Main Steam 2A Isolation NA SM-9 #
Main Steam 2D Isolation Bypass Ctrl.
NA
??
SM-10 #
Main Steam 2C Isolation Bypass Ctrl.
NA SM-11 #
Main Steam 2B Isolation Bypass Ctrl.
NA SM-12 #
Main Steam 2A Isolation Bypass Ctrl.
NA SV-19 #
Main Steam 2A PORV NA FF SV-13 #
Main Steam 2B PORV NA SV-7 #
Main Steam 20 PORV NA Q{
SV-1 #
Main Steam 20 PORV NA WL-867A**
Containment Vent Unit Drains Inside Containment Isolation s 10
((
WL-869B**
Containment Vent Unit Drains Outside Containment Isolation s 10 en
~=
s I
_ ~
l TABLE 3.6-2b (Continued) n l
UNIT 2 CONTAINMENT ISOLATION VALVES 5
MAXIMUM i
VALVE NUMBER FUNCTION ISOLATION TIME (s)
C 3.
Manual (Continued) en SM-103#
Main Steam 2C N.A.
p-SM-119#
Main Steam 2C N.A.
m SM-141#
Main Steam 2C N.A.
l SA-4#
Main Steam 2C N.A.
l SM-19#
Main Steam 20 N.A.
i SM-70#*
Main Steam 2D N.A.
SM-102#
Main Steam 2D N.A.
SM-118#
Main Steam 20 N.A.
l SM-140#
Main Steam 20 N.A.
l R
WE-20*
Cont Bldg Supply Isol N.A.
WE-22*
Cont Bldg Supply Isol N.A.
?
WE-56*
Cont Bldg Supply Isol N.A.
ti FW-4*
Refueling Water N.A.
i l
NV-862#*
Pressurizer Auxiliary Spray ND Outside Containment N.A.
l WLA-21#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
l WLA-24#*
Steam Generator Drain Pump Discharge Outside Containment Isolation N.A.
- May be opened on an intermittent basis under administrative control.
- E
- Valve also receives a High Radiation (H) and/or a High Relative Humidity isolation signal.
kh
- Not subject to Type C leakage tests.
- Not applicable to Unit 2 after refueling outage 2EOC8.
l'
--EE
??
NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times.
See Specification 3/4 3.2 for system actuation response times.
f
,