ML20112E451
| ML20112E451 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/31/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20112E453 | List: |
| References | |
| NUDOCS 9606060090 | |
| Download: ML20112E451 (9) | |
Text
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,p M tto Jh UNITED STATES v
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B NUCLEAR REGULATORY COMMISSION U
I WASHINGTON. D.C. 20mwo001 49.....,o 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. 146 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) 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 November 15, 1995, as supplemented March 15, and April 10, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth 6.to 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 Comission; 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 been satisfied.
9606060090 960531 ADOCK0500g3 DR
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} 2.
Accordingly, the license is hereby amended by page changes to the t
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 Snecifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix'A, as revised 1
through Amendment No.146., 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 4
i Specifications and the Environmental Protection Plan, j
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION i
fAjf/'
/Hf H rbert N.-Be dow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Technical Specification l
Changes Date of Issuance: May 31, 1996 i
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't UNITED STATES S
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 20645 0001 4
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9 DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 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. I and Piedmont Municipal Power Agency (licensees), dated November 15, 1995, as supplemented March 15, 4
and April 10, 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 i
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 Commission's regulations and all applicable i
requirements have been satisfied.
l
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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:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 140, 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 3
Specifications and the Environmental Protection Plan.
I 3.
This license amendment is effective as of its date of issuance and shall il be implemented within 30 days from the date of issuance.
FOR THE NUCL AR EGULATORY COMMISSION du i
l He ert N. Ber
,D ector i
P oject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation I
Attachment:
j Technical Specification i
Changes
(
Date of Issuance: May 31, 1996 l
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' ATTACHMENT TO LICENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. NPF-35 2
DOCKET NO. 50-413 2
i
.1' TO LICENSE AMENDMENT NO. 1an 4
FACILITY OPERATING LICENSE NO. NPF 52 DOCKET NO. 50-414 i
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 Paaes Insert Paaes 3/4 7-1 3/4 7-1 1
3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-3 B 3/4 7-1 B 3/4 7-1 I
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a3 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES i
LIMITING CONDITION FOR OPERATION l
3.7.1.1 All main steam line Code safety valves associated with each steam i
generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
APPLICABILITY: MODES 1, 2, and 3.
- ACTION:
With four reactor coolant loops and associated steam generators in a.
operation and with one or more main steam line Code safety valves i
inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least H0T 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 />.
A b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.
During surveillance testing, as-left lift settings shall be within i 1%.
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4 CATAWBA - UNITS 1 & 2 3/4 7-1 Amendment No. 146 (Unit 1) 4 Amendment No. 140 (Unit 2) i
TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH j
INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION
\\
MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1 87 l
2 65 1
3 43 1
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CATAWBA - UNITS 1 & 2 3/4 7-2 Amendment No.146 (Unit !)
Amendment No.140 (Unit 2)
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TABLE 3.7-2 l
h STEAM LINE SAFETY VALVES PER LOOP
=
2 VALVE NUMBER LIFT SETTING * (t 3%)
ORIFICE SIZE l
Looo A Loon 8 Loon C Loop D 1.
SV-20 SV-14 SV-8 SV-2 1175 psig 14.18 in.2 c.
2.
SV-21 SV-15 SV-9 SV-3 1190 psig 14.18 in.2 3.
SV-22 SV-16 SV-10 SV-4 1205 psig 14.18.in.2
'4.
SV-23 SV-17 SV-Il SV-5 1220 psig 14.18 in.2 5.
SV-24 SV-18 SV-12 SV-6 1230 psig 14.18 in.2 a
7' w
- The lift setting pressure shall correspond to ambient onditions of the valve at nominal operating temperature and pressure.
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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main ' steam line Code safety valves ensures that the Secondary System pressure will be limited to within 110% (1304 psig) of its design pressure of 1185 psig during the most severe anticipated system operational transient. The maximum relieving capacity is associated with a Turbine trip from valve wide-open condition coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are.in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. Table 3.7-2 allows a i 3% setpoint tolerance for OPERABILITY; however, the valves are reset to i 1% during surveillance testing to allow for drift. The steam lines is 16.l5 x 10}otal relieving capacity for all valves on all of the lbs/h which is 105% of the total secondary steam flow of 16.05 x 10 lbs/h at 100% RATED THERMAL POWER.. A minimum of two -
OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable ~ THERMAL POWER restriction'in Table 3.7-1.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary' Coolant System steam flow and THERMAL POWER required by the -
reduced Reactor trip settings of the Power Range Neutron Flux channels.
The Reactor Trip.Setpoint reductions are derived on the following bases:
For four loop operation (X) - (Y)(V) x (109)
SP =
X Where:
SP'=
Reduced Reactor Trip Setpoint in percent of. RATED THERMAL
- POWER, Maximum numbe'r o'f inoperable safety valves per steam line, V
=
Power Range Neutron Flux-High Trip Setpoint for four loop 109 operation, X --
Total relieving capacity of all safety valves per steam line in 1bs/ hour, and Maxi:num relieving capacity of any one safety valve in Y
=
1bs/ hour Amendment No. 146 (Unit 1)
Amendment No. 140 (Unit n CATAWBA - UNITS l'& 2 B 3/4 7-1
.