ML20244D291
| ML20244D291 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/14/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244D293 | List: |
| References | |
| NUDOCS 8904210269 | |
| Download: ML20244D291 (13) | |
Text
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UNITED STATES E
1 NUCLEAR REGULATORY COMMISSION 5
g WASHINGTON, D. C. 20555
(...../
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 OPEP.ATING LICENSE Amendment No. 61 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 Septenber 19, 1988, as supplemented December 28, 1988, and March 6, 1989, 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 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 Comission; C.
There is reasonable assurance (1) 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 Comission'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.
/
/
8904210269 890414 PDR ADOCK 05000413 P
1 2.
Accordingly, the lic.ense is hereby amended by page changes to the Technical Specifications as indicated in the attachments 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendnent No.
61, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with tre Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUC EAR REGULATORY COMMISSION v
i avid Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
April 14, 1989 I
P..
c.
. 2.
Acco dingly, the license is hereby amended by 'page changes to the Technical Specifications as indicated in the attachments 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 Specifications The Technical Specifications contained in Appendix A, as. revised
- through Amendment No. 61,, are hereby incorporated into the license.
The licensee shallioperate the facility in'accordance with the Technical Specifications and the Environmental Protection Plan.
I 3.
This license amendment is effective as of.its date' of issuance.
FOR.THE NUCLEAR REGULATORY C0HHISSION-
/'
David B. Matthews, Director Project Directorate II-3
' Division of. Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
April 14, 1989 OFFICIAL RECORD COPY l
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o UNITED STATES 8'
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NUCLEAR REGULATORY COMMISSION o
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- E WASHINGTON. D. C. 20555 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. 55 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Comission) 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 September 19, 1988, as supplemented December 28, 1988, and March 6, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1989, complies with the standards and re
, 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 ar.d 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 i
defense and security or to the health and safety of the public; and j
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 attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby 1
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 55
, are hereby incorporated into the license.
The licensee 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.
FOR THE NUCLEAR REGULATORY COMMISSION
[
David B.
atthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of' Issuance:
April 14, 1989 l
- 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments 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 Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No.
55, are hereby incorporated into the license.
The licensee 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.
FOR THE NUCLEAR REGULATORY C0ffilSSION David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation Attachnent:
Technical Specification Changes Date of Issuance:
April 14, 1989 i
i i
1 I
0FFICIAL RECORD COPY
/
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ATTACHMENT TO LICENSE AMENDMENT NO. 61 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDMENT NO.
55 FACILITY OPERATING LICENSE NO. NPF-52
.o DOCKET N0. 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.
The corresponding over-leaf page is also provided to maintain document completeness.
Amended Page Overleaf Page 2-5 3/4 3-29 3/4 3-30 3/4 3-31 B 2-7 8 2-8 1
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LIMITING SAFETY SYSTEM SETTINGS BASES Steam Generator Water Level The Steam Generator Water Level Low-Low trip protects the reactor from loss of heat sink in the event of a sustained steam /feedwater flow mismatch resulting from a loss of normal feedwater or a feedwater system pipe break.
l The specified Setpoint provides allowances for starting delays of the Auxiliary Feedwater System as well as for errors in the level instrumentation.
l Undervoltage and Underfrequency - Reactor Coolant Pump Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips pro-vide core protection against DNB as a result of complete loss of forced coolant flow.
The specified Setpoints assure a Reactor trip signal is generated before the Low Flow Trip Setpoint is reached.
Time delays are incorporated in the Underfrequency and Undervoltage trips to prevent spurious Reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required for a signal to reach the Reactor trip breakers following the simultaneous trip of two or more reactor coolant pump bus circuit l
breakers shall not exceed 1.2 seconds.
For underfrequency, the delay is set so that the time required for a signal to reach the Reactor trip breakers after the Underfrequency Trip Setpoint is reached shall not exceed 0.3 second.
On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approximately 10%
l of RATED THERMAL POWER; with a turbine impulse chamber pressure at approxi-mately 10% of full power equivalent); and on increasing power, reinstated l
automatically by P-7.
i Turbine Trip A Turbine trip initiates a Reactor trip.
On decreasing power the Reactor trip from the Turbine trip is automatically blocked by P-9 (a power level of approximately 69% of RATED THERMAL POWER); and on increasing power, reinstated automatically by P-9.
Safety Injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip 1
System instrumentation, the ESF automatic actuation logic channels will l
initiate a Reactor trip upon any signal which initiates a Safety Injection.
The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.
l l
CATAWBA - UNITS 1 & 2 B 2-7 Amendment No. 61 (Unit 1) l Amendment No. 55 (Unit 2)
,j LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Trip System Interlocks The Reactor Trip System interlocks perform the following functions:
P-6 On increasing power P-6 allows the manual block of the Source Range trip (i.e., prevents premature bicek of Source Range trip), deener-gizes the high voltage to the detectors.
On decreasing power, Source Range Level trips are automatically reactivated and high voltage restored.
P-7 On increasing power P-7 automatically enables Reactor trips on low flow in more than one reactor coolant loop, reactor coolant pump bus undervoltage and underfrequency, pressurizer low pressure and pressurizer high level.
On decreasing power, the above listed trips are automatically blocked.
P-8 On increasing power P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops.
On decreasing power, the P-8 automatically blocks the above listed trips.
P-9 On increasing power P-9 automatically enables Reactor trip on Turbine trip.
On decreasing power, P-9 automatically blocks Reactor trip on Turbine trip.
P-10 On increasing power P-10 allows the manual block of the Intermediate Range trip and the Low Setpoint Power Range trip; and automatically blocks the Source Range trip and deenergizes the Source Range high voltage power.
On decreasing power, the Intermediate Range trip and the Low Setpoint Power Range trip are automatically reactivated.
Provides input to P-7.
P-13 Provides input to P-7.
CATAWBA - UNITS 1 & 2 8 2-8 1