ML20151K636
| ML20151K636 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/27/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151K641 | List: |
| References | |
| NUDOCS 8808030233 | |
| Download: ML20151K636 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
k WASHINGTON, D. C. 20555 j
l-p DUKE POWER COMPAllY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORAT10ll SAll'DA RIVER ELECTRIC COOPERATIVE, INC.
D0CKET N0. 50-413 CATA4BA NUCLEAR STATION, UNIT 1 AMEi,DMEllT TO FACILITY OPERATIllG LICEllSE Amendment No. 49 License No. NPF-35 1.
The fluclear Regulatory ConTnission (the Commission) has found that:
A.
The application for amendment to the Catawba fluclear 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 June 29, 1987, as supplemented December 4, 1987, ant
- ril 1, 1988, complies with the standards and requirements of th.
comic Energy Act of 1954, as amended (the Act), and the Commissicn's rules and regulations as set forth in 10 CFR Chapter I; B.
The fecility 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 'he 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 requirements have been satisfied.
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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 35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as rcvised through Amendment No. 49, 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 anendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMiilSSI0tl Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II
Attachment:
Technical Specification Changes Date of Issuance: July 27, 1988 l
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DtjKE POWER COMPAtlY NORTH CA001 INA fillflTCIPAL POWER AGEllCY t10.1 PIEDMONT l'.UllICIPAL POWER AGENCY DOCKET t10. 50-414 CATAWBA NUCLEAR STATION, UtlIT 2 APENDMEtlT TO FACILITY OPERATIllG LICENSE Amendment No. 42 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to che Catawbc Nuclear Station, Unit 2 (the facility) Facility Operat' cicense No. NPF-52 filed by the Duke Power Company acting fo-alf, North Ca olina Municipal Power l
Agency No.1 and Piedmont Mu.a., pal Power Agency, (licensees) dated June 29, 1987, as supplemented December 4, 1987, and April 1, 1988, complies with the standards and requirements of the Atonic 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 l
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 Comission's regulations set forth in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the common defense and security or +o 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 satis-fied.
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. 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 !!o. tiPF-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
42, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Enviror. mental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE ?!UCLEAR REGULATORY C0&iISS10tl Original signed by:
q David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of Issuance: July 27, 1988
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ATTACHf4ENT T0 LICEllSE AMENDMENT' NO. 49 FACILITY OPERATING LICENSE !!0. NPF-35 DOCKET fi0. 50-413 At:0 TO LICEl!SE AMEi!DI1ENT' NO. 42 FACILITY OPERATIllG LICENSE N0. flPF-52 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 nunber and contain vertical lines indicating the areas of. change.
Amended Page 3/4 3-9 3/4 3-12 e
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TABLE 4.3-1 c3 D
]E REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
TRIP ANALOG ACTUATING MODES FOR c
55 CHANNEL DEVICE WHICH gt CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED g
p.
j 1.
Manual Reactor Trip N.A.
N.A.
N.A.
R N.A.
1, 2, 3*, 4 *, 5*
s, 2.
Power Range, Neutron Flux a.
High Setpoint S
D(2, 4),
M N.A.
N. A.
1, 2 M(3, 4),
i Q(4, 6),
R(4, 5) b.
Low Setpoint S
R(4)
H N.A.
N.A.
1###, 2 R
- o 3.
Power Range, Neutron Flux, N.A.
R(4)
M N.A.
N.A.
1, 2 y
High Positive Rate u) 4.
Power Range, Neutron Flux, N.A.
R(4)
M N.A.
N.A.
1, 2 High Negative Rate S.
Intermediate Range, S
R(4, 5)
S/U(1),M N.A.
N.A.
1###, 2 Neutron Flux NE gg 6.
Source Range, Neutron Flux 5
R(4, 5)
S/U(1),M(9)
N.A.
N.A.
2##, 3, 4, 5
$E gg 7.
Overtemperature AT S
R M
N.A.
N.A.
1, 2 ee 8.
Overpower AT S
R M
N.A.
N.A.
1, 2 ypp[
CS 9.
Pressurizer Pressure-Low S
R M
N. A.
N.A.
1 jfjf 10.
Pressurizer Pressure-High S
R M
N.A.
N.A.
1, 2 11.
Pressurizer Water Level-High S
R M
N.A.
N.A.
1 s, g t
s-s-12.
Reactor Coolant Flow-Low S
R M
N.A.
N.A.
1
TABLE 4.3-1 (Continued)
TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.
Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.
Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) If not performed in previous 7 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(3) Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3%.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(4) Neutron aetectors may be excluded from CHANNEL CALIBRATION.
(5) Detector plateau curves shall be obtained, evaluated and compared to manufacturer's data.
For the Intermediate Range and Power Range Neutroa Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(7) Each train shall be tested at least everv 62 days on a STAGGERED TEST BASIS.
(8) With power greater than or equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive status light.
(9) Monthly surveillance in MODES 3*, 4*, and 5* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive status light.
(10) Setpoint verification is not applicable.
(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.
(12) Deleted (13) For Unit 1, CHANNEL CALIBRATION sh611 ensure that the filter time constant associated with Steam Generator Water Level Low-Low is adjusted to a value less than or equal to 1.5 seconds.
CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No. 49 (Unit 1)
Amendment No. 42 (Unit 2)
.