ML20151L611
| ML20151L611 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/28/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151L617 | List: |
| References | |
| NUDOCS 8808040095 | |
| Download: ML20151L611 (7) | |
Text
._
/
'o UNITED STATES
~,,
NUCLEAR REGULATORY COMMISSION o
g E
WASHING TON, D. C. 20555
,o DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 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 Juke Power Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,
(licensees dated February 15, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissior.'s rules and regulations as set forth in 10 CFR Chapter I; 8.
The facility will optrate iq confurrtity wit.1 the application, tne provisions of the Act, and the rules and regulations of the Commission; I
C.
There is reasonable assurance (1) that the activities authorized by this amendment car, 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 comon 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.
8808040095 380720 DR ADOCK 050004 3 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-35 is hereby-amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.51
, 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 HUCLEAR REGULATORY COMMISSION Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of issuance:
July 28, 1988 l
t d
I 0FFICIALRECORDCOPYW Ky.J ff' c
g v
i I
ifR&&a{I-3 LA:P PM:PDil-3 SP ST DPLB C
D:PDII-3 d
KJabbour:pw JCr fro DMatthews 6W/88 f/M/88 s/21/88 9 /u /88 7/d/88
/
\\
MDR2:AORP:HRR G1 itias 8
ffH%9 4.,
4 UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555
\\*..../
DUKE POWER COMPANY
@RTHCAROLINAMUNICIPALPOWERAGENCYN0.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET N0. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-52 1.
The Nuclear Regulatory Comission (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. 1 and Piedmont Munici]al Power Agency, (licensees) dated February, 15, 1988, complies wit 1 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 (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 witn the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 l
of the Comission's regulations and all applicable requirements have been satisfied.
l l
l l
l l
l
2.-
Accordingly, the license is hereby amended by pa0e 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 contuined in Appendix A, as revised through Amendment No.
44, 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-Original signed by:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of Issuance: July 28, 1988 l
o i
g g#
g#
th pI f
0FFICIAL REC 0PD COPY LA: p PH/
11-3 SP B-ST DPLB:
SJ OGC-WF D:PDII-3 MRd{od'{I-3 KJabbour:pw JCr g FRos W
DMatthews f//f/88 f////88
/
88
- /2 88
/ /88 7/gf/88 AD.:A P(NRR GL a
/
ATTACHMENT TO LICENSE AMENDMENT 110. 51 FACILITY OPERATING.lCENSE NO. NPF-35 D0 3ET NO. 50-413 AND TO LICENSE AMENDMENT N0. 44 FACILITY OPERATING LICENSE N0. NPF-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 number and contain vertical lines indicating the areas of change.
Amended Page 3/4 8-6 3/4 8-7
m ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b)
Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.
After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 volts and 60 + 1.2 Hz during this test;** and c)
Verifying that all automatic diesel generator trips, except engine overspeed, low-low lube oil pressure, generator differential, and the 2 out of 3 voltage controlled overcurrent relay scheme, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal.
7)
Verifying, during shutdown, the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The diesel generator shall be loaded to greater than or equal to 5600 kW but less than or equal to 5750 kW.
The generator voltage and frequency shall be 4160 + 420 volts and 60 + 1.2 Hz within 11 seconds after the start signal; the steady! state generator voltage and frequency shall be maintainea within these limits during this test.
8)
Verifying, during shutdown, that the auto-connected loads to each diesel generator do not exceed 5750 kW;**
3)
Verifying, during shutdown, the diesel generator's capability to:**
a)
Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b)
Transfer its loads to the offsite power source, and c)
Be restored to its standby status.
- 10) Verifying, during shutdown, that with the diesel generator operating in a test mode, connected to its bus, a simulated Safety Injection signal overrides the test mode by: (1) return-l ing the diesel canerator to standby operation, and (2) automati-cally energiz; 4. L
- emergency loads with offsite power;**
- This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.
CATAWBA - UNITS 1 & 2 3/4 8-6 Amendment No. 51 (Unit 1)
Amendment No.44 (Unit 2)
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 11) Verifying that the fuel transfer valve transfers fuel from each fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;
- 12) Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within the tolerances given in Table 4.8-2;
- 13) Verifying that the voltage and diesel speed tolerances for the accelerated sequencer permissives are 92.5 t 1% and 98 + 1%,
respectively, with a minimum time delay of 2 1 0.2 s; l
- 14) Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:
a)
Turning gear engaged, or b)
Maintenance mode; and
- 15) Operating at greater than or equal to 5600 KW but less than or equal to 5750 KW for one hour or until operating temperature has stabilized.
Within 5 minutes after completing this test, perform Specification 4.8.1.1.2g.6)b).
h.
At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting both diesel genarators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 441 rpm in less then or equal to 11 seconds; and i.
At least once per 10 years by:
1)
Oraining each fuel oil storage tank, removing the accumulated sediment and c. leaning the tank using a sodiuu hypochlorite solution or its equivalent, and 2)
Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110% of the systen design pressure.
3)
Performing tank wall thickness measurements.
The resulting data shall be evaluated and any abnormal degradation will be justified or corrected.
Any abnormal degradation will be documented in a report to the Commission.
4.8.1.1.3 Reports _ - All diesel generator failures, valid or non-valid, shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.
Reports of diesel generator failures shall include the informa-tion recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revi-sion 1, August 1977.
If the number of failures in the last 100 valid tests (on a per nuclear unit basis) is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C 3.b of Regulatory Guide 1.108, Revision 1, August 1977.
CATAWBA - UNITS 1 & 2 3/4 8-7 Amendment No. 51 (Unit 1)
Amendment No. 44 (Unit 2)
.