ML20217D350
| ML20217D350 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  (NPF-87-A-058, NPF-87-A-58, NPF-89-A-044, NPF-89-A-44) |
| Issue date: | 04/20/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217D356 | List: |
| References | |
| NUDOCS 9804240285 | |
| Download: ML20217D350 (7) | |
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30eeH001
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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 l
1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 58 License No. NPF-87 1.
The Nuclear Regulatory Commission (the Commissior.) has found that:
l A.
The application for amendment by Texas Utilities Electric Company (TU Electric, j
the licensee) dated February 25,1998, (TXX-98050) as supplemented by letter dated March 9,1998, (TXX-98066) for License Amendment Request (LAR)98-002; and subsequent applications dated March 12,1998, (TXX-98076) for LAR 98-003; and March 18,1998, (TXX-98079) for LAR 98-004, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the l
Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 l
public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
T'ee issuance of this license 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.
2.
Accordingly, the license is amended by 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-87 is hereby amended to read as follows:
l 9804240205 980420 PDR ADOCK 05000445 P
PDP
l Mr. C. Lance Tony t 2.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
58. and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
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Timothy J. Pelich, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of issuance: April 20, 1998 l
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t UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30616 0001
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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50446 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 44 License No. NPF-89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated February 25,1998, (TXX-98050) as supplemented by letter dated March 9,1998, (TXX-98066) for License Amendment Request (LAR)98-002; and subsequent applications dated March 12,1998, (TXX-98076) for LAR i
98-003, and March 18,1998, (TXX-98079) for LAR 98-004, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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; D.
The issuance of this license 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.
2.
Accordingly, the license is amended by 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-89 is hereby amended to read as follows:
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l Mr. C. Lance Tony
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l (2)
Technical Soecdications and Environmental Protection Plan The Technical Speedications contained in Appendix A, as revised through Amendment No.
44, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TU Electric 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 Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 20, 1998 4
I ATTACHMENT TO LICENSE AMENDMENT NOS. 58 AND 44 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 l
Replace the following pages of the Appendix A Technical SpeCfications with the attached pages.
The revised pages are identified by Amendment number and contain marginal lines indicating the l
areas of change. The corresponding ovedeaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 8-6 3/4 8-6 l
1 l
l l
l l
ELFCTRICAL POWER SYSTEMS SURVEILL ANCE REQUIREMENTS (Continued) 4)
Simulating a loss-of-offsite power by itself, and:
a)
Verifying deenergization of the emergency busses and load shedding *"
from the emergency busses *, and b)
Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected shut-down loads through the load sequencer" and operates for greater than or equal to 5 minutes while its l
generator is loaded with the shutdown loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 6900 690 volts and 60 1.2 Hz during this test.
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l 5)
Verifying that on a Safety injection Actuation test signal, without loss-of-offsite l
power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 6900 690 volts and 60 1.2 Hz within 10 seconds after the auto-start signal; the steady-state generator voltage and frequency shall be maintained within these limits during this test; l
6)
Simulating a loss-of-offsite power in conjunction with a Safety Injection Actuation test signal, and:
a)
Verifying deenergization of the emergency busses and load shedding"*
from the emergency busses;*
l b)
Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer" l
and operates for greater than or equal to 5 minutes while its generator is
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loaded with the emergency loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 6900 690 volts and 60 1.2 Hz during this test; and c)
Verifying that all automatic diesel generator trips, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety injection Actuation signal.
l 7)
Verifying 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 />. During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator
- The testing of the load shedding feature of MCC XEB4 3 for Unit 2 is not required until the startup subsequent to 2RFO4 or the next Unit 2 outage greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in duration. " On a one-time l
basis, the verification of the auto connected shut-down loads through the load sequencer may be performed at power for fuel cycle 6 on Unit 1 and fuel cycle 4 on Unit 2. *" On a one-time basis, the verification that load shedding occurs as a result of the deanergization of the emergency busses may be performed at power for fuel cycle 6 on Unit 1 and fuel cycle 4 on Unit 2.
COMANCHE PEAK - UNITS 1 AND 2 3/4 8-6 Unit 1 - A'mendment No. 58 Unit 2 - Amendment No. 44
ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) a)
An API Gravity of within 0.3 degrees at 60*F, or a speci-fic gravity of within 0.0016 at 60/60*F, when compared to the supplier's certificate, or an absolute specific gra-vity at 60/60*F of greater than or equal to 0.8348 but less than or equal to 0.8984, or an API gravity of greater than or equal to 26 degrees but less than or equal to 38 degrees; b)
A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes (alternatively Saybolt viscosity, SUS at 100*F of greater than or equal to 32.6, but less than or equal to 40.1), if gravity was not determined by comparison with the sup-plier's certification; c)
A flash point equal to or greater than 125"F; d)
Either a clear and bright appearance with proper color when tested in accordance with ASTM-D4176-1982 or a water and sediment content of less than or equal to 0.05% volume when tested in accordance with ASTM-D1796-1968; 2)
By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM-D975-1981 are met when tested in accordance with ASTM-D975-1981 except that the analysis for sulfur may be performed in accordance with ASTM-D1552-1979 or ASTM-D2622-1982.
e.
At least once every 31 days by obtaining a sample of fuel oil in accordance with ASTM-D2276-1978, and verifying that total particu-late contamination is less than 10 mg/ liter when checked in accor-dance with ASTM-D2276-1978, Method A; f.
At least once per 18 months *, during shutdown, by**:
l 1)
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service; 2)
Verifying the generator capability to reject a load of greater than or equal to 783 kW while maintaining voltage at 6900 t 690 volts and frequency at 60 1 6.75 Hz; 3)
Verifying the generator capability to reject a load of 7000 kW without tripping.
The generator voltage shall not exceed 8280 volts during and following the load rejection;
- The surveillance test interval is extended to 24 months for Train A, Unit 2, to remain in effect until the completion of the second refueling outage for Unit 2.
- For any start of a diesel, the diesel must be operated with a load in l
accordance with the manufacturer's recommendations.
All planned diesel engine starts for the purpose of this surveillance may be preceded by a prelube period in accordance with vendor recommendations.
C06NCHEPEAK-UNITS 1&2 3/4 8-5 Unit 1 - Amendment No. MrE4,31
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Unit 2 - Amendment No. M,17 j
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