ML17285A364
| ML17285A364 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/30/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285A365 | List: |
| References | |
| NUDOCS 8904120417 | |
| Download: ML17285A364 (9) | |
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UNITED STATES NUCLE~MREGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT.NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Comnission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the licensee),
dated December 2, 1988 as supplemented by letter dated February 1,
1989 corrplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility wi 11 operate in conformity with the application, the provisions of the Act, and the 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 vrill be conducted in compliance with the Commissior.'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 Fart 51 of the Commission's regulations and all applicable requirements have been satisfied.
8904i204i7 890330 PDR AOOCK 05000397 P
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xf. 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-21 is hereby amended to read as follows:
(2)
Technical S ecifications and Envirormental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
66, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULA ORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 30, 1989 eorge
. Knighton, irector Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
ENCLOSURE TO LICENSE AMENDMENT HO.
66 FACILITY OPERATING LICENSE NO NPF-21 DOCKET NO. 50-397 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.
Also to be replaced are the following overleaf pages.
AMENDMENT PAGE 3/4 8-6 OVERLEAF PAGE 3/4 8-5
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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.
, Simulating a'oss-of-offsite power'by itself, and:
a)
For divisions 1 and 2:
5 ~
6.
1)
Verifying deenergization of the emergency busses and load shedding from the emergency busses.
2)
Verifying the diesel generator. starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the autoconnected
'shutdown -loads through the load sequencer and operates for greater than or
. equal to 5 minutes while its generator is loaded with the shutdown loads.
After energization, the steady state voltage ahd frequency of the emergency busses shall be maintained at 4160 f 420 volts and,60
+
3.0 Hz during this test.
b)
For division 3:
1)
Verifying deenergization of the emergency bus.
2)
Verifying the diesel generator starts on the auto-start
- signal, energizes the emergency bus with the perma-nently connected loads within 13 seconds and operates for. greater than. or equal to 5 minutes while its gen-erator is loaded with the shutdown. loads.
After ener-
- gization, the steady-state voltage and frequency of the emergency bus shall be maintained at 4160
+ 420 volts and 60. a, 3. 0 Hz during this test.
Verifying that on an ECCS actuation test signal, without loss-of-offsite 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 4160
(+420, -250) volts for DG-1 and OG-2, 4160 2 420 volts for DG-3 and 60
+ 3.0 Hz within 10 seconds'or DG-1 and OG-2 and 13 sec-onds for DG-3 after the auto-start signal; the steady-state generator voltage and frequency shall be maintained within 4160 f 420 volts and the above frequency limit during this test.
I Simulating a loss-of-offsite power in conjunction with an ECCS actuation test signal, and:
a)
For divisions 1 and 2':
1)
Verifying deenergization of the emergency busses and loads shedding from the emergency busses.
2)
Verifying the diesel generator starts on the auto-start
- signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected loads through the load sequencer and operates WASHINGTON NUCLEAR - UNIT 2 3/4 8-5 Amendment No.
19
A
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ELECTRICAL POWER SYSTEMS
'URVEILLANCE RE UIREMENTS (Continued 7.
8.
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 + 3. 0 Hz during this test.
b)
For division 3:
1)
Verifying deenergization of the emergency bus.
2)
Verifying the diesel generator starts on the auto'-start
- signal, energizes the emergency bus with the permanently connected loads and the auto-connected emergency loads within 30 seconds and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.
After energization, the stea'dy state voltage and frequency of the emergency bus shall be maintained at 4160 + 420 volts and 60 + 3.0 Hz.
during this test.
Verifying 'that al,l automatic diesel generator division 1, 2, and 3 trips are automatically bypassed upon an ECCS actuation signal except engine overspeed, generator differential current, incomplete starting sequence and emergency manual stop.
Verifying the diesel generator oper ates 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 shall be loaded to greater than or equal to 4650 kW for DG-1 and DG-2 and 2850 kM for DG-3.
During the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to'4400 kM for DG-1 and DG-2 and 2600 kW for DG-3.
The generator voltage and frequency shall be 4160 (+420, -250) volts for DG-1 and DG-2, 4160
+ 420 volts for DG-3 'and 60 + 3.0 Hz within 10 seconds for DG-1 and DG-2 and 13 seconds for DG-3 after the start signal;"
the steady-state generator voltage and frequency shall be main-tained within 4160 + 420 volts and the above'requency limit during this test.
Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement
- 4. 8. l. 1. 2. e. 4. a)2) and b)2). "
Surveys ance Requirements
- 4. 8. 1. l. 2. e. 4. a)2) and/or b)2) are not satis-factorily completed, it is not necessary to repeat the preceding 24-hour test.
- Instead, the diesel generator may be operated at 4400 kW for DG-1 or DG-2 or 2600 kM for DG-3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or until operating temperature has stabilized.
MASHINGTON NUCLEAR - UNIT 2 3/4 8-6 Amendment No.