ML17326A708
| ML17326A708 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/10/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326A709 | List: |
| References | |
| NUDOCS 8008140235 | |
| Download: ML17326A708 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMEHDMIENT TO FACILITY OPERATING LICENSE Amendment No.
22 License Ho.
DPR-74 1.
The Nuclear Regulatory Commission (the ComiIission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 22, 1980 and March 28,
- 1980, complies 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, the provisions of the Act, and the rules and regulations of the ComIission; 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 ac'tivities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the coIIriion 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. DPR-74 is hereby amended to read as follows'2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
22
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COYiilISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10, 1980 ga, h ef Operating Reacto s Branch gl Division of Licensing
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 22 TO FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO.
50-316 Revi se Appendix A as follows:
Remove Pa es 3/4 3-20a 3/4 3-25a 3/4 3-32a 3/4 8-3a Insert Pa es 3/4 3-20a 3/4 3-25a 3/4 3-32a 3/4 8-3a
TABLE 3.3-3 (Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.
OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE t)ODES ACTION 6.
MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low b.
4 kv Bus Loss of Voltage 3/Stm.
Gen.
2/Bus 2/Bus 2/Bus 2/Stm.
Gen.
any Stm.
Gen.
2/Stm.
Gen.
1,2,3 1,2,3 14*
7.
TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low 3/Stm.
Gen.
8.
LOSS OF POWER 2/Stm.
Gen.
2/Stm.
Gen.
1, 2, 3
any 2 Stm.
Gen.
)4*
a.
4 kv Bus Loss of Voltage b.
4 kv Bus Degraded Voltage 3/Bus 3/Bus 2/Bus 2/Bus 2/Bus 2/Bus 1,2,3,4 1, 2, 3, 4
14*
14*
O
TABLE 3.3-4 (Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOIHTS FUNCTIONAL UNIT TRIP SETPOIHT ALLOWABLE VALUES.
6.
MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low b.
4 kv Bus Loss of Voltage 7.
TURBINE DRIVEN AUXILIARYFEEDWATER PUMPS a.
Steam Generator Water Level -- Low-Low-8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage 4 kv Bus Degraded Voltage
> 10K of narrow range instrument span each steam generator 3196 volts with a 2-second delay
> 10K of narrow range instrument span each steam generator 3196 volts with a 2-second delay 3196 volts with a 2.0 min. time delay
> 9X of narrow range instrument span each steam generator 3196+18 volts with a 3+ ~ 2 second delay
> 9X of narrow range instrument span each steam generator 3196+18 volts with a 2+.2 second delay 3196+18 volts with a 2.0 minute + 6 second time delay
TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREHENTS FUNCTIONAL UNIT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE RE UIRED 7.
TURBINE DRIVEN AUXILIARY FEEDMATER PUMPS a.
Steam Generator Water Level--Low-Low.
8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage 4 kv Bus Degraded Voltage R
1,2,3 1, 2, 3, 4
1, 2, 3, 4
ELECTRICAL POWER SYSTEMS
'URVEILLANCE RE UIREMENTS Continued b)
Verifying the 'diesel starts from ambient condition on the auto-start signal,'energizes the emergency busses with permanently connected
- loads, energizes the auto-connected shutdown loads through the load sequencer and operates for 5 minutes while its generator is load'ed with the shutdown loads.
6.
Verifying that on an ESF actuation test 'signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for 5
minutes.
7.
Veri fying that on a simulated loss of the diesel gener-ator (with offsite power not available),
the. loads are shed from the emergency busses and that subsequent loading of the diesel generator is in accordance with design requirements.
8.
Simulating a loss of offsite power in conjunction with an ESF actuation tes't signal, and a)
Verifying de-energization of the emergency busses and load shedding from the emergency busses.
b)
Verifying the diesel starts from ambient condition on the auto-start
- signal, energizes the emergency busses with permanently connected
- loads, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for 5 minutes while its generator is loaded with the emergency loads..
c)
Verifying that on diesel generator trip, the loads are shed from the emergency buses and the diesel re-starts on the auto-start signal following manual resetting of the diesel trip lockout relay, the emergency buses are energized with permanently connected
- loads, the auto-connected emergency loads are energized through the load sequencer and the diesel operates for >5 minutes while its generator is loaded with emergency loads.
d) Verifying that all diesel generator trip's, except engine overspeed and generator differential, are automatically bypassed upon loss of voltage on the emergency bus and/or safety injection actuation signal.
9.
Verifying the diesel generator operates for at 1'east 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 3850 kw and 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 3500 kw.
Within 5 minutes after com-pleting this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, repeat Specification 4.8.1.1.2.c.5.
D.
C.
COOK - UNIT 2 3/4 8-3a Amondnont No. 22, Unit 2