ML20196D703
| ML20196D703 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/07/1988 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196D706 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8812090167 | |
| Download: ML20196D703 (7) | |
Text
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UNITED STATES
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al., dated August 29, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; l
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C.
There is reasonable assurance (1) that the cctivities 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; D.
The issuance of this arendment will not be inimical to the comon defense and security or to the nealth 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 requirenents have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operaung License No. DPR-49 is hereby amended to read as follows:
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-2 (2) Technica14 pecifications The Technical Specifications contained in Appendix A, as invised through Amendment No.156, are hereby incorporated in the license. 1he itcensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendme.u is effectiva as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
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John N. Hannon, Director Project Directorate !!!-3 Division of Reactor Projects - !!I, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Decanber 7, 1988 l
ATTACHMENT TO LICENSE AMENDMENT NO. 156 FACILITY OPERATING LICENSE NO. OPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3.2-14a 3.2-15 3.2-25 3.2-453 f
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TABLE 3.2-B (Continued)
INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimun No.
cf Operable I strument Number of Channels Per Instr a nt Channels Trip System (1)
Trip Function Trip Level Setting Provided by Design Remarks 2
125 VDC System
>105 VDC 1 5% (6) 2 2 relays, 1 per bus Undervoltage Relay 1
250 VDC System
>210 VDC + 5% (6) 1 1 relay, 1 per bus Undervoltage Relay 4
1 24 VDC System
>21 VDC + 5% (6) 4 4 relays, 2 per bus F
Undervr1tage Relay m
k 1
120 VAC
>110 VAC 1 5% (6) 1 1 relay, 1 per bus Uainterruptibic AC Undervoltage Relay 2
120 VAC
>110 YAC 1 5% (6) 2 2 relays, 1 per bus Instrwent AC Undervoltage Relay E
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DAEC-1 NOTES FOR TABLE 3.2-B 1.
Whenever any CSCS subsystem is required by Subsection 3.5 to be operable, there shall be two operable trip systems.
If the first column cannot be net for one of the trip systems, that trip system snall be placed in the tripped condition or the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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2.
Close isolation valves in RCIC subsystem.
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3.
Close isolation valves in HPCI subsystem.
4 Zero referenced to tcp of active fuel.*
5.
HPCI has only one trip system for these sensors.
6.
There is no trip function associated with these relays. The relays provide signals to annunciators only, 7.
Foer undervoltage relays with integral timers per 4Kh bus. The relay output contacts are connected to form a one.out-of-two twice coincident logic matrix. With one relay inoperable, operation may proceed provided that the inoperable relay is placed in the tripped condition within one hour.
- Top of active fuel zone is defined to be 344.5 inches above vessel zero (see Bases 3.2).
3.2-15 Amendment No. J7,46,156
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TABLE 4.2-8 MINIMt#1 TEST AND CALIBRATION FREQUENCY FOR CSCS Instrtsnent Calibration Instrument I.istrirnent Channel Functional Test (9)
Frequency (9)
Check
- 1) Reaci.or Water Level (1)
Once/3 months Once/ day
- 2) Drywell Pressure (1)
Once/3 months None
- 3) Reactor Pressure (1)
Once/3 months None
- 4) Auto Sequencing Timers N/A Annual None
Once/3 months None Pressure Interlock
- 6) Trip System Bus Power tenitors (1)
Not Applicable None h
- 7) Recirculation System d/p (1)
Once/3 months Once/ day
- 8) Core Spray Sparger d/p (1)
Once/3 months Once/ day
(1)
Once/3 months None
(1)
Annual Once/ day
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Once/3 months None
- 12) 19CI Suction Source i.evels (1)
Once/3 months None E
- 13) a.
4KV Emergency Power System Annual Annual None
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Voltage Relays o
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4KV Emergency Power System Once/ month Annual None C;g Voltage Relays (Degraded Voltage) o E
Annual None
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battery bus undertoltage relays y
- 15) Low-Low Set Function (1)
Once/6 months Once/ day
DAEC-1 1
stop valves or fast closure of the turbine control valves with reactor power greater than 30% and a simultaneous failure of the turbine bypass valves to open. The operating limit MCPR of section 3.12.C is calculated assuming an operable EOC-RPT system.
If the requirements of Table 3.2-G are not met, then the reactor power level is reduced to a level (85% of raf d) which will ensure that the full-power MCPR limits of section 3.12.C wo not be violated if such a transient were to occur.
L function settings are included for Instrument AC and Uninterruptible AC at battery busses for surveillance of undervoltage relays. The undervoltage relays are required to sense a reduction in the power source voltage so that the subject instruments can be transferred to an alternate power source.
Surveillance tests cther than a monthly functional check of the bus power monitors for the RHR, Core Spray, ADS, HPCI and RCIC trip systems are not required since they serve a:. annunciators for complete loss of power and do not monitor reduction of voltage.
The subject functional check consists of openir.g the appropriate circuit breakers or removing the appropriate fuses and observing the loss of power annuncistor activation.
The accident monitoring instrumentation listed in Table 3.2-H were specif-ically added to comply with the requirments of NUREG-0737 and Generic Letter 83-36. The instrumentation listed is iesigned to provide plant status for accidents that exceed the design basi. accidents discussed in Chapter 15 of the DAEC UFSAR.
Footnote 9 of Table 3.2-H deviates from the guidance of Generic Letter 83-36 as continued operati m for 30 days (instead of 7 days as recommended in the j
generic letter) is allowed with one of two torus water level mc11 tor (TWLM) l channels inoperable. Continued operation is justifieri by the following considerations:
- 1) Redundancy is available in that at least one channel of the containment water level monitor (CWLM; instrumentation must be available. Since the CWLM envelopes the span measured by the TWLM, the torus water level can be monitored by the CWLM system.
3.2-45a Amendment No. Df, Mi, 156
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