ML20096D919
| ML20096D919 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/22/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20096D921 | List: |
| References | |
| DPR-49-A-104, TASK-2.B.3, TASK-TM NUDOCS 8409060352 | |
| Download: ML20096D919 (5) | |
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- - dt NUCLEAR REGULATORY COMMISSION I
, M,. y WASHINGTON, D. C. 20555 Q
i 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. 104 License No. OPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated January 27, 1984, 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 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 with the Commission's regulations; 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.
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.
e DPR-49 is hereby amended to read as follows:
Wh?O P
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, are hereby incorporated in the license. The licensee shall operate the facility in accordance With the Technical Specifications.
- 3.
The license amendment-is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-- } '} { & a 3:
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 22, 1984 f
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ATTACHMENT TO LICENSE AMENDMENT N0. 104 FACILITY OPERATING LICENSE N0. DPR-49 DOCKET N0. 50-331 Revise the Appendix "A" Technical Specifications by removing the current pages and inserting the revised pages listed below. The revised areas are identified by vertical lines.
LIST OF AFFECTED PAGES 3.2-23b 3.2-34a
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meets NOTES FOR TABLE 3.2-H NOTES FOR TABLE 3.2-H
,,W (1)
Each channel is comprised of three instruments (pressure switches) which are arranged in a "two out _of three" logic connected to a relay.
l (2) From and after the date that a channel is inoperable, the torus temperature will be monitored at least once oer shift to observe any unexplained temperature increase which might be indicative of an open SRV; continued reactor operation is permissible only during the succeeding 30 days, unless such channel is sooner made operable.
(3) When the ability to obtain a sample has been lost:
- a. Within 7 days confirm a samole can be obtained within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the time a decision is made to sampit; and
- b. W' ithin 90 days, restore the sampling capability.
- c. If the requirements of notes 3 (a) and 3 b) cannot be met, be in at f
s least a HOT SHUTDOWN Condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (4) When the ability to analyze a sample has been lost:
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- a. Within 7 days, confirm tJiat alternative sample analytical succort-services can be initiated within 24 hoars of the ' time a decision is made to sample:
and
- b. Within 90 days, restore sample knalysis capability,
- c. If the recuirements of notes 4(a) and 4(b) cannot be met, be in at least a HDT SHU(DOWN Condition within the next '?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(5) With the' number of operable ci.annels (both indicator and recorder inoperable) less than the Minimum Channels Operable Recuirement,.
initiate the preplanned alternate method of monitoring the acprocriate carameter(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- a. either restore the inoperable channel (s) to operable status within seven (7) _ days following the event, or
- b. prepare and submit a Special Report i:o the Cournission within 14 days following the event describing the action taken, the cause of the inoperability and the plans and schedule for restorino the system to-operable status.
Amendment No.,1FI, 104 t
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i l AlllE 4.2-11 ACCillENI HfNili(NilHG INSIRUMENIATION SURVEILLANCE REf]UIREMENIS i ns t ru..icn t Calibration Frequency
_ Instrument Check ('2)
Safety / Relief Valve Position Indicator (Primary) (1)(2)
Once/olerating cycle
-Once/ month i
t Safety / Relief Valve Position ludicator (Backup-Thermocouple)
Once/ operating cycle Once/ month
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Safety Valve Position Indicator (Primary) (t)(2)
Once/ operating cycle Once/ month Safety Valve Position Indicator (Backup-Iliermoccuple)
Once/ operating cycle Once/ month Extended Range Effluent Radiation Monitors:
a) Reactor Rullding Exhaust Stacks Once/ operating cycle (3)
Once/ week
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b) Turbine Building Exhaust Stack Once/ operating cycle (3)
Once/ week c) OfIgas Stack Once/ operating cycle (3)
Onep/ week w
Reactor Coolant, Containment Atmosphere, and Torus Water Post-Accident Sampling Once/ operating cycle (4).
N/A N
h.
HOIES FOR TABLE 4.2-H Functional test of the relay is done once/3 months.
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1.
4 Instrument check shall consist of the qualitative assessee.:t of channel behavior during 2.
observation.
Ihls determination sliall luclude where possible. comparison of the channe Indi peration by j
status with other indications and/or status de ived from indepe,ndent instrument channels (e..g. cation and j
thermocouple) measuring the same parameter.
backup 3.
Accident range effluent monitors shall be calibrated by means of a built-in check source or a known j
radioactive source.
4.
Not a calibration, but demonstration of systen operabil1ty.
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