ML19249D552
| ML19249D552 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/04/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19249D553 | List: |
| References | |
| NUDOCS 7909240827 | |
| Download: ML19249D552 (8) | |
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UNITED STATES
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NUCLEAR REGULATORY COMT-V.JN w
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p IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA F0WER C00FERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-3H i
DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, Cent'ral Iowa Power Cooperative, and Corn Belt Power Coooerative (the licensee) dated December 27, 1978, v supple-mented May 23, 1979, August 15, 1979 and August 17, 1979, 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 conformi c with the application, the.
nrovisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized oy 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 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 Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
homa
. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 4, 1979 9
ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix "A" Technical Spec'ifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines, indicating the area of change.
Remove Replace 3.3-6 3.3-6 3.3-17 3.3-17 3.3-18 3.3-18 3.3-19/3.3-20 3.3/19 3.3.21/ 3.3-2?
3.3-23 3.12-9a 3.12-9a i
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS C.
Scram Insertion Times C.
Scram Insertion Times 1.
The average scram insertion time, 1.
After each refueling outage based on the de-energization of all operable rods shall be the scram pilot valve at time scram time tested from the zero, of all operable control fully withdrawn position with rods in the reactor power opera-the Nelear system pressure tion condition shall be no above 950 psig (with saturation greater than:
temperature) and the requirements of Specification 3.3.B.3a met.
This testing shall be completed prior to exceeding 40% power.
Average Scram Below 301 power, only rods in Rod Insertion those seque4ces (Al2 and A34 or B12 Position Times (Sec) and 834) which tre fully withdrawn in the region from 100% rod 46 0.361 density shsll be scram time tested.
36 0.917 During all scram time testing 26 1.479 below 30". power, the Rod Worth 06 2.693 Minimizer shall be operable or a second licensed oparator shall 2.
The average scram insertion times verify that the operator at the for the three fastest control reactor console is following the rods of all groups of four con-control r?d pograio, trol rods in a 2 x 2 array shall be no greater than:
2.
Near the sted of cycle, all operable
~
rods shall be scram time tested from Average Scram the fully' withdraca position with Rod Insertion the nuclear system pressure above Position Times (Sec) 950 psig (witn saturation temper-ature) and the requirements of 46 0.383 specification 3.3.b.3a met.
36 0.972 h
3.
The data from the testing specified in section 4.3.C.2 shall be compared to the data from the testing required 3.
Maximum scram insertion time for in section 4.3.C.1 to verify that 90% insertion of any operable n trend of degradation exists. A control rod should not exceed 7.00 report of this evaluation shall be
- seconds, submitted to the NRC within 90 days of testing.
g99 Surveillance Requirements 4.3.C.2 and 4.3.C.3 shall be deleted upon
.3-6 Amendment No. 54 completion of Cycin 6.
DAEC-1 bypassed from the console for maintenance and/or testing.
Tripping of one of the channels will block erroneous rod withdrawal soon enough to prevent fuel damage.
This system backs up the operator who withdraws control rods according to written sequences. The specified restrictions with one channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists.
A limiting control rod pattern is a pattern which results in the core being on a thermal hydraulic limit.
During use of such patterns, it is judged that testing of the RBM system prior to withdrawal of such rods to assure its operability will assure that improper withdrawal does not occur.
It is the responsibility of the Reactor Engineer to identify these limiting patterns and the designated rods either wt.en the patterns are initially established or as they develop due to the occurrence of inoperable control rods in other than limiting patterns.
Other personnel qualified to perform this function may be designated by the DAEC Chief Engineer.
3.
Scram Insertion Times The control rod system is designed to bring the reactor subcritical at a rate fast enought to prevent fuel damage; i.e., to prevent the MCPR from becoming less than the safety limit.
3.3-17 Amendment No. 54 g99
DAEC-1 After initial fuel loading and subsequent refuelings when operating above 950 psig, all control rods shall be scram tested within the constraints imposed by the Technical 3pecifications and before the 40% power level is reached.
This testing shall also be conducted near the end of cycle (through Cycle 6) to confirm non-degradation of scram times over a fuel cycle. The requirements for the various scram time measurements ensure that any indication of systematic problems with rod drives will be investigated on a timely basis.
l 4.
Reactivity Anomalies During each fuel cycle excess operative reactivity varies as fuel depletes and as any burnable poison in supplementary control is burned. The magnitude of this excess reactivity may be inferred from the cirtical rod configuration.
As fuel burnup progresses, anomalous behavior in the excess reactivity may be detected by comparison of the critical rod pattern at selected base states to the predicted rod inventory at that state.
Power operating base conditions proi1'fe the most sensitive and directly interpretable data relative to core reacti v' ty.
Futhermore using power operating base conditions pennits frequent reactivity comparisons.
Requiring a reactivity comparison at the specified fraquency assures that a comparison will be made before the core reactivity change exceed 1% 4 k.
Deviations in core reactivity greater than 1% 4 k are not expected and require thorough evaluation.
One percent reactivity limit is considered safe since an insertion of the reactivity into the core would not lead to transients ex-ceeding design conditions of the reactor system.
3.3-18 Amendment No. 54
3,3, 4.3 References 1.) NEDO 24087-3, 78NED265, Class 1 Jt:1e 1978 " General Electric Boiling Water Reactor Reload 3 (Cycle 4) Licensing Amendment For Duane Arnold Energy Center, Supplement 3: Application of Measured Scram Times" Amendment No.
54 3.3-19 lb 999
TABLE 3.12-2 MCPR LIMITS Fuel Type 7x7 1.22 8x8 1.26 3.12-9a Amendment No. 54
.