ML20116H228
| ML20116H228 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/18/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116H217 | List: |
| References | |
| NUDOCS 8505020135 | |
| Download: ML20116H228 (3) | |
Text
',
UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 5
- j WASHING TON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 118 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 1.0 Introduction By a letter dated December 7,1984, the Iowa Electric Light and Power Company (the licensee /IELP) proposed to change the Technical Specifications for the Duane Arnold Energy Center (DAEC) to permit loading of the General Electric Company's (GE) advanced fuel Lead Test Assemblies (LTAs).in the DAEC core.
In support of its application, the licensee submitted a supplemental reload submittal (Reference 1).
The licensee has agreed to participate in GE's advanced fuel development program by accepting five LTAs for use in DAEC beginning with Cycle 8 operation. The design of the LTAs and the demonstration of their conformance to all applicable thermal-mechanical performance criteria are documented in the GE report, " Generic Licensing of 1984 Lead Test Assemblies (Special Report MFN-068-84)." The NRC staff's conditional acceptance of the GE report is documented in our Safety Evaluation Report,
" Acceptance of Referencing of Licensing Special Report MFN-068-84, Lead Test Assembly Licensing."
2.0 Evaluation The licensee wishes to insert five Lead Test Assemblies into the Cycle 8 Four would be located near the center of the core in quadrant-core.
symmetric sets and the fifth near the core boundary. These assemblies, called GE.1984 Lead Test Assemblies, are described in Reference 2.
Approval of tiieir use in BWRs is given in Reference 3.
That approval was subject to three conditions:
1.
The 1984 Lead Test Assemblies will not be the most limiting fuel assemblies in the core at any time during their residence.
2.
The user of these LTAs must verify that the fuel design criteria and Specified Acceptable Fuel Design Limits (SAFDLs) are met for the assemblies in whatever reactor is chosen for their irradiation.
3.
The user of the LTAs must supply the results of the transient and accident analyses for the assemblies and modify the plant Technical Specifications as necessary to reflect their use.
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ADOCK 05000331 PDR
Reference 1 provides revisions to the Cycle 8 reload licensing submittal to take into account the presence of the LTAs. The licensee confirms that the LTAs are not limiting in Cycle 8 and commits to verification that they will not be limiting in future cycles. We conclude that this complies with condition 1 above and is acceptable.
The transients and accidents have been examined to determine the effect of the LTAs on their consequences. Maximum Average Planar Linear Heat Generation Rate (MAPLHGP.) limits for the LTAs have been established by analysis of the Loss-of-Coolant Accident (LOCA) event by approsed methods assuming a linear heat generation rate of 14.4 kw/ft for the LTA fuel. The LTAs do not affect the rod drop event. The transients have been analyzed to assure that SAFDLs are not violated for the LTA fuel during these events. An exception is the fuel misloading (misorientation) event.
Special surveillance will be performed during loading of these assemblies in order to preclude this event. Since there are only five of these assemblies, we conclude that this is acceptable. We also conclude that this meets condition 2 above.
The licensee has supplied the results of transient and accident analyses, and supplied the Technical Specification revisions to accomodate the presence of the LTAs in the core. The proposed revisions satisfy the staff's acceptance condition 3, are consistent with results of the analyses, and are acceptable.
We conclude that the use of five Lead Test Assemblies, as described in Reference 2, is acceptable for Cycle 8 of DAEC.
3.0 Environmental Considerations This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
l 4.0 Conclusion We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such i
s 3-activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inirJeal to the common defense and security or to the health and safety of the public.
5.0 References 1.
Supplemental Reload Licensing Submittal for Duane Arnold At >mic Energy Center, Unit 1 Reload 7, General Electric Report 23A1739, Revision 1, December 1984.
2.
Letter, J. S. Charnley (GE) to C. O. Thomas (NRC), Generic 4.icensing of 1984 Lead Test Assemblies (Special Report MFN-068-84), June 4, 1984.
3.
Letter, C. O. Thomas (NRC) to J. S. Charnley (GE), Acceptar:e for Licensing, October 9, 1984, Referencing of Licensing Special Repo Principal Contributor:
W. Brooks s
Dated: April 18,1985 I
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