ML20073K394
| ML20073K394 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/01/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073K389 | List: |
| References | |
| NUDOCS 8304200216 | |
| Download: ML20073K394 (2) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION r.
j-wAsMsworow, o. c. rosss
,,,,s SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.86 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER 1.0 Introduction By letter dated December 13, 1982 Iowa Electric Light and Power Company (the licensee) forwarded a proposed Technical Specification change that establishes revised vessel level setpoints that are consistent with a new common in-strument zero level. The proposed common reference level is 344.5" above vessel zero.
Establishment of the common zero level for all reactor vessel level instrumentation is addressed in TMI Action Item II.K.3.27 in NUREG-0737, 2.0 Evaluation Different reference points of the various reactor vessel water level in-i strument may cause operator confusion.
Therefore, all level instruments should be referenced to the same point. The licensee defines this common re-ference level as the absolute level (inches above vessel zero) of the trip settings; the " top of active fuel" has been defined to be 344.5 inches above vessel zero.
We have reviewed each of the proposed revised setpoints and find them to be consistent with the previously established safety settings. However, we re-quire and the licensee has committed by its letter dated February 3,1983, that all operators will be trained on the new level setpoints by the completion of the refueling outage commencing February 1983. The required changes to
. procedures and Technical Specifications will be entered prior to operating l
with the new setpoints installed.
Since no changes in actual water level for any function is involved in the proposed Technical Specification revisions, and no instrumentation is being changed, and since the proposed Technical Specification reviesions conform,to j
the guidelines of Item II.K.3.27 of NUREG-0737 we find the revisions accep' table.
3.0 Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in 8304200216 830401 PDR ADOCK 05000331 P
any significant environmental impact." Having made this determination, we have further concluded that the amendment involves an action which is in-significant from the standpoint of environmental impact and pursuant to 10 CFR Section Sl.5(d)(4) that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 Conclusion We have concluded, based on the considerations discust'> above, that: (1)because the amendment does not involve a significant increase tu the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a safety margin, the amendment does not involve a significant hazards consideration (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: April 1,1983 Principal Contributor: Frank 1. Apicella
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