ML18054A628
| ML18054A628 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/03/1989 |
| From: | Smedley R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18054A630 | List: |
| References | |
| TAC-59970, NUDOCS 8904120229 | |
| Download: ML18054A628 (2) | |
Text
consumers Power PDWERINli MICHlliAN~S PROliRESS General Offices: 1945 West Parnall Road, Jackson,* Ml 49201 * (517) 788-0550 April 3, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
COMPLIANCE WITH PRESSURIZED THERMAL SHOCK RULE 10CFR50.61 AND REGULATORY GUIDE 1.99 REVISION 2 -
FLUENCE REDUCTION STATUS(TAC NO. 59970)
Consumers Power Company submittal dated November 30, 1988 provided a preliminary report on reactor vessel fluence for Cycles 1-8.
Attached is the revised Cycle 8 fluence reduction report describing the effect of incorporating low-leakage fuel management and partial stainless steel.
shielding assemblies on the pressure vessel inner wall fast flux (E>l.O MeV) levels relative to previous high neutron leakage fuel management.
This revised report reflects results that incorporate corrections to the input neutron source file and to the moderator densities used in the neutron transport calculations.
The neutron source file corrections were discussed in our November 30, 1988 submittal.
The error involving moderator densities was only recently discovered and is discussed herein.
The revised report concludes that the PTS screening criteria will be exceeded at the axial welds in early 2002, as opposed to the previously estimated exceed date of 1999 as specified in our November 30, 1988 submittal.
- Thus, the conclusion that the flux reduction achieved in the Cycle 8 core loading pattern is, by itself, insufficient to allow plant operation to the current expected end of life in 2011 is still valid.
Further measures, eg, greater flux reduction, Regulatory Guide 1.154 analysis," etc, must be pursued to allow plant operation to the nominal end of plant life or beyond.
Consistent with our November 30, 1988 submittal, our current plans at this time are to complete a Cycle 9 and beyond vessel f luence analysis for submittal to the NRC by August 1, 1989.
It should be noted, however, that the current mode of operation in Cycle 8 (ie, extended reduced power operation) with the possibility of steam generator replacement at the end of Cycle 8 is OC0389-0107-NL04 A CA/IS ENERGY COMPANY
Nuclear Regulatory Commission Palisades Plant Pressurized Thermal Shock Rule April 3, 1989 2
instigating reevaluation of fuel management plans for Cycle 9, for which a substantial amount of fuel management analyses has been performed.
In the event that Cycle 9 fuel management strategies are substantially revised, the submittal of the Cycle 9 to end of life vessel fluence report will most likely need to be rescheduled.
~~~
Richard W Smedley Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC0389-0107-NL04