ML18052A413
| ML18052A413 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/05/1986 |
| From: | Kuemin J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8605080249 | |
| Download: ML18052A413 (2) | |
Text
consumers Power POW ERi Nii MICHlliAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 May 5, 1986
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
GENERIC LETTER 83 SALEM ATWS EVENT -
ITEM 1.2 -
CONTROL ROD POSITION Consumers Power Company letter of July 1, 1985, provided our response to Item 1.2 of Generic Letter 83-28.
The NRC has indicated, in a letter dated April 1, 1986, that there is no indication of data collection or recording of control rod positions in our response.
The NRC letter requested a discussion of the capabilities existing or planned for retrieving* data on control rod positions following a reactor trip.
It is our intention to upgrade the data collection of control rod drive positions following a reactor trip by the end of the 1987 refueling outage.
The present capabilities of the control rod drive position indication equip-ment will not provide the recording of all CRD positions following reactor trip.
Indication, however, is displayed in the control room, and immediate operator action specified in the Emergency Operating Procedures following trip is to ensure that the control rods are fully inserted as well as ensuring reactor power is decreasing.
Control rods, other.than partial length rods, which have not fully inserted on a reactor trip, would be noted in the appro-priate log book.
Investigation of the cause of rods not inserting on a trip signal would be accomplished in the post trip review, but would also be dependent upon the operator action to note the deviation.
Our understanding is that the NRC does not consider this reliance on manual operator action desirable with regard to post trip review and anticipated transients without scram (ATWS).
The present capabilities to record rod position following reactor trip are provided by both the Plant Information Processor (PIP) and the Secondary
- Position Indication (SPI) data processors which operate independently and simultaneously.
These data processors have limited memories and limited printer output buffers which, upon reactor trip, become filled and are unable to record all the post trip rod positions.
The modifications that we intend to perform will provide the capability to record positions of all full length control rods following reactor trip.
OC0486-0080-NL02
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A description of the present contr~l rod drive position ind.ication capabili-ties is found in Section 7.6.2.3 of the updated FSAR *.
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James L Kuemin Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades OC0486-0080-NL02