ML18053A407
| ML18053A407 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/10/1988 |
| From: | Kuemin J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.05, TASK-TM GL-86-06, GL-86-6, TAC-49700, NUDOCS 8806160016 | |
| Download: ML18053A407 (2) | |
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consumers Power POW ERi Nii lllllCHlliAN'S PROliRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 June 10, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
NUREG-0737, ITEM II.K.3.5 - REACTOR COOLANT PUMP TRIP (TAC NO. 49700) DELAY REQUEST The NRC letter, dated April 15, 1988, requested additional information to be submitted within 60 days of receipt of the letter, concerning Consumers Power Company's May 29, 1987 response to Generic Letter 86-06 on parameter setpoints and instrument uncertainties for Primary Coolant Pump Trip Two - Leave Two strategy.
Due to other work loads, the response to the April 15, 1988 letter is incomplete at this time.
We request delay of our submittal until on or before October 14, 1988.
Since our May 29, 1987 submittal, the wide range pressurizer pressure transmitters used for PCS pressure have been replaced with Rosemount model 1154 transmitters.
They were formerly Rosemount model 1153D.
The 1154 model has a reduced range and thereby reduces the uncertainties associated with it.
The preliminary PCS pressure uncertainties provided in the May 29, 1987 letter were associated with the 1153D model.
We have completed a final in-house analysis of the uncertainties associated with the PCS pressure 1153D model and steam generator pressure instruments.
They are as follows:
Normal Accident* (1)
Accident (2)
(1) Trip fi-rst two PCPs PCS Pressure 60 psi 87 psi 123 psi Steam Generator Pressure 22 psi 66 psi (2) Trip second two-PCPs The above uncertainties for the PCS Pressure instruments, Rosemount model 1153D, are determined to be conservative in comparison to the model 1154 instruments which are essentially equ-ivalent except for the reduced range which reduces the uncertainty.
A comparison of these final results with the preliminary CEOG funded effort to establish methodology for instrument OC0688-0038-NL04
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Nuclear Regulatory Commission Palisades Plant NUREG-0737 Item II.K.3.5 June 10, 1988 uncertainties also shows the uncertainty values to be conservatively calculated.
We intend to further review this evaluation prior to our requested October 14, 1988 completion date.
A complete response will be submitted at that time.
~K:r Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades OC0688-0038-NL04 2