ML18051B238

From kanterella
Jump to navigation Jump to search
Provides Addl & Clarifying Info to Support Util 841005 & 1130 Requests for Extension of Outage from Mar-Nov 1985 for Replacement of Environ Qualification Equipment
ML18051B238
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/15/1985
From: Johnson B
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Office of Nuclear Reactor Regulation
References
EEQ-85-01-NL02, EEQ-85-1-NL2, NUDOCS 8501180287
Download: ML18051B238 (4)


Text

  • ~. -..

consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 *.{517) 71;18-0550 January 15, 1985

Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR
  • PALISADES PLANT

~ EQ REPLACEMENT SCHEDULE ADDITIONAL INFORMATION Consumers Power Company submittal dated November 30, 1984 identified the Justification for Continued Operation (JCO's) for EQ equipment being replaced in an outage to start no later than November 30, 1985.

Based on discussions with the NRC staff, additional and clarifying information is required in order to fully support the request for extention of the outage from March 1985 to November 1985.

These items of information provided here, tie together and correct information given in our submittals dated November 30, 1984 and October 5, 1984.

The following table identifies the equipment to be installed by type, number of pieces, identifying number and JCO:

Type Position I~dication Equipment To Be Installed Number 2

Identifying Number POS 3027B.3056B (POS-3018,3036,3037 3059) will be installed before March 1985 and are therefore, not included.

(

I I

8501180287 850115 *rn:

1' PDR ADOCK 05000255 ; I P

PDR *,,

t_._-f.

EEQ-85-0l-NL02 JCO J-48 Pos-16

Director, NRR EQ Replacement Schedule January 15, 1985 Type Position Indication Transmitter (Level)

Transmitter (Level)

Transmitter (Level)

Transmitter (Pressure)

Transmitter (Pressure)

Radiation Elements Temperature Elements Equipment To Be Installed (Continued)

Number 11 8

1 4

1 8

4 22 Identifying Number-POS-2117,2113,2115 0861,0862,0864, 0865,0867,0869, 0870, 0873 LT-0751A,B,C,D LT-0752A,B,C,D LT-0103 LT-0701,0702,0703 0704 PT-0306 PT-0751,A,B,C,D PT-0752,A,B,C,D RE-1805,1806,1807 TE-0112 CA,CB,CC, CD,HA,HB,HC,HD, TE-0122,CA,CB,CC, CD,HA,HB,HC,HD, TE-01 llA, B,H TE-0121A,B,H 2

JCO J-48 POS-19 J-48 LT-4 J-48 LT-4 J-48 LT-5 J-48 PT-1 J-48 PT-5 J-48 RE-1 J-48 TE-1 The JCO's identified in the previous table are presented in Attachment 2 (Pages 1-4) to Consumers Power Company submital dated June 15, 1984.

Details for the basis of these JCOs are given in our submittals dated March 3, 1982 and December 4, 1981.

Discussions with NRC staff personnel indicated that for six of these JCOs certain items in the basis discussion should be clarified.

These clarifications are as follows:

EEQ-85-0l-NL02

Director, NRR EQ Replacement Schedule January 1°5, 1985
  • 3
1.

J-48 LT-3:

The statement regarding the 4 transmitters recently installed being qualified by test can be updated to indicate those 4 transmitters are now qualified.

2.

J-48 LT-5:

Same update as in number 1 for the 6 transmitters in this JCO.

3.

J-48 POS-16:

POS 3027B and 3056B are position indication for SIRW tank recirculation isolation valves.

The accident mitigation function of their associated control valve is to insure potentially high radioactivity water is not recirculated into the SIRW tank following the automatic switchover to containment sump for safety injection suction.

Since these are series valves closure of either valve will accomplish the required function.

The available indication to the control room operator are a redundant set of valve position indicators POS-3027A and 56A, as well as, a flow indicator FI-0404 which is in series with the subject valves.

4.

J-48 POS-19:

POS 2113, 15, and 17 are position indicators for control valves CV-2113, 15 and 17 respectively.

These three valves are in a parallel header arrangement off the primary coolant charging line.

They direct flow to the Primary Coolant System (PCS) Loop 1 (CF-2113), PCS Loop 2 (CV-2115) or the pressurizer spray nozzle (CV-2117).

Their control position is either full open or full close, ie, these are non-modulating valves.

During normal operation the two loop supply valves are open and the auxiliary spray valve is closed.

The only control function this set of valves would be expected to perform the following a small LOCA or steam generator tube rupture, would be to terminate flow to the looops and initiate auxiliary pressurizer spray flow.

The objective being to reduce PCS pressure and limit primary coolant losses.

These valves would not be called on to function following a MSLB or large LOCA.

5.

J-48 POS-19:

The charging line header is monitored by pressure indicator alarm PIA-0212 and flow indicator alarm FIA-0212.

These devices are all outside the harsh environment.

If all three valves were closed pressure and flow would be out-of-range and annunciated.

If the auxiliary spray line was falsely indicated the actual valve status could be inferred from changes in the pressurizer pressure (PT-0105A or PT-0105B both are EEQ qualified devices) or pressurizer temperature.

If either loop supply valve is falsely indicated there are no adverse operating or accident consequences since either line can accomodate full flow.

EEQ-85-01-NL02

Director, NRR EQ Replacement Schedule January 15, 1985
  • 4 On a more generic bases these position switches are actually two discrete devices, one. positioned to actuate a light when the valve is full open the other positioned for full closed.

When a failure occurs one or the other would open, short line to line, or short line to ground.

Any single device failure on a given valve will result in either both indicating lights being on or neither light on.

This immediately alerts the operator that the instrumentation is suspect.

6.

J-48 PT-5:

Subsequent failure of these will not reopen any valves because of the manual reset needed for containment isolation.

7.

J-48 RE-1:

Subsequent failure of these will not reopen any valves because of the manual reset needed for containment isolation.

Brian D Johnson Staff Licensing Engineer CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades EEQ-85-0l-NL02