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consumers Power POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 March 20, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
consumers Power POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 March 20, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
UPDATE TO ACTION ITEMS SUPPORTING THE MAY 21, 1986 CONFIRMATORY ACTION LETTER In material presented to the NRC during the February 17, 1989 Quarterly Update Meeting at Region III Headquarters, Consumers Power committed to provide the NRC with an update on the status of action items supporting the May 21, 1986 Confirmatory Action Letter. These action items are identified in IEIR 86035 and our responses to the NRC dated December 1, 1986, January 28, 1987, September 14, 1987 and October 30, 1987. They incorporate the Material Condition Task Force, the System Functional Evaluation, the Safety System Functional Inspection and a total of 1,270 action items. As of this date, 71 of these action items remain open.
UPDATE TO ACTION ITEMS SUPPORTING THE MAY 21, 1986 CONFIRMATORY ACTION LETTER In material presented to the NRC during the February 17, 1989 Quarterly Update Meeting at Region III Headquarters, Consumers Power committed to provide the NRC with an update on the status of action items supporting the May 21, 1986 Confirmatory Action Letter.
These action items are identified in IEIR 86035 and our responses to the NRC dated December 1, 1986, January 28, 1987, September 14, 1987 and October 30, 1987.
They incorporate the Material Condition Task Force, the System Functional Evaluation, the Safety System Functional Inspection and a total of 1,270 action items.
As of this date, 71 of these action items remain open.
Following the status update of Confirmatory Action Items is an update of other commitments scheduled for completion during 1988-89.
Following the status update of Confirmatory Action Items is an update of other commitments scheduled for completion during 1988-89.
Listed below is the status of action items which were scheduled for the 1988 Refueling Outage but were not completed:
Listed below is the status of action items which were scheduled for the 1988 Refueling Outage but were not completed:
Commitment Issue                                   Number                      Status Diesel Generator                     PR12/0l/86A-l 72               The Plant experienced historical Lube Oil Temperature                  PR12/0l/86A-173                 nuisance problems with temperature Switch                                PR06/0l/87A-53                 switch TS-1478. Remote and local PW09/14/87B-07                  alarms below designed setpoints have occurred irregularly, most recently in July 1988. Investigations following each incident found no problem with the switch and verified that the switch would alarm at the designed
Issue Diesel Generator Lube Oil Temperature Switch 1:>>0:327(>:~:<)2 PDR ADOO::
::: 1:>>0:327(>:~:<)2    :3*:;1(>:32(>
p
PDR        ADOO:: O!'.:i000255 p                                PDC OC0389-0094-NL02
:3*:;1(>:32(>
O!'.:i000255 PDC OC0389-0094-NL02 Commitment Number PR12/0l/86A-l 72 PR12/0l/86A-173 PR06/0l/87A-53 PW09/14/87B-07 Status The Plant experienced historical nuisance problems with temperature switch TS-1478.
Remote and local alarms below designed setpoints have occurred irregularly, most recently in July 1988.
Investigations following each incident found no problem with the switch and verified that the switch would alarm at the designed  


Nuclear Regulatory Comm1ss1on                                            2 Palisades Plant I.
I.,
Update to Action Items March 20, 1989 setpoint. Material Condition Task Force (MCTF) recommended that the switch be replaced or the System Engineer should develop a solution which is free of repetitive failures.
Nuclear Regulatory Palisades Plant C.**
A modification is planned to replace the remote mounted switch with one locally mounted. This modification will take place during the 1990 Refueling Outage, or earlier pending modification approval, switch procure-ment and installation method.
omm1ss1on Update to Action Items March 20, 1989 Bettis Robot Arm Actuators Restoring Original Operating Margins on Service Water and Component Cooling Water Flows PR12/0l/86A-317 PR06/01/87A-115 PW01/28/87C-23 PW01/28/87C-26 Containment Isolation PR12/0l/86A-135 Valves on Hydrogen Monitoring System OC0389-0094-NL02 2
Bettis Robot Arm      PR12/0l/86A-317 The MCTF recommendation indicated that Actuators              PR06/01/87A-115 all Bettis actuators should be rebuilt.
setpoint. Material Condition Task Force (MCTF) recommended that the switch be replaced or the System Engineer should develop a solution which is free of repetitive failures.
A modification is planned to replace the remote mounted switch with one locally mounted.
This modification will take place during the 1990 Refueling Outage, or earlier pending modification approval, switch procure-ment and installation method.
The MCTF recommendation indicated that all Bettis actuators should be rebuilt.
All Bettis operators were rebuilt either during the 1986 Maintenance Outage or during the 1988 Refout with the exception of VOP-0846 and VOP-0857.
All Bettis operators were rebuilt either during the 1986 Maintenance Outage or during the 1988 Refout with the exception of VOP-0846 and VOP-0857.
These were not able to be rebuilt due to mechanical interferences at their installed locations and cannot be removed without installation of alternate service water supplies to the component cooling heat exchangers.
These were not able to be rebuilt due to mechanical interferences at their installed locations and cannot be removed without installation of alternate service water supplies to the component cooling heat exchangers.
This modification cannot be economically justified at this time. Presently the val~es stroke acceptably and stroking is insured on a continuing basis via PPAC X-OPS-281.
This modification cannot be economically justified at this time.
Restoring Original    PW01/28/87C-23  These commitments required evaluation Operating Margins on  PW01/28/87C-26  of alternatives to restore the original Service Water and                      operating margins on service water and Component Cooling                      component cooling water flows. A Water Flows                            consultant was contracted to study these issues and their report made several recommendations regarding equipment enhancements to improve reliability. Consumers Power has requested a meeting with the NRC to discuss these recommendations.
Presently the val~es stroke acceptably and stroking is insured on a continuing basis via PPAC X-OPS-281.
Containment Isolation  PR12/0l/86A-135 This commitment was made to pursue a Valves on Hydrogen                    Technical Specification change to Monitoring System                      reduce testing frequency of the OC0389-0094-NL02
These commitments required evaluation of alternatives to restore the original operating margins on service water and component cooling water flows.
A consultant was contracted to study these issues and their report made several recommendations regarding equipment enhancements to improve reliability.
Consumers Power has requested a meeting with the NRC to discuss these recommendations.
This commitment was made to pursue a Technical Specification change to reduce testing frequency of the  


Nuclear Regulatory Comm.ion                                                   3 Palisades Plant Update to Action Items March 20, 1989 hydrogen monitoring system containment isolation valves. Presently the valves are stroked daily and due to this frequent use, have become a high maintenance item. The majority of this maintenance is directly related to valve position indication which is accomplished through the use of reed switches. These switches come out of calibration after extensive valve stroking and cause faulty valve position indications. The restructured Technical Specifications will reduce this frequency to a quarterly bases.
Nuclear Regulatory Comm.ion Palisades Plant 3
Update to Action Items March 20, 1989 hydrogen monitoring system containment isolation valves.
Presently the valves are stroked daily and due to this frequent use, have become a high maintenance item.
The majority of this maintenance is directly related to valve position indication which is accomplished through the use of reed switches.
These switches come out of calibration after extensive valve stroking and cause faulty valve position indications.
The restructured Technical Specifications will reduce this frequency to a quarterly bases.
Therefore, based on the restructured Technical Specifications, no actions will be taken at this time.
Therefore, based on the restructured Technical Specifications, no actions will be taken at this time.
We also have a number of action items which were scheduled for a 1989 Maintenance Outage. Due to numerous recent forced outages, Consumers Power does not presently anticipate a Maintenance Outage in 1989. These action items are discussed below:
We also have a number of action items which were scheduled for a 1989 Maintenance Outage.
Commitment Number               Issue PR12/0l/86A-169       These MCTF items pertain to the fuel oil supply for the PR12/0l/86A-170        diesel generators. Specifically they address the modifi-PR12/0l/86A-171        cation to connect T-926 to T-10, procurement of a spare PR06/0l/87A-50        fuel oil transfer pump and providing a secondary containment PR06/0l/87A-51        for the fuel oil storage tank. We anticipate procuring PR06/0l/87A-52        the spare pump and resolving the secondary containment issue by the end of 1989. The modification to provide additional storage capacity will be completed during the next scheduled outage of sufficient length and scope.
Due to numerous recent forced outages, Consumers Power does not presently anticipate a Maintenance Outage in 1989.
PR12/01/86A-297        This MCTF item was to replace the steam generator PR06/0l/87A-108        blowdown radiation monitor RIA-0707. This will still be completed by December 31, 1989 PR12/0l/86A-241        The MCTF recommended that primary loop measurement channel 1 PR12/0l/86A-254        temperature/pressure recorder, PTR-0115 and primary loop measurement channel 2 temperature/pressure recorder PTR-0125 be upgraded. During the 1988 Refueling Outage, functionally identical recorders were installed as part of a core cooling modification. PTR-0115 and PTR-0125 will be removed during the next outage of sufficient length and scope.
These action items are discussed below:
OC0389-0094-NL02
Commitment Number PR12/0l/86A-169 PR12/0l/86A-170 PR12/0l/86A-171 PR06/0l/87A-50 PR06/0l/87A-51 PR06/0l/87A-52 PR12/01/86A-297 PR06/0l/87A-108 PR12/0l/86A-241 PR12/0l/86A-254 OC0389-0094-NL02 Issue These MCTF items pertain to the fuel oil supply for the diesel generators.
Specifically they address the modifi-cation to connect T-926 to T-10, procurement of a spare fuel oil transfer pump and providing a secondary containment for the fuel oil storage tank.
We anticipate procuring the spare pump and resolving the secondary containment issue by the end of 1989.
The modification to provide additional storage capacity will be completed during the next scheduled outage of sufficient length and scope.
This MCTF item was to replace the steam generator blowdown radiation monitor RIA-0707.
This will still be completed by December 31, 1989 The MCTF recommended that primary loop measurement channel 1 temperature/pressure recorder, PTR-0115 and primary loop measurement channel 2 temperature/pressure recorder PTR-0125 be upgraded.
During the 1988 Refueling Outage, functionally identical recorders were installed as part of a core cooling modification.
PTR-0115 and PTR-0125 will be removed during the next outage of sufficient length and scope.  


Nuclear Regulatory                                                           4 Palisades Plant Update to Action Items March 20, 1989 The status updates listed below relate to issues outside the scope of the Confirmatory Action Letter:
Nuclear Regulatory Palisades Plant Update to Action Items March 20, 1989 4
Commitment Issue                     Number          Status Level Indicating       PR01/22/86A-Ol     In our supplemental response dated System for Safety      PR04I11/86C-01      April 11, 1986 to IEIR 85027, we Injection Tanks                            indicated that we would notify the NRC if we decided not to modify the safety injection tank level indicating system as previously committed. This modification would have included relocating the lower instrument tap and thereby excluding the SIT outlet pipe as an instrument reference leg.
The status updates listed below relate to issues outside the scope of the Confirmatory Action Letter:
Since repairs have been made to reduce in-leakage, we feel that this modification is unnecessary. We have decided, however, to modify the floats for the SIT level switches to increase the operating band for acceptable water levels in the SITs.
Issue Level Indicating System for Safety Injection Tanks Adequacy of Minimum Flow Lines for Auxiliary Feedwater Pumps OC0389-0094-NL02 Commitment Number PR01/22/86A-Ol PR04I11/86C-01 PW07/07/88B-04 Status In our supplemental response dated April 11, 1986 to IEIR 85027, we indicated that we would notify the NRC if we decided not to modify the safety injection tank level indicating system as previously committed.
This modification would have included relocating the lower instrument tap and thereby excluding the SIT outlet pipe as an instrument reference leg.
Since repairs have been made to reduce in-leakage, we feel that this modification is unnecessary.
We have decided, however, to modify the floats for the SIT level switches to increase the operating band for acceptable water levels in the SITs.
This will also necessitate a change to the Technical Specifications.
This will also necessitate a change to the Technical Specifications.
This modification will be completed during the 1990 Refueling Outage.
This modification will be completed during the 1990 Refueling Outage.
Adequacy of Minimum    PW07/07/88B-04      In our response to NRC Bulletin 88-04 Flow Lines for                            dated July 7, 1988, we committed to Auxiliary Feedwater                        develop a testing program to establish Pumps                                      the exact minimum flow rate required for AFW pump P-8C. This was to be completed during or before the 1989 Maintenance Outage. The test will be written by September 1, 1989 and the test run during the first outage of sufficient length and scope.
In our response to NRC Bulletin 88-04 dated July 7, 1988, we committed to develop a testing program to establish the exact minimum flow rate required for AFW pump P-8C.
OC0389-0094-NL02
This was to be completed during or before the 1989 Maintenance Outage.
The test will be written by September 1, 1989 and the test run during the first outage of sufficient length and scope.  


*~*
*~*  
"\
"\\
Palisades Plant Update to Action Items March 20, 1989 Nuclear Regulatory Commission                                                5 The NRC will be notified if changes are made to any of the above action items.
Nuclear Regulatory Commission Palisades Plant Update to Action Items March 20, 1989 5
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III; NRC NRC Resident Inspector - Palisades OC0389-0094-NL02}}
The NRC will be notified if changes are made to any of the above action items.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III; NRC NRC Resident Inspector - Palisades OC0389-0094-NL02}}

Latest revision as of 09:17, 6 January 2025

Submits Update to Action Items Supporting 860521 Confirmatory Action Ltr Re Diesel Generator,Lube Oil Temp & Switch.Items Scheduled for 1988 Refueling Outage But Not Completed
ML18054A595
Person / Time
Site: Palisades 
Issue date: 03/20/1989
From: Johnson B
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CAL, NUDOCS 8903270302
Download: ML18054A595 (5)


Text

...

consumers Power POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-0550 March 20, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

UPDATE TO ACTION ITEMS SUPPORTING THE MAY 21, 1986 CONFIRMATORY ACTION LETTER In material presented to the NRC during the February 17, 1989 Quarterly Update Meeting at Region III Headquarters, Consumers Power committed to provide the NRC with an update on the status of action items supporting the May 21, 1986 Confirmatory Action Letter.

These action items are identified in IEIR 86035 and our responses to the NRC dated December 1, 1986, January 28, 1987, September 14, 1987 and October 30, 1987.

They incorporate the Material Condition Task Force, the System Functional Evaluation, the Safety System Functional Inspection and a total of 1,270 action items.

As of this date, 71 of these action items remain open.

Following the status update of Confirmatory Action Items is an update of other commitments scheduled for completion during 1988-89.

Listed below is the status of action items which were scheduled for the 1988 Refueling Outage but were not completed:

Issue Diesel Generator Lube Oil Temperature Switch 1:>>0:327(>:~:<)2 PDR ADOO::

p

3*:;1(>:32(>

O!'.:i000255 PDC OC0389-0094-NL02 Commitment Number PR12/0l/86A-l 72 PR12/0l/86A-173 PR06/0l/87A-53 PW09/14/87B-07 Status The Plant experienced historical nuisance problems with temperature switch TS-1478.

Remote and local alarms below designed setpoints have occurred irregularly, most recently in July 1988.

Investigations following each incident found no problem with the switch and verified that the switch would alarm at the designed

I.,

Nuclear Regulatory Palisades Plant C.**

omm1ss1on Update to Action Items March 20, 1989 Bettis Robot Arm Actuators Restoring Original Operating Margins on Service Water and Component Cooling Water Flows PR12/0l/86A-317 PR06/01/87A-115 PW01/28/87C-23 PW01/28/87C-26 Containment Isolation PR12/0l/86A-135 Valves on Hydrogen Monitoring System OC0389-0094-NL02 2

setpoint. Material Condition Task Force (MCTF) recommended that the switch be replaced or the System Engineer should develop a solution which is free of repetitive failures.

A modification is planned to replace the remote mounted switch with one locally mounted.

This modification will take place during the 1990 Refueling Outage, or earlier pending modification approval, switch procure-ment and installation method.

The MCTF recommendation indicated that all Bettis actuators should be rebuilt.

All Bettis operators were rebuilt either during the 1986 Maintenance Outage or during the 1988 Refout with the exception of VOP-0846 and VOP-0857.

These were not able to be rebuilt due to mechanical interferences at their installed locations and cannot be removed without installation of alternate service water supplies to the component cooling heat exchangers.

This modification cannot be economically justified at this time.

Presently the val~es stroke acceptably and stroking is insured on a continuing basis via PPAC X-OPS-281.

These commitments required evaluation of alternatives to restore the original operating margins on service water and component cooling water flows.

A consultant was contracted to study these issues and their report made several recommendations regarding equipment enhancements to improve reliability.

Consumers Power has requested a meeting with the NRC to discuss these recommendations.

This commitment was made to pursue a Technical Specification change to reduce testing frequency of the

Nuclear Regulatory Comm.ion Palisades Plant 3

Update to Action Items March 20, 1989 hydrogen monitoring system containment isolation valves.

Presently the valves are stroked daily and due to this frequent use, have become a high maintenance item.

The majority of this maintenance is directly related to valve position indication which is accomplished through the use of reed switches.

These switches come out of calibration after extensive valve stroking and cause faulty valve position indications.

The restructured Technical Specifications will reduce this frequency to a quarterly bases.

Therefore, based on the restructured Technical Specifications, no actions will be taken at this time.

We also have a number of action items which were scheduled for a 1989 Maintenance Outage.

Due to numerous recent forced outages, Consumers Power does not presently anticipate a Maintenance Outage in 1989.

These action items are discussed below:

Commitment Number PR12/0l/86A-169 PR12/0l/86A-170 PR12/0l/86A-171 PR06/0l/87A-50 PR06/0l/87A-51 PR06/0l/87A-52 PR12/01/86A-297 PR06/0l/87A-108 PR12/0l/86A-241 PR12/0l/86A-254 OC0389-0094-NL02 Issue These MCTF items pertain to the fuel oil supply for the diesel generators.

Specifically they address the modifi-cation to connect T-926 to T-10, procurement of a spare fuel oil transfer pump and providing a secondary containment for the fuel oil storage tank.

We anticipate procuring the spare pump and resolving the secondary containment issue by the end of 1989.

The modification to provide additional storage capacity will be completed during the next scheduled outage of sufficient length and scope.

This MCTF item was to replace the steam generator blowdown radiation monitor RIA-0707.

This will still be completed by December 31, 1989 The MCTF recommended that primary loop measurement channel 1 temperature/pressure recorder, PTR-0115 and primary loop measurement channel 2 temperature/pressure recorder PTR-0125 be upgraded.

During the 1988 Refueling Outage, functionally identical recorders were installed as part of a core cooling modification.

PTR-0115 and PTR-0125 will be removed during the next outage of sufficient length and scope.

Nuclear Regulatory Palisades Plant Update to Action Items March 20, 1989 4

The status updates listed below relate to issues outside the scope of the Confirmatory Action Letter:

Issue Level Indicating System for Safety Injection Tanks Adequacy of Minimum Flow Lines for Auxiliary Feedwater Pumps OC0389-0094-NL02 Commitment Number PR01/22/86A-Ol PR04I11/86C-01 PW07/07/88B-04 Status In our supplemental response dated April 11, 1986 to IEIR 85027, we indicated that we would notify the NRC if we decided not to modify the safety injection tank level indicating system as previously committed.

This modification would have included relocating the lower instrument tap and thereby excluding the SIT outlet pipe as an instrument reference leg.

Since repairs have been made to reduce in-leakage, we feel that this modification is unnecessary.

We have decided, however, to modify the floats for the SIT level switches to increase the operating band for acceptable water levels in the SITs.

This will also necessitate a change to the Technical Specifications.

This modification will be completed during the 1990 Refueling Outage.

In our response to NRC Bulletin 88-04 dated July 7, 1988, we committed to develop a testing program to establish the exact minimum flow rate required for AFW pump P-8C.

This was to be completed during or before the 1989 Maintenance Outage.

The test will be written by September 1, 1989 and the test run during the first outage of sufficient length and scope.

  • ~*

"\\

Nuclear Regulatory Commission Palisades Plant Update to Action Items March 20, 1989 5

The NRC will be notified if changes are made to any of the above action items.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III; NRC NRC Resident Inspector - Palisades OC0389-0094-NL02