ML18347A691
| ML18347A691 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/08/1976 |
| From: | Bixel D Consumers Power Co |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A691 (3) | |
Text
consumers Power company General Offices: 212 West Michigan Avenue, Jack.;;on, Michigan 49201
- Area Code 517 788-0550 March 8, 1976 Director of Nuclear Reactor Regulation Att:
Mr Robert A. Purple, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT -
BORON CONCENTRATION In our letter of August 27, 1975, we indicated that we would advise you, on a bimonthly basis, of the status of our program to prevent unacceptable chemical concentrations during the long term after a Loss of Coolant Accident (LOCA).
This program involves the qualification of equipment required to provide in-dependent flow paths to the reactor vessel.
This letter provides the third status report of this program and covers the period through March 5, 1976.
The qualification of equipment needed for long-term cooling is proceeding with all possible haste.
Completion of all qualification requirements will provide two alternate equipment alignments to assure long-term cooling of the reactor core following a cold leg break LOCA at Palis.ades.
The qualification will assure that a "single" failure within containment cannot eliminate both align-ments.
The qualification program has assumed that minor repairs can be made in some areas outside of containment following a LOCA.
Potential repairs have been limited to those that c.an be made within the 12-hour requirement, and with acceptable radiation exposure, to establish long-term cooling.
Qualification or replacement of certain equipment has been complicated because of the position taken by two suppliers apparently due to present or proposed regulatory requirements relating to Quality Assurance.
The following is the status of particular component qualifications.
ITEM 1 - M0-3015, M0-3016 The new motors from Limitorque (Reliance Electric) arrived on site in February.
Both motors will be replaced during the present outage.
Preliminary results of a review by Operating Services and Bechtel indicate that the power cables within conta1nment, to the motors, must be replaced.
To meet separation requirements of the primary and secondary alignments, the power and control cables for M0-3015 and M0-3016 will be run in their own conduits within con-tainment.
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2 ITEM 2 - PS-0103 A qualified pressure switch cannot be obtained during the present outage.
Therefore, a temporary procedure is being written to bypass the interlock, between PS-0103 and M0-3015 and M0-3016, in the event that the pressure switch fails following a LOCA event.
Also, a qualified pressure transmitter manufactured by Rosemont was ordered.
This transmitter will provide a signal from 0 to 500 psig of PCS pressure.
Delivery date is not yet available.
ITEM 3 - CV-2113, CV-2115 IT&T Hammel-Dahl is not able to meet the required delivery of qualified re-placement parts for these valves.
Therefore, Bechtel and IT&T will perform the analysis necessary to design modifications to the valve actuators to seismically qualify them.
Other suppliers of actuator diaphragms are being investigated.
ITEM 4 - CV-2117 The replacement diaphragm and seal housing required to qualify the valve are.
on site.
The necessary paperwork and seismic report should be delivered by March 12, 1976.
ITEM 5 - SV-2113, SV-2115, SV-2117 ASCO has indicated they cannot meet the required delivery date.
Operating Services is investigating the acceptability of qualifying the existing valves.
At most, this will require removing one valve and testing it at the Lab under the post-LOCA temperature and humidity conditions.
ITEM 6 -
CONTROL AIR SYSTEM The system has been inspected.
J. A. Jones Company will be contracted to in-stall additional piping supports to meet Bechtel's recommendations.
This item is scheduled to be completed by April 1, 1976.
The above modifications are being made to the control air system within containment only.
This will Q-list that part of the system.
In the event of failure of some portion of the Control Air System outside of containment following a LOCA, a supply of nitro-gen can be connected to the system.
This connection will be made between the two isolation valves (P&ID 212, D-3) utilizing an existing, normally locked closed, test valve.
ITEM 7, CV-1057, CV-1059 Status of this item is identical to Item 4.
ITEM 8 -
E/P~l057, E/P-1059 New qualified E/Ps were ordered from Fisher Controls.
Delivery date is scheduled to be March 26, 1976.
A maintenance order has been written to re-place these devices.
3 ITEM 9 - ELECTRICAL POWER AND CONTROL CABLE QUALIFICATION Inspection _of the cable has been completed.
Those cables requiring replacement are identified under the items involved.
ITEM 10 - ELECTRICAL POWER INDEPENDENCE Inspection by Bechtei and Consumers Power Co has identified all the cable in-volved in both the.primary and secondary alignments.
A Bechtel report, due March 8, 1976, will detail any modifications required to provide electrical separation, within containment, between the two alignments.
ITEM 11 - MISCELLANEOUS The status of this item remains the same.
- Plant stock records, drawings and maintenance procedures reviews will be completed following upgrading of the individual components.
ITEM 12 - MISCELLANEOUS Check Valve 3174 (P&ID M-204, B-7) will be moved to an area that would permit internals removed following an accident or have its internals.removed as a permanent fix during this qutage.
The necessity of this valve is still under investigation
- David A. Bixel Assistant Nuclear Licensing Administrator CC:
JGKeppler, USNRC