ML18347A546
| ML18347A546 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/18/1976 |
| From: | Bixel D Consumers Power Co |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A546 (2) | |
Text
consumers REGULATDRY DOCl\\EJ f Jlf ~OPf Power
~
company General Offices:' 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 October 18, 1976 Director of Nuclear Reactor Regul.~u~~~1 Att:
Mr Albert Schwencer, Chief.9 Operating Reactor Branch No 1 US Nuclear Regulatory Commission 9 Washington, DC 20555 DOCKET 50-255, LICENSE DPR ~
PALISADES PLANT - BORON CONCENTRAT LONG-TERM COOLING 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 seventh status report of this program and covers the period through October 14, 1976.
Item 1.
MOV-3015 and MOV-3016 - Primary Alignment This item is considered complete as stated in the fourth status report (4-15-76).
Item 2.
PS-0103 - Primary Alignment As stated in our fourth status report, the long-term cooling procedure includes provisions for bypassing the interlock between the pressure switch (PS-0103) and motor-operated valves (MOV-3015 and MOV-3016).
A new qualified pressure trans-mitter is on site.
Engineering of associated electronics and instruments is under way.
Completion date of new transmitter installation is unknown at this time.
This item will be completed during or before the next scheduled refuel-ing outage (now scheduled for August 1977).
Item 3.
CV-2113 and CV-2115 - Alternate Alignment It has been determined that new bonnets and bolting are needed to qualify these valves.
These parts have been ordered and some items have been received.
Viton diaphragms and 0-rings must also be installed.
This item will be completed during or before the next scheduled refueling outage.
Item 4.
CV-2117 - Alternate Alignment This item is considered complete as stated in the fourth status report (4-15-76).
106?9
1*
2 Item 5.
SV-2113, SV-2115 and SV-2117 - Alternate Alignment No change in status since last report.
Qualified replacement valves have been received.
New valves will be installed during an outage of sufficient duration to permit. installation, or in any event not later than the end of the next scheduled refueling outage.
Item 6.
Instrument Air System - Alternate Alignment This ite~ is considered complete as stated in the fourth status report (4-15-76).
Updating of plant records and drawings, however, remains to be completed.
Item 7~ CV-1057 and CV-1059 - Alternate Alignment The diaphragm and seal housing assembly has been changed on these valves and we consider this equipment to meet the requirements for long-term cooling.
Item 8.
E/P-1057 and E/P-1059 - Alternate Alignment This item is considered complete as stated in the fourth status report (4-15-76).
Documentation showing that this equipment meets radiation exposure requirements has not been received.
We expect this documentation to be received by the end of 1976.
Item 9, Electrical Power and Control Cable Qualification - Primary and Alternate Alignments All primary and alternate. alignment cables, as originally installed, have been qualified to post-LOCA environmental conditions.
Item 10.
Electrical Power Independence - Primary and Alternate Alignments No change in status since last report.
A study of cable separation requirements between the two alignments has determined that additional separation will be re-quired.
Engineering for additional separation is scheduled to be completed by March 1977.
Installation will be completed by the end of the next scheduled refueling outage.
Item 11.. Miscellaneous Procedures - Primary and Alternate Alignments As stated previously, operating procedures for establishing long-term cooling have been completed.
Plant stock records, drawings and maintenance procedure review will be completed following upgrading of the individual components.
Item 12.
Miscellaneous - Check Valve 3174 As stated in the fourth status report (4-15-76), it was determined that this valve was not required.
This valve has been removed and replaced with a pipe spool instead of removing the valve internals.
We consider this item completed.
- ~~~
/
David A Bixel Assistant Nuclear Licensing Administrator CC:
JGKeppler, USNRC