ML18347A655
| ML18347A655 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 07/07/1976 |
| From: | Bixel D Consumers Power Co |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A655 (2) | |
Text
...--
~:* *~
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 July 7, 1976 f
lt..*~
~t!l}1~-tj Director of Nuclear Reactor Regulation If;.-* _..m~
Att:
Mr Albert Schwencer, Chief
(~
_,SNl!Cl>.
-v~~
Operating Reactor Branch No 1
(~-
~
us Nuclear Regulatory Commission
- JULl 01976... r Washington, DC 20555
,l...
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 fifth status report of this program and covers the period through June 14.
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.
Item 3.
CV-2113 and CV-2115 - Alternate Alignment It has been determined that new bonnets and bolting are needed to qualify these valves.
Materials will be ordered as soon as.manufacturer's qualification report is received.
Viton diaphragms and 0-rings must also be installed.
Completion date unknown.
Item 4.
CV-2117 - Alternate Alignment This item is considered complete as stated in the fourth station report (4-15-76),
2 Item 5.
SV-2113, SV-2115 and SV-2117 - Alternate Alignment Qualified replacement valves have been received.
Installation of the new valves is being scheduled.
Item 6.
Instrument Air System - Alternate Alignment This item 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 No change in status since last report.
All cables have been identified, All primary alignment cables are qualified to post-LOCA environmental conditions.
Item 10. Electrical Power Independ*ence - 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 and design work are expected to take about six months and could not be completed during the past outage.
Item 11.
Miscellaneous Procedures - Primary and Alternate Alignments As stated in the last report, 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, 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 as stated in our last report.
We consider this item completed.
David A. Bixel Assistant Nuclear Licensing Administrator CC:
JGKeppler, USNRC