ML18347A574

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Providing 6th Status Report of Boron Concentration - Long-Term Cooling, Covering Period Through August 14, 1976
ML18347A574
Person / Time
Site: Palisades 
Issue date: 08/18/1976
From: Bixel D
Consumers Power Co
To: Schwencer A
Office of Nuclear Reactor Regulation
References
Download: ML18347A574 (2)


Text

August l8, 1976

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!W~ t!Jltilli. LI il Ut;.,iL. \\VJ~~ f Director of Nuclear Reactor Regulation Att:

Mr Albert Schwencer, Chief Operating Reactor Branch No l US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR PALISADES PLANT -

BORON CONCENTRATION """*

LONG-TERM COOLING In our letter of August 27, 1975., we indi.cated 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 sixth status report of this program and covers the period through August l4, 1976.

Item l. 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 petween 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-2ll3 and CV-2ll5 - Alternate Alignment It has been determined that new bonnets and bolti.ng are needed to qualify these valves.

These parts have been ordered.

Viton diaphragms and 0-rings must also be _installed.

Completion date unknown.

Item 4, CV-2ll7 - Alternate Alignment

  • This item is considered complete as stated in the fourth status report (4-15-76).

8538*

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2 Item 5.

SV-2ll3, SV-2ll5 and SV-2ll7 - Alternate Alignment No change in status since last report.

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-l057 and CV-l059 - Alternate Alignment The diaphragm and seal housing assembly has been changed on these valves and we consider this eg_uipment to meet the reg_uirements for long-term cooling.

Item 8.

E/P-l057 and E/P-l059 - Alternate Alignment This item is considered complete as stated in the fourth status report (4-l5-76).

Documentation showing that this eg_uipment meets radiation exposure reg_uirements 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 g_ualified to post-LOCA environmental conditions.

Item lO.

Electrical Power Independence - Primary and Alternate Alignments No change in status since last report.

A study of cable separation reg_uirements between the two alignments has determined that additional separation will be re-

g_uired, Engineering and design work are expected to take about six months and could not be completed during the past outage.

Item ll. 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 l2.

Miscellaneous - Check Valve 3l74 As stated in the fourth status report, it was determined that this valve was not reg_uired.

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,

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/S1I~<,1,Ll,'1th-David A. Bixel Assistant Nuclear Licensing Administrator CC:

JGKeppler, USNRC