ML19221A508
| ML19221A508 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/06/1979 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905230107 | |
| Download: ML19221A508 (3) | |
Text
.
Issued:
4/6/79 MEETING MINUTES 1200 Hrs.
of TECHNICAL WORKING GROUP i
Meeting No. 2 (1700 Hrs., 4/5/79)
Item 1 - Venting Waste Gas in the Containment - Venting process being started.
"B" waste gac tank will be the first to be vented.
(Note:
0800, 4/6/79:
valve problems; "A" tank to be vented first)
Item 2 - Degassing - It is not planned to provide hydrogen over-pressure in the makeup tank The IAG will make a recommendation relative to the need to take a primary system sample, based on latest information from NRC.
The robot is not trained to take a pres.=urized..aple.
It is planned to use the robot to take an unp. 'ssurized sample, hopefully within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(see Item 12)
~
Action - Levenson Item 3 - Westinghouse DHR - Preliminary Schedule for installation of DHR to be provided by 4 P.M. Friday, April 6, 1979.
Ware-hcuse for collecting needed equipment is to be at Three Mile Island site.
The spent fuel area and cooling pumps are not to be used as part of the DHR unless absolutely necessary.
System must be available at the time plant goes to natural circulation:
no later than five days frcm now (4/10/79).
Westinghouse to provide whatever redundancy and leak tightness that can be provided in the five-day span.
Action - Westinghouse, Cobean Item 4 - Pressurizer Level Instrumentation - failure.
Develop test procedure and obtain NRC approval for alternate schemes.
Action - Herbein 163 29-5 Item 5 - Derinition of Safe ty System - Mr. Cobean and Mr. McMillan are to complete lists of critical systems, considering current operating mode, and provide to Dick Wilson.
Action - Cobean and McMillan.
7905230/0 7 (s) 4 April 6, 1979
' Item 6 - Additional Boiler Capacity - Confirm effect of continued steam dump to ecndenser assuming loss of vacuum.
Action - Wilson Item 7 - Long Term Cooling - Wilson, McMillan, and Levenson to confirm proposed course of action by Friday, April 6, 1979.
Preparations, including engineering and procurement, to proceed immediately.
Actual plant modification will be authorized by Arnold and Dieckamp at a later day.
Confirm status of 10 mw diesel.
Action - Wilson, McMillan, Levenson, and Cobean (Diesel Status)
Item 8 - Site Evacuation - Gilbert Associates studying core unloadind for Unit 1.
(This will probably not be done)
Levenson to provide Herbein with description of what is to be looked at in terms of fire protection.
Mr. S tern and Mr. Arnold will make recommendations relative to plant configuation in case of Control Room evacuation.
NRC will supply estimated melt-through times based on current core condition.
NRC to investigate providing assistance.
Action - Herbein, Stern, Arnold, and NRC.
Item 9 - Static Pressure System - B&R to proceed on stand pipe design and procurement.
IAG to make recommendation for alternate methods of pressure and volume control.
Action - Cobean and Levenson Item 10 - DELETED Item 11 - Secondary Modifications - One 2,500 kw diesel generator shipped Friday.
May not be sufficient; another should be obtained.
Action - Cobean Item 12 - Primary Coolant Sample - Actual capacity of robot and results of tests to date to be confirmed.
Action - Herbein Item 13 - Oconee Test - Test will not be conducted.
Item 14 - Added Emergency Power - See Item 7.
O April 6, 1979
.y Item 15 - Aux. Building Activity Levels - Frank Palmer to provide definitive recommendation (caustics, etc.)
for 9 A.M.
Friday morning.
Action - Palmer Item 16 - Reactor Building under vacuum - No action at present.
If negative pressure approaches 2.0 PSI, investigate shutting water flow to fan coolers.
163 295.
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