ML19249D345

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Submits TMI-2 Weekly Status Rept.Discusses Plant Status
ML19249D345
Person / Time
Site: Crane 
Issue date: 08/05/1979
From: Jay Collins
NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE
To: Harold Denton, Vollmer R
NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE, Office of Nuclear Reactor Regulation
References
NUDOCS 7909240190
Download: ML19249D345 (3)


Text

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August 5, 1979 MEMORANDtM FOR: Harold R. Denton, Director, NRR Richard H. Vollmer, Dire tor, TMI-2 Support FROM:

John T. Collins, Deputy Director, TMI-2 Support

SUBJECT:

THI-2 WEEKLY STATUS REPORT Plant Status:

Natural circulation operation continues with the following core and plant conditions:

0 Pressure - 268 psig Pressurizer Temperature - 380 F (solid operation)

Rx Building

- 0.5 psig (negative)

- 1620F

, RC I.eak Rate

- 0.5 gym

,That T old

- 155 F Rx Building Water Level - 289.9 e

Max TC

- 257 F We continue to maintain about 13% closed on the turbine bypass valve. Weekly notor megger readings and twice weekly switchbox magget readings for DH-V-1, DH-V-171, DR-V-2 and CF-V-115 remain the same.

There have been no significapt releases to the environment in the past vcek.

Iodine-131 levels at the discharge point renained constant ar about 1 x 10-14 uCi/cc. All environmental surveys and samples show nothing above background.

On July 27, 1979, the Deputy Director, TMI-2 Support, together with repre-sentatives of the Office of State Programs, NMSS and GPU/ Met-Ed. attended a nesting with Governor Ray, State of Washington, to discuss P.he shipment of waste from TM1-2 to Richland, Washington.

Following this meeting, NRC and CPU representativcs met with local of ficials in Richland to discuss resubption of shipments to Richland.

CPU / Met-Ed' expects to resume shipments of vaste about August'7, 1979. The first several shipments will consist of dry compacted wastes in 55-gallon Once the drums (approximately 157) and 4 x 8 LSA boxes with dry wastes.

routina has been established, enroute states will be notified by the Office of State Programs.

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Harold R. Denton 2 _

August 5. 1979 Richard H. Vollmer The tank larm is now fully operational.

On July 28, 1979, approximately 17,000 gallons of water f rom the THI-2 auxiliary building was transferred to the lower tanks without incident.

Operator training and pre-operational testing are continuing on EPICOR-II. The shielded transfer bell is now scheduled to be delivered the week of August 6.

1979. The system should be declared operational in the next two wacks.

The NRC staff is currently reviewing and auditing all operating procedures and operator training associated with this system.

The "B" compressor for the waste gas processing system was removed and found to contain a damaged impellor which probably contributed significantly to the leakaga from this system. Plans are to helium test the entire vent header sys-tem during the coming week.

Pre-operational testing of the standby pressure control system is continuing.

The problem with the N regulators has been resolved.

2 The decay heat system is scheduled to be filled, vented and hydro tested during the coming week.

During the past week, a resin liner f rom EPICOR-I sy. stem was transferred to the interim se.orage area. The liner reading 900 mr/hr on contact was lowered into the culvert and covered with a 3-foot shield block.

Radiation measurenants taken outside the shield block showed a reading of 7 mr/hr which 'is in excess of the design basis value of less than 5 mr/hr.

Assuming a linear relationship, a 1000 r/hr cask from EPICOR-II would give a field of 7.8 r/hr which is unac-ceptable. It appears that we are getting streaming between the bottom of the shield block and "

surf ace of the earthen enhankment. Cpu is reevaluating the long-term storage taci.11ty to make sure a similar problem does not exist.

On %ursday, August 2. 1979, the Deputy Director, THI-2 Support together with rep-reJentatives of NHIS met with Chairman Hendric and Coc:missioner Ahearne to dis-cass the need for solidification of waste from nuclear power plants and other licensed facilities.

In addition we also discussed the need for solidification-of resins from TMI-2.

No formal action was taken on either of these cubjects.

Commissioner Ahearne requested that NRR and NMSS work more closely r.ogether to arrive at a mutually accepta!,le pcsition.

I informed Chairman Hendrie that we were forwarding to him an information paper outlining CPU's plans and programs for shipping waste to Richland.

I also informed the Commissioners that on August 1, 1979, I had received the value impact assessment from CPU and that we would for-ward to them a copy of NRR's evaluation of this report in the very near future.

On Thursday, July 26, 1979, Met-Ed initiated a routine release of treated waste water from Unit 1 WECT tank.

The relcase was typical of other releases and was made in compliance with the plant Tech Speca. The discharge was halted after 4,000 gallons were re? ased at the request of the NRC pending an analysis for beta emitters. Subsequent analyses identified strontium present in concentrations that resulted in the discharge of strontium being 8.77. of the maximum allowablu k

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Harold R. Denton

- 3 August 5, 1979 Richard H. Vollmer concentration. Operating procedures have been revised to require that a gross beta analysis be performed on all liquid discharges prior to release.

t This past week Met-Ed successfully completed a mock-up test of the containment sump sampling device. Additional tests will be conducted on the actual pene-tration line prior to making the initial cut.

If everything goes alright, we should be able to sample the containment sump water later this week or the be-ginning of next week.

ohn T. Collins. Deputy Director TMI-2 Support cc:

E. Case J. Collins V. Stello Chief, Resident Office, IE R. Mattson D. Eisenhut B. Crimes D. Ross D. Muller S. Hanauer F. Schroeder B. Boger B. Fitzpatrick H..Creenberg A. Ignatonis J. Lee T. Murphy C. Hinson R. Weller L. Bell W. Travers S. Newberry J. Wermiel M. Williams R. Bangart W. Kreger TMI Rdg. File SEP TMI adg. File NRR TMI Rdg. File PDR 4

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