ML20024D360

Forwards TMI Program Ofc Weekly Status Rept for Wk of 830717-23

ML20024D360
Person / Time
Site:	Crane
Issue date:	07/25/1983
From:	Barrett L Office of Nuclear Reactor Regulation
To:	Harold Denton, Snyder B Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-83-047, CON-NRC-TMI-83-47 NUDOCS 8308040634
Download: ML20024D360 (11)

Text

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July 25, 1983 NRC/TNI-83-047 MENORANDUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FROM:

Lake H. Barrett, Deputy Program Director THI Program Office

SUBJECT:

NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT FOR July 17 - July 23, 1983 Data from effluent and environmental monitoring systems indicated no plant releases in excess of regulatory limits. Waste shipments and water processing tasks continued on a routine basis. Plant parameters showed no significant changes.

General clean-up and preparations for headlift continued. The reactor coolant system is scheduled to be depressurized next week to prepare for underhead inspections.

Major activities this week were ongoing decontamination of drains and systems in the Auxiliary Building, continued decon facility construction, "A" spent fuel pool refurbishment, procedure review, preparations for underhead characterization, and continued followup of polar crane issues. -Four Reactor Building entries supported ~

miscellaneous tasks.

(For more details see appropriate paragraphs below.)

Significant items included in the enclosure are:

I Auxiliary and Fuel Handling Activities k q ['

Reactor Building Activities MF<

l Polar Crane Status Spent Fuel Pool "A" Refurbishment Waste Management Activities l

Publ_ic Meeting l

Data sumary sheets included in this report are:

Liquid Effluents Environmental Data Radioactive Material /Radwaste Shipment Data Water Processing Data f

f),9 Plant Status Data i

Oh sammemy f

l Me R. Bangtgy p

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8308040634 830725 Lake H. Barrett kDRADOCK05000 Deputy Program Director l

TMI Program Office l

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-Enclosttrer As-stated-DATE >

4 NRC FORM 318 (10-80) NRCM O240 OFFICIAL RECORD COPY l

f INTERNAL DISTRIBUTION EDO OGC Office Directors Comnissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS THIProgramOfficeStaff(15)

PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI TMIPO IlQ r/f TMI SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File I

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ENCLOSURE AUXILIARY Af4D FUEL HAf1DLING BUILDING ACTIVITIES:

The major ongoing activit'y in the Auxiliary and Fuel Handling Buildings (AFHB) continues to be the decontamination of the 282' elevation.

No remote -

decontamination was performed since the robot malfunctioned during its last use. Cubicle decon work may resune once the robot is cleaned and repaired.

Cleaning of the Auxiliary and fuel Handling Building floor drains have been terminated due to budgetary constraints.

Shielding was installed around a highly radioactive pipe in the waste evaporator cubicle to reduce dose rates for maintenance work.

Routine trash compaction and tool separation / decontamination continued in support of other tasks and activities presently in progress.

Expansion of the decontamination facility continued with the partial installation of the stainless steel floor and service air and water system.

The duct work is in place for the ventilation system.

Supporting procedures governing the operation and use of the newly purchased decontamination equipment remain in the licensee's review chain.

Construction of the facility I

should be completed in late August.

REACTOR BUILDING ACTIVITIES:

Four reactor building entries were completed during the week of July II.-1983 1

and three entries are scheduled for the week of July 24, 1983. On Monday,'

July 25, 1983, the implementation ot procedures.to depressurize and low $r the water levs1 in the reactor coolant system will commence in preparation for the reactor vessel Underhead Characterization Study. The primary system water level will be lowered in stages to permit the removal of one control rod drive mechanism (CRDM) and eventually to expose the top of the upper plenum assembly for dose rate measurements. A contingency closure has been provided for the pressure boundary at the disassembled CRDM nozzle, however it is anticipated that the reactor coolant system will remain depressurized and partially drained following the removal of the CRDM.

The NRC has completed the safety evaluations and procedure reviews of the initial tasks associated with the underhead characterization. Approved j

procedures are in place for CRDM removal, for lowering the primary system water to a level app'roximately one foot below the top of the upper plenum assembly (10 feet above the core region) and for taking'a series of radiation measure-E ments in this configuration. During this time, a closed circuit television inspection will be performed of the plenum surfaces and the underside of the reactor head.- Debris / swipe samples will be obtained from the surface of the plenum.

An ultrasonic device will be used to obtain a topographical outline of the damaged core.

As part of the u'nderhead characterization task, the NRC has established a contract with PNL to review major elements of this task (including radiation measurements, Cs plate-out on the plenum and other related chemistry phenomenon).

Information related to this and other underhead characterization a

studies is avai1~able at the NRC Middletown Office.

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2 The NRC is conducting a safety evaluation of GPUN's plans to obtain a debris sample from the loose rubble in the core region.

This safety evaluation addresses criticality issues, ALARA and radiological considerations, pryophoricity, Etc.

GPU huclear's schedule for the Underhead Characterization Study includes the following:

Commence depressurization/draindown - July 25, 1983 Remove CRDM - August 10, 1983 Underhead radiation measurements - August 18-29, 1983 Core Topography - September 5,1983 1

Core debris sample - September 9,1983

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Data obtained during the Underhead Characterization Study will serve as a major source of information for planning reactor vessel head removal concepts and procedures.

The TMIPO statf continues to closely monitor GPUN's efforts to reduce occupa-tional radiation exposures.

GPUN has a special. program to implement actions to minimize Reactor Building occupational exposures as part of its overall program to maintain all radiation exposures to As Low As Reasonably Achievable.(ALARA) levels. GPUN will brief TMIP0 staff (and PNL consultants) at 1:00 PM oh l

July 28, 1983, at the site on the status of its programs.

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POLAR CRANE STATUS:

i The TMI Program Office has resumed activities associated with the review of the Safety Evaluation for the Polar Crane Load Test and associated procedures. The staff forwarded a letter to the licensee on July 18, 1983, requesting additional information that is required for the NRC to complete its review.

l After the review of information already received and that which is being l

requested, the staff will make a determination on the acceptability of the load I

test as proposed by GPUNC.

i To date, the staff has not received a response to the letter dated July 8, 1983, requesting additional information on the head and internals handling indexing fixture (tripod). The licensee must obtain NRC approval of all corrective actions before the tripod can be used for load test and i

subsequent headlift.

The licensee has requested a meeting with NRC staff on August 5, 1983, to discuss the current status, including B&W stress analyses of the tripod fixture.

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l FUEL POOL "A" REFURBISHMENT:

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Decontamination and disposal of the steam eductor removed from the lower tank

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farm have been initiated.

The sump sucker pipe is being rerouted around the i

tank farm shield blocks.

The leak test procedure for the new pipe has been i

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reviewed and approved by NRC.

The rails of the Fuel Handling Building crane have been realigned, repairs and preparations for the load test of the shield clock lifting lugs are progressing.

The licensee submitted a license amendment asking for deletion of the reserve waste tankage requirement; formal noticing of this amendment by NRC occurred on July 18 in the Federal Register.

In the interim, the licensee also requested removal of the upper and. lower tank farm from the reserve tankage requirement and the addition of approximately 100,000 gallon reserve tankage, established from the freeboard of 6 additional tanks including the EPICOR off-spec tank (CC-T-1) and clean receiving tank (CC-T-2).

The NRC staff approved this request recognizing a reserve tankage margin (> f actor of 2) for unexpected events and the need for tank farm removal as part of the "A" pool refurbishment in preparation for future defu,eling and fuel storage.

WASTE MANAGEMENT ACTIVITIES:

1.

SDS Liner Shipments.

No SDS shipments were made this week.

Preparations are being made for the eleventh SDS shipment (D20026) which is scheduled for August 2, 1983. This waste liner, which contains approy > ately 9,700 curies, will not require a gas passification recombiner ystem for shipping purposes, because the curie loading and associated gas generation rates are sufficiently low to insure non-combustible gas conditions during handling.and shipment.

At the recommendat. ion of Rockwell Hanfords a 236 gram catalyst charge will be inserted in D20026 for long term stability purposes and the extensive vacuum-drying will also be performed.. Prior to shipment, the licensee will be required to monitor and sample the D20026 liner to demonstrate non-combustible gas conditions for a period -tif ~over twice the expected shipping period (s 14 days).

2.

EPICOR Demineralizer Shipments.

As reported in the July 18, 1983 Weekly Status Report, all 50 EPICOR II prefilters have been shipped from TMI to the Idaho National Engineering Laboratory (INEL).

The EPICOR system has been subsequently used to process the effluent from the 505 system (see previous Weekly Status Report, water processing - Arpendix 4). To date there have been a. total of 31 low level EPICOR demineralizers that have been generated from processing SDS effluents. These demineralizers, which contain from 0.5 to 4 curies of radioactivity, have been temporarily stored onsite at both the solid waste storage and the southeast storage facilities.

The licensee has initiated activities to ship these 31 EPICOR demineralizers to the Hanford, Washington, commercial burial facility over the rema.inder of 1983.

The shipping preparations will include re-dewater-ing at the EPICOR building and placement *of the liners (for > type A quantities) into shipping casks for transport and disposal.

PUBLIC MEETING:

1 The Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet on July 28,, 1983 from 7:00 PM to 10.00 PM in the Holiday Inn, 23 South Second Street, Harrisburg, Pennsylvania.

The meeting will be open to the public. The Panel will discuss TMI-2 cleanup activities. The TMI Unit 2 licensee and Federal agencies involved in the cleanup will provide a status report. The Adyisory Panel will also entertain public comment regarding the cleanup of TMI-2.

Persons or organizations desiring to comment during the Advisory Panel Meeting are asked to write to Mr. Joel Roth, 4705 Carlisle Pike, Mechanicsburg, PA 17055.

4 PdELIC l:EETIf!G:

The Advisory Panel for the Decontanination of Three flile Island Unit 2 will n.eet en July 28, 1983 from 7:00 PM to 10.00 PM in the Holiday Inn, 23 South Second Street, Harrisburg, Pennsylvania.

The meeting will be open to the public. The Panel will discuss TMI-2 cleanup activities. The TMI Unit 2 licensee and Federal agencies involved in the cleanup will provide a status report.

The Advisory Panel will also entertain public comment regarding the cleanup of TMI-2.

Persons or organizations desiring to comment during the Advisory Panel tieeting are asked to write to Mr. Joel Roth, 4705 Carlisle Pike, 14echanicsburg, PA 17055.

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APPEr: DIX 1 L10VID EFFLUENT DATA l

GPU Nuclear Based on sampling and monitoring, liquid effluents from the TMI site released to the Susquehanna River were determined to be within regulatory limits and in accordance with NRC requirements and the City of Lancaster Agreement.

During the period July 15, 1983, through July 21, 1983, the effluents contained no detectable radioactivity at the discharge point.

Individual effluent sources originating within Unit 2 contained minute amounts of radioactivity.

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Calculations indicate that less than 8.3 E-8 (0.00000008) of a curie of Cs-137 was discharged.

Environmental Protection Agency

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Lancaster Water Samples:

7 samples Period Covered:

June 26 - July 2, 1983 Results:

Gamma Scan Negative TMI Water Samples:

5 samples Period Covered:

July 1 - July 9, 1983 Results:

Gamma Scan Negative f

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l' APPENDIX 2 i

l ENVIRONMENTAL DATA

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EPA Environmental Data The EPA measures Kr-85 concentrations at several environmental monitoring l

stations and reported the following results:

s Location June 24, 1983 - July 8, 1983 3

(pCi/m)

Goldsboro 28 Middletown 25 Yorkhaven 30 TMI Observation Center 28 The EPA Middletown Office has not received the environmental Kr-85

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analytical results for the samples which were taken subsequent to July l

8,1983, from the EPA's Counting Laboratory at Las Vegas, Nevada.- these results will be included in a subsequent report.

No radiation above normally o'ccurring background levels was detected in any of the samples collected from the EPA's air and gamma rate ndw~orks during the period from July 12, 1983, through July 20, 1983.

I-NRC Environmental Data Results from NRC monitoring of the environment around the TMI site were as follows:

The following are the NRC air sample analytical results for the onsite continuous air sampler:

1-131 Cs-137 Sample Period (uCi/cc)

(uCi/cc)

HP-376 July 13, 1983 - July 20, 1983 <6.0 E-14

<6.0 E-14 e

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APPENDIX 3 SHIPMENTS RA010ACT!VE MATERIALS /RADI0 ACTIVE WASTE On July 21, 1983, 86 drums of contaminated laundry from Units 1 and 2 were shipped to Interstate Uniform Service, New Kensington, PA.

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APPEf4 DIX 4 WATER PROCESSIflG DATA 50bmerged Demineralizer System (SDS)

SDS was shutdown during the week.for maintenance.

EPICOR II LPICOR II was shutdown during the week.

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APPENDIX 5 PLANT PARAMETERS Core Cooling Mode:

Heat transfer from the reactor coolant system (RCS) to Reactor Building ambient.

Available Core Cooling Mode: Mini Decay Heat Removal (MDHR) system.

RCS Pressure Control Mode:

Standby Pressure Control System.

Major Parameters (as of 5:00 AM, July 22,1983)(approximatevalues)'

Average Incore Thermocouples*:

98*F*

Maximum Incore Thermocouple *:

118*F RCS Loop Temperatures:

A B

Hot Leg 94 F 93 F Cold Leg ((1) 81*F 79 F 2) 82 F 80*F RCS Pressure:

64 psig

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Reactor Building: Temperature:

81 F Pressure:

-0.3 psig Airborne Radionuclide Concentrations:

i 3.3 E-7 uC1/cc H3 (Tritium)

(sample taken 7/21/83) 1 2.6 E-9 uCi/cc particulates (predominately Cs-137)

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(sample taken 7/21/83) 4

• Uncertainties exist as to the exact location and accuracy of these readings.

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