IR 05000729/2008004

Submits TMI Program Ofc Weekly Status Rept for Wk of 850729-0804

ML20133N788
Person / Time
Site:	Three Mile Island, 05000729
Issue date:	08/05/1985
From:	Travers W Office of Nuclear Reactor Regulation
To:	Harold Denton, Snyder B Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-85-056, CON-NRC-TMI-85-56 NUDOCS 8508130629
Download: ML20133N788 (5)

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i August 5, 1935 flRC/Tl!I-85-056

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itEMORAllDUM FOR: llarold R. Denton, Director Office of fluclear Reactor Regulation Bernard J. Snyder, Program Director TH1 Program Office FROM: William D. Travers, Deputy Program Director THI Program Office SUBJECT: llRC T111 PROGRAM 0FFICE WEEKLY STATUS REPORT FOR JULY 29, 1985 - AUGUST 4, 1985 t

J PLAllT STATUS l -

The facility remains in long term cold shutdown with the Reactor

. Coolant System (RCS) vented to the reactor building atmosphere and

] the reactor vessel head and plenum assembly removed from the reactor e

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. vesse The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallcw ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top

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of the plenum).

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The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151

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feet above the top of the core region).

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Calculated reactor decay heat is less than 12 kilowatt RCS cooling is by natural heat loss to the reactor building ambient atmospher Incore thennocouple readings range from 71*F to 90*F with an average of 80*F. Average cold leg temperature is 57' The average reactor building temperature is 59'F. The reactor building airborne activity is 2.6 E-9 uC1/cc Tritium and 3.4 E-10 uCi/cc particulate, predominantly Cesium 13 . WASTE IWlAGEMEllT

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The Submerged Demineralizer System (SDS) and EPICOR II were shutdown /

this perio n

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Total volume processed through SDS to date is 2,963,375 gallons, and /

the total voluae processed through EPICOR II is 2,547,671 gallon p) M,

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Harold R. Denton 2 August 5, 1985 Bernard J. Snyder NRC/TMI-85-056 _ DOSE REDUCTION / DECONTAMINATION ACTIVITIES

- Decontamination activities are continuing on the 281' level of the Auxiliary Buildin Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building. The change in radiation levels from previous reports is the result of a change in the manner in which the average radiation level is determined. The averages are now based on occupancy time-weighting of tasks accomplished in the reactor building as opposed to the previous method of averaging survey meter readings. The new values are based on an attempt to report radiation levels representative of those to which workers are actually expose . ENVIRONMENTAL MONITORING

- EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreemen TMI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from July 13, to July 20, 1985. Gamma scans detected no reactor related radioactivit The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consists of a seven day composite sample taken from July 21 to July 28, 1985. A gamma scan detected no reactor related radioactivit The NRC outdoor airborne particulate sampler at the TMI Site

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collected a sample between July 25, and July 31, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectabilit . REACTOR BUILDING ACTIVITIES

- Installation of the rotating work platform and service platform continued over the reactor vesse Equipment was staged into the reactor building and installation began on the cable management syste Work continued in support of installation of the reactor building service platform jib crane Loop calibration of DWCS instrumentation and final preparations for system preoperational testing continued this wee . AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES

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Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is scheduled to be completed in late Augus The first of four fuel canister rach. are on site with further celiverier schedclec' thrcugP Augus _ _ - _ _ _

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Harold R. Denton 3 August 5, 1985 Bernard J. Snyder NRC/Tl1I-85-056 TMI-2 OCCUPATIONAL DOSE

- Total person-rem for January through June 1985 is 398. Total for March 1979 through June 1985 is 2,417 person-re . SHIPMENTS DURING JULY 1985

- Shipments of contaminated laundry were made to Royersford, PA on:

July 3 - 66 drums, 2 boxes July 16 - 112 drums, 2 boxes July 24 - 63 drums, 3 boxes July 31 -

68 boxes

- July 2 - Liquid samples (Unit 1) to San Jose, Californi July 2 - Liquid samples (Unit 1) to Rockville, Marylan July 3 - Electrical equipment samples (Unit 2) to Richland, Washingto July 3 - Electrical equipment samples (Unit 2) to Scoville, Idah July 5 - Liquid samples (Unit 1) to Rockville, Marylan July 18 - Three solidified resin liners (Unit 1) to Hanford, Washingto July 18 - 104 drums (Unit 1 and 2) compacted and non-compacted waste to Hanford, Washingto July 26 - 28 Boxes of uncompacted shield blocks to Hanford, Washingto . NRC EVALUATIONS IN PROGRESS

- Defueling Water Cleanup System Technical Evaluation (including Revision 6).

- Technical Specification Change Requests numbers 46, 48, 49, and 5 Recovery Operations Plan Change numbers 27, 29, 31, and 3 Fuel Canister Technical Evaluatio Fuel Handling Senior Reactor Operator Training Program .

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Defueling Safety Evaluatio Application for seismic exemptio The NRC Vendor Programs Branch performed an inspection at the Nuclear Energy Services (NES) facility in Greensboro, North Carolina, where the fuel storage canisters, fuel storage rzcks, and fuel canister transfer shields are being fabricated. The inspection examined construction activities and included a review of the implementation of the quality assurance program at NE The inspection report, issued July 26, 1985, indicates that NES failed to meet certain NRC requirements related to implementation of its quality assurance program. NES is required to submit (1) a description of steps that have been or will be taken to correct

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those items identified in the report; (2) a description of the steps that have been or will be taken to prevent recurrence; and (3) the dates that the corrective actions and preventive measures were or will be complete . PROJECTED SCHEDULE OF FUTURE EVENTS

- Mar cf Sciueim;: 0 :re- 19EE

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Harold R. Denton 4 August 5, 1985 Bernard J. Snyder NRC/TMI-85-056 11. PUBLIC MEETING The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 1985 at a location in Annapolis, Maryland, the specific date and location will be identified late I &

4 O_0 3 +w a < W William D. Travers Deputy Program Director TM1 Program Office

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Harold R. Denton 5 August 5, 1985 Bernard J. Snyder NRC/THI-85-056 INTERNAL DISTRIBUTION EDO OGC Offico Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS TMI Program Office Staff (10)

PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI TMIPO HQ r/f

THI SITE r/f CENTRAL FILE 7; NRC PDR LOCAL PDR

. THI-2 Project Section File

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