ML19347C838

Quarterly Rept for Fourth Quarter of 1980

ML19347C838
Person / Time
Site:	Crane
Issue date:	01/14/1981
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML19347C837	List: ML19347C836 ML19347C838
References
NUDOCS 8103100051
Download: ML19347C838 (22)

Text

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QUARTERLY REPORT FOURTH QUARTER 1980

?.hree Mile Island - Unit 2 Docket No. 50-320 January 14, 1981 1

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TMI-2 Quarterly Report Fourth Quarter 1980 Part 1 SIGNIFICANT ACTIVITIES IN THIS QUARTER Data Acquisition Program (Entries)

The third containment entry was accomplished October 16, 1980.

Two major maintenance tasks were conducted. The first was the removal of the non-operational source range monitor and two vibration monitor preamps. The second was the repair of #1 Personnel Air Lock (inside equipment hatch).

These tasks vare performed by a 5 man entry team. A radiation survey of the exteriors of the Core Flood Tanks and the Cont =Inment Air Cooler was also performed.

The fourth containmen't entry was accomplished November 13, 1980.

Entry was conducted in three shifts. Tha first, a three-man team, video-taped the 305-foot level. The second, a six-man team (including an NRC representative video-taped the 347-foot level, moved the fuel handling bridge, and surveyed the top of the D-rings. The third, a three man team, conducted a decon-tamination test and took measurements for an interior containment lay-down area near the Personnel Air Lock.

The fifth containment entry was accomplished on December 11, 1980. The entry was conducted in two shifts with the second shift segmented to allow members to exit upon completion of their assigned tasks. The first team of four men conducted a hot spot survey of the 305' elevation. The second shift of ten men conducted the following activities:

1) hot, spot survey 347' elevation; 2) radiation survey of the reactor vessel head; 3) radiation survey and partial visual inspection of the polar crane; 4) photo survey and inspection;

5) decon tests using high and low pressure water and solution sprays.

Containment entries for data acquisition and maintenance tasks are scheduled to occur on a frequency of about one per month for the first quarter of 1981.

PURGES The practice of purging prior to each entry was continued. At this time, it appears that the krypton contained in air purged from the Containment Building in the future will be minimal as most of the krypton in the sump water and. Waste Gas Decay Tanks has been released.

" LOSS TO AMBIENT" TEST The planned test was carried out from November 6, 1980, to November 21, 1980. Tra system was returned to heat loss via the "A" OTSG on December 8, 1980. The test was successful. A report is being prepared as are procedures so the system can be returned to the " Loss to Ambient" cooling mode.

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2-SOLIDIFICATION OF EPICOR II LINER RESINS Specifications for a temporary solidification system for some 25-30 EPICOR II liners of low curie content were sent aut to ten (10) prospective bidders on December 5, 1980, and a bidders' meeting was held December 18, 1980.

A full-scale test of resin solidification with cement was run on i

November 12, 1980, by Hittman Nuclear and Development Cor,) oration.

Results did not fully meet test specifications as to b'mogeneity, and free standing liquid as shown by opening of the line and coring the contents. A report of this is being prepared.

EPICOR II OPERATION With the bulk of the waste water in the Fuel Handling and Auxiliary Building having been processed, need for continued operation of EPICOR II has been reduced. This condition, coupled with adequate available storage tankage in Unit 2, permitted a temporary suspension of operation of EPICOR II while discussions were held with the NRC on the appropriate ion cxchange medis for the prefilters for future continued operations.

EPICOR II PREFILTER LINER SAMDLING Unforeseen difficulties caused postponement of the planned December 19, 1980, sampling of the PF 16 liner until January, 1981.

AUXILIARY BUILDING DECONTAMINATION Reduction in manpower applied to Auxiliary Building decontamination has

-resulted in the effort being generally restricted to maintaining the status quo.

i GROUNDWATER MONITORING (Tritium)

The intensive monitoring program related to elevated tritium levels in groundwater near the BWST has been completed with the analytical data

- now being studied and a report written.

Routine monitoring continues.

CORK SEAL CONTAMINATION Contamination of cork seals-between the Auxiliary Building, Control Building, Service Building, and the Reactor Building was discovered on November 26, 1980. TLL 657,' dated December 15, 1980, provided a preliminary report on the contamination, including action already taken and plans for later action..An interim report was made to the NRC by TLL 678, dated

,t December 19, 1980. 'As stated in TLL 657, a follow-up report will be provided to the NRC by January 16, 1981.

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. LINER STORAGE MODULE SUMP CONTAMINATION Contamination has been found in both the interim and long-term liner storage modules. Analyses of samples have shown the presence of tritium at a very consistent, but low, concentration. Cesium was found at an extremely low level in one sample, but later analyses by two different laboratories showed none. The source of the contamination is not yet defined, but study is proceeding. Actions have been started to prevent 1

the entry of rain water in the long-term modules. An interim report is in preparation for submittal to the NRC.

MILESTONE ACTIVITIES ANTICIPATED FOR FIRST QUARTER OF 1981*

Activity Time Complete tie-ins from Chemical Clean-First half of January ing Building to Processed Water Storage Tanks Complete Borated Water Storage Tank Last half of January enclosure Start Interim Solid Waste Storage Last half of March i

Facility i

Tie in remote instrumentation to Last half of March Processed Water Storage Tanks It is anticipated that technical evaluation reports for the interim solid waste staging facility and the containment recovery services building will be submitted for NRC review during the first quarter in 1981.

• Dates shown for NRC planning purposes and may change. NRC will be informally notified of any change.

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TMI-2 Quarterly Report Fourth Quarter 1980 Part 2 Data Sheet 3 MO.

AS OF RANGE 12/31/80 Reactor Cooling System Pressure, psig.

88-99 93 Temperatures, OF '

Incore Thermocouples Average 143-121 122 Maximum 180-150 154 Hot Legs 137-118 118 Cold Legs 84-80 80 Reactor Building Temperature, oF 81-59 64 Sump water leval, ft. from floor 7.9-8.1 8.1 8

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-0.2 Pressure, psig.

Purges DATE DURATION, Min.

CURIES Kr-85 10/10/80 361 13.48 10/11/80 2

0 10/14/80 - 10/16/80 3,061 1.83 11/07/80 357 10.14 l

11/12/80 - 11/13/80 1,630 2.59 l

12/09/80 410 6

l 12/09/80 - 12/11/80 3,180 1.42 12/15/80 3

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l Liquid Discharges, total ci for period 0 from radwaste systems

• Entries-Longest Total Total time

Time, Man-hrs.

any man, Date Hours in Bldg.

Hours 10/16/80 1.5 5.5 1.5 11/13/80 3.0 13.6 1.5 12/11/80 3.2 19.6 2.0

• Very low concentrations of radionuclides have been found occasionally in the industrial. waste ' stream and sanitary waste.

Information on this is.being provided to the NRC. These concentrations in the TMI-2 Industrial Waste Stream are not detectable in' samples of the effluent stream from TMI prior to final discharge to the Susquehanna River.

. Water Processed - EPICOR II_

This quarter, gal., net 64,000 Total to date, gal., net 565,000 Water Inventory, gal.

As of 12/31/80 Contaminated - RCS 90,000 RB Sump 618,000 Auxiliary Building 11,200 Fuel Handling Building 0

Processed 645,000 Waste Inventory As of 12/31/80 EPICOR II, Prefilters No.

50 1st Demineralizer, No.

15 2nd Demineralizer, No.

7 Boxes, No.

4 15 LSA Drums, No.

162 Waste Shipments, this quarter As of 12/31/80 Boxes, No.

32 Drums, No.

46 Construction Status, % complete As of 12/31/80 SDS 70 Liner Module "C" 1

"D" 3

MDHRS 100 Processed water system Capability to transfer water from EPICOR II to the tanks 100*

Capability to recirculate, sample and transfer out of the tanks 0

• Temporary electric supply and only local controls now in use.

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, % chtel's site construction organization (30 persons) was completely demobilized during the month of October due to regulatory constraints to proceeding with the cleanup.

Engineering and other home office manpower was reduced from 140 to about 70 during that same period.

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Page 1 of 10 TMI-2, Qucrterly R: port Fourth Quarter 1980 Part 3 MANAGEMENT PT.AN PROGIESS Finoing Corrective Action Due Date Status

1. Management commitment

d. Implement a Radiation Protection 2 weeks after Submitted to NRC in January in support of Radiation Plan which outlines the philo-NRC action.

1980.

Comments generated were Snfety Program. (morale /

sophy, basic objectives, and addressed and incorporated attitude problem, policies relating to the into a revised plan.

This operations influence)

Radiological Control Program.

plan was approved by the President of GPU Nuclear and is currently awaiting distribution.

This action

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is considered complete.

f. Establish supervisory and December 1980 Selected members of the THI-2 management development Radiological Controls Mana m ;al/

training programs.

Supervisory staff have parti-cipated in management training seminars presented this year.

A Supervisory and Management Skills Training Program for all TMI-2 supervisory personnel has been developed by TMI Training.

The program consists of a one week classroon session and a guided home study program.

Although the above actions have been taken within Unit 2 a comprehensive supervisor /

management development program is being developed on the corporate level by Vice President, Quality Assurance.

3. Technical depth of

a. Initiate a recruiting program August 1980 for current conditions at IMI-2, Radiation Safety to reinforce the technical /

this action is considered Program.

supervisory expertise within complete.

the Radiological Controls Department..

• Aereiens previously identi fied an "comnlorn",rc en i n m,-

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4. Training (Training

c. Establish criteria for July 1980 The procedure establishing the for Radiation special training on "high criteria for special training Safety & Operations risk tasks".

on "high risk tasks" was P rsonnel was approved in December 1980 inadequate).

and is currently awaiting distribution.

Action complete.

6. Preparation and

a. Revise all Radiological implementation of Procedures compatible with procedures.

verbatim compliance objectlyes.

(1) Five (5) initial April 1,1980 To date, three (3) of the prccedure revisions five (5) procedures have been applicable to current approved and distributed, the activities.

remaining two (2) procedures have been approved and are awaiting distribution.

Action complete.

(2) Complete a Radiological December 1, 1980 There were approximately 80 Control Procedure Manual.

procedures originally scheduled for revision / generation.

With the exception of the procedure defining the program described in Item 7F below, all Radiological Control Procedures have been revised and have either been issued or are in the approval cycle.

Although the Radiological Control Procedures have been distributed and incorporated in the same manner as other TMI-2 procedures.

Segregation was achieved by reserving a procedure number block for the revised Radiological Controls procedures.

Paga 3 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

6. Continued

a. (2) Continued There is currently an intense effort to distribute the remaining 20 procedures.

Although these procedures are scheduled to be approved by December 31, 1980, it is not expected that all 20 will be implemented by December 31, 1980.

All procedures will be implemented by January 31, 1981.

Other priority efforts

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and failure to accomplish the technical specification change to expedite the procedure review cycle contributed to the delay in accomplishing this item fully.

b. Criteria for action August 1, 1980 Criteria incorporated in THI-2 sign off steps in work ALARA review program procedures.

procedures.

These procedures have been approved and are currently awaiting distribution.

c. Change tech specs to Open Requests for changes to expedite review.

Section 6.0 (Adminis-trative Controls) were submitted to the NRC in February, 1980 (TLL 037 and TLL 071).

By letter of November 25, 1980, the NRC advised that they had terminated their review of these requests.

Pag 2 4 ef 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

6. Continued

c. Continued Priority cf work on changes to Section 6.0, of the Tech. Specs. has been established to be consistent with other, related, efforts.

7. External Dosimetry

b. Evaluate TLD system and December 1, 1980 Based on post accident implement modifications.

experience with the current liarshaw 2-chip personnel dosimeter, it was decided that a new dosimetry system was needed.

This decision was made in December 1979.

The search for a new cystem revealed that only one system, Panasonic, was commericially available.

This systemwas used uninly for ganma dosinetry and environmental work, and its beta response had not been adequately studied. Two otlwr systems were being developed, one by the Department of Ihergy at Idaho Falls and a second by liarshaw Chemical Conpany.

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Page 5 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

7. Continued

b. Continued was necessary to evaluate the response of all three systems, particularly to beta radiation, prior to selecting one on the basis of the results, hardware design and availability.

Calibrated beta sources were necessary to accomplish an evaluation.

No sources of the quality and type needed were available in the United States in January 1980.

DOE-INEL had initiated procure-ment; however, the manufacturer was experiencing difficulty with making the sources.

Con-sequently, three beta sources suitable for precise dosimetry work were ordered from Amersham Corporation.

The sources were received in May 1980, and were then sent to the National Bureau of Standards for cali-bration.

The results of this

' calibration were received by Met-Ed/GPU at the end of July 1980.

Preliminary measurements were started on the Panasonic dosimeters using an off-site reader.

These measurements revealed that the filtration on the badge elements was not precisely suitable for our purposes, and also that the

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Page 7 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

7. Continued.

b. Continued available sanetime July 1981.

EG&G, Idaho has completed additional evaluations of the INEL badge and has more completely characterized the beta source in use at TMI with respect to dose rates and energy spectra. The results of this work were presented to GPU/ Met-Ed on December 12, 1980.

Panasonic has supplied Met-Ed/

GPU with a limited number of modified badges to a configu-ration more suitable for our purposes, and the loaner Panasonic reader was received at TMI about the first of December. The first group of Harshaw four-chip dosimeters were received on December 4, 1980.

Obtaining and setting up a Harshaw reader for this system has delayed completing the evaluation of this badge until the end of December.

It is anticipated that evaluatiol of the Harshaw and Panasonic systems will be completed by January 31, 1981 and that a management decision on which systen to adopt will be made by that time.

Page 8 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

7. Continued

f. Computerized exposure December 31, 1980 The computer capabilities to tracking by specific support an exposure tracking tasks.

program as defined by the original coninitment exists as a result of modifications made to the previously existing exposure records computer program.

Exposure tracking by specific tasks on other than a limited basis has not been achieved due to lack of a company-wide standardized coding systun for task description.

A coding system (COMEC) for organization and task descrip-tions has recently been developed and is expected to be implemented soon by corporate directive for financial tracking.

A proposed program will be submitted to Information System by January 31, 1981 atd the program written anI computer tested by May 1981.

This date is considered adequate to support scheduled opera-tioas.

The large number of.:omputer programs to be revised and developed has also contributed to the delay in accomplishing this item fully and a compre-I

Page 9 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS-Finding Corrective Action Due Date Status

7. Continued

f. Continued hensive program will be required before this item can be fully met.

9. Instrument Program

f. Implement improvements to June 1,1980 Action complete.

counting lab.

j. Implement an improved survey February 1,1980 Procedure approved, awaiting frequency schedule in distribution. Action complete.

procedural fonnat.

-12. Implement a program

a. Implement a Radiation NA See 1.d above which emphasizes the protection plan which reduction of personnel stresses TMI-II's exposures to ALARA.

commitment to a strong radiological control program within the concept of ALARA.

b. Implement a program for September 1,1980 See 7.f above exposure tracking.

c. Issue reports on exposure NA See 7.f above returas to supervision as 7.n aid in tracking exposure for their. personnel.

Page 10 of 10 TABLE 1 - MANAGEMENT PLAN PROGRESS Finding Corrective Action Due Date Status

13. Hold personnel account-

a. Delegate responsibility NA Program implemented in able for the actions for resolving audit findings February 1980.

Action complete.

they take.

Establish to supervisory personnel an understanding of responsible for the area responsibilitics and in which the finding occurs.

cxpectations associ-

-ated with achieving a sound Radiological Control Program.

b. Insert action sign off steps August 1, 1980 Criteria incorporated in TMI-Il in operational work procedures ALARA program procedures, to ensure proper attention is Action complete.

given to radiological con-siderations.

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TMI-2 Quarterly Report Fourth Quarter 1980 Part 4 TMI-II LICENSING CORRESPONDENCE TO THE NRC DATE TLL. NO.

SUBJECT 10/02/80 505 LER 80-043/03L-0 Auxiliary Building Ventila-tion System Inoperable 10/03/80 502 EPICOR II Resin Solidification Program 10/06/80 503 Disposal of EPICOR II Ion Exchange Media 10/07/80 483 TMI-2 Operators Training 10/07/80 499 IE Bulletin 80-18 Response 10/07/80 506 Combined Inspection Report 80-02 10/07/80 520 Idemnity Fee Payment 10/07/80 521 LER 80-040/03L-0 Late Submittal 10/09/80 395 Process Water Storage Tanks 10,v9/80 519 LER 80/040--Not reportable 10/09/80 526 LER 80-041/OlL-0 Incore Thermocouple M-9 failure 10/09/80 527 LER 80-042/03L-0 RCS Flow Instrumentation--

out of tolerance 10/13/80 478 Submerged Demineralizer System 10/13/80 510 Inspection Report 79-29 10/13/80 530 Rogovin Report References 10/15/80 528 TMI-2 Quarterly Report--3rd Quarter 10/16/8C 542 SDS System Description 10/17/80' 550 Late Letter for TLL 541--same subject 10/20/80 540 Emergency Preparedness

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10/20/80 544 EPICOR II First Stage Liner Sampling (meeting)

r-Pcg2 2 of 5 DATE TLL. NO.

SUBJECT 10/24/B0 548 Programmatic Environmental Impact Statement 10/27/80 555 LER 80-044/01L-0 PAL No. 1 Outer Door Excessive Seal Leaksge 1D/28/80 557 (in)

LER 80-49/IP Unauthorized ASME' Code Stamp Affixed to a Safety Relief Valve 10/29/80 561 LER 80-045/03L-0 Emergency Diesel Generator DF-X-1B failure to start 10/30/80 501 Recovery Quality Assurance Plan 10/30/80 552 RCS Water Chemistry and Corrosion Control 10/30/80 5'63 LER 80-046/01L-0 De-energized busses 2-38 and 2-48 10/31/80 535 License Amendment Request No. 1 10/31/80 565 Termination of Senior Reactor Operator License 10/31/80 567 IE Bulletin-revision of complet?.on date 10/31/80 568 MDHR System Description, Revision 4 4

10/31/80 569 LER 80-035/03L-0 BOP Diesel Generator (white)

Failure of U.V. Radiation Detector 11/03/80 572 Response to Inspection Report 80-11 11/04/80 541 Contingency Plan for Tran.=fai and Storage of Reactor Containment Pailding Sump Water i

11/05/80 536 Reserve Waste Water Tankage 11/07/80 578 Programmatic Environmental Impact Statement 11/11/80 577 TMI-2 Recovery--Licensing Plan i

11/13/80 589 Inspection Report 50-320/80-11 11/13/30 587 Programmatic Environmental Impact Statement 11/14/80 592 EPICOR II Liner Metallurgical Evaluation 11/14/80 594

.PEIS Comments--Revision to page 2 11/14/80 596 Status on Proprietary Documents k

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SUBJECT 11/17/80 545 EPICOR II Resin Solidification Procurement 11/17/80 606 LER 80-047/03L-0 PAL No. 2 Inner Door Excessive Seal Leakage 11/17/80 607 LER 80-52/1P PAL No. 2 Inner Door Excessive Seal Leakage 11/17/80 608 LER 80-53/IP Incore Thermocouples Failure 11/17/80 609 LER 80-048/03L-0 Failure of Containment Isolation Valve of-V115 11/18/80 611 LER 80-53/IP--Corrective Lette-11/19/80 580 Service Distribution List 11/20/80 616 Programmatic Environmental Impact Statement 11/21/80 604 Disposal of EPICOR II and Low Level Activity SDS Low Exchange Media 11/24/80 623 EPICOR II Liner Metallurgical Evaluation 11/25/80 624 LER 80-049/01L-0 Unauthorized ASME Code Stamp affixed to a Safety Relief Valve 11/26/80 590 NRC Project Approval 11/26/80 626 IE Bulletin 80-10 (late letter) 11/26/80 627 PEIS Comments 11/31/80 553 Rogovin Report References l

12/02/80 629 Submerged Demineralizer System 12/03/80 636 Licensed Transport Casks 12/04/80 593 Emergency Drill 12/04/80 o19 Interim Solid Waste Storage Facility 12/04/80 632 Submerged Demineralizer System 12/04/80 633 Loss to Ambient Test Results 12[04/80 634 EPICOR II Liner Metallurgical. Evaluation Sectus 12/04/80 638 EPICOR II Operations 12/04/80 639 Submerged Demineralizer System

Page. 4 of 5 DATE T L. 30 SUBJECT 12/08/80 646 LER 80-050/01L-0 Ir ore Thermocouple H-9 failure 12/09/80 645 Recovery Operations Plan, Surveillance

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Requirements Relief Request 12/10/80 653 Reactor Decay Heat Removal 12/11/80 641 EPICOR II Liner Evaluation Status 12/11/80 644 Programmatic Environmental Impact Statement 12/11/80 652 LER 80-051/03L-0 Deficient Fire Barrier Seal 12/12/80 658 IE Bulletin 80-23 12/15/80 649 Written and Oral Examinations 12/15/80 657 Cork Seal Contamination Report 12/15/80 659 LER 80-052/01L-0 PAL No. 2 inner door excessive seal leakage 12/15/80 660 Investigation 50-320/79-10 12/15/80 662 Programmatic Environmental Impact Statement 12/15/80 666 Methodology for Calculations of Integrated Dose 12/16/80 665 IE Bulletin 80-10 12/17/80 608 LER 80-53/1L-Incore Thermocouples N-8/

N-9 failure 12/17/80 669 Licensee Event Report 80-053/01L-0 Incore Thermocouples N-8/N-9 failure 12/18/80 664 Corrections to Programmatic Environmental Impact 12/18/80 674 LER 80-054/031-0 Emergency System Diesel Generator DF-X-1B failure to start 12/18/80 676 Radioactive Materials Shipping Cask 12/18/80 677 Licensed Transport Casks (Personnel Change) 12/19/80 579 Written and oral Examinations

Peg 2 5 of 5 DATE TLL. NO.

SUBJECT 12/19/80 678 Cork Seal Contamination Report 12/19/80 683 Resin Solidification Requirements 4 -

12/23/80 684 Design Criteria for the Modification for l

Closure of Reactor Building Penetration 12/23/80 688-Invescigatior 50-320/79-10 (late letter) k2/24/80 687 LER 80-055/03L-0 Emergency Diesel Generator DF-X-1B failure to start 12/29/80 682 IE Bulletin 80-21 9

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