ML20205A956

Annual Rept for Decommissioned Facility for Jul 1985 - June 1986

ML20205A956
Person / Time
Site:	Fermi
Issue date:	06/30/1986
From:	Drouillard R, Griffing E, Lenart R DETROIT EDISON CO.
To:	Zwolinoki J, Zwolinski J NRC
References
EF-132, NP-86-0291, NP-86-291, NUDOCS 8608110488
Download: ML20205A956 (11)

Text

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THE DE71POIT EDISON COMPANY Enrico Fermi Unit I Decarmissioned Atanic Power Plant Docket No. 50-_16 License No. DPR-9 Report for Year beginning July 1, 1985 and ending June 30, 1986 EF-132 Prepared by: bsWfl H/ lbte: 7,f29 fab

' Michard C.'Drouillard Custodian Delegate Approved by: / __

Date: 7!f/

[_ _

l Robert S. Lenart Custodian l Approved by: @ _'_ / (b--@ ate: ~/ S o E b U

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l Edward P. Griffing' #

Chairmati, Review Ccanittee I

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81h p R

i a

TARrR OF CONTINPS h

Page I. PREFAG............................................ 1 II. RETIREMENP STA'IUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Pri.Try System................................ 1 Soditan Storage Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Administrative and Surveillance Procedures.................................... 1 III. HE.WHI PHYSI CS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Personnel Exposure............................ 1 Environmental Surveys......................... 2 IV. PERIODIC TEST ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Weekly Test and Inspections................... 2 Water Intrusion Alarm................... 2 Monthly Inspections. . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Controlled Area Inspections............. 2 Quarte rly Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Smear Surveys............................ 2 Reactor Building. . . . . . . . . . . . . . . . . . . . 3 Fuel and Repair Building............ 3 Semi-Annual Tests............................ 3 Water Intrusion Alarms.................. 3 Raw Water Beta Activity................. 4 Sediment Gansna Activity. . . . . . . . . . . . . . . . . 5 Carbon Dioxide Cover Gas Pressure....... 6 1

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TABLE OF CONIDES Page Annual Tests........................... 6 Carbon Dioxide Cover Gas Pressure Relief Valve...................... 6 V. REW EW CCNMITTEE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 List of Members................................... 6 Audit Subccuraittee. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 VI. NOIDORIHY ITENS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Site Survey.......................................... 6 MK 7-8-9-15 Liquid Waste Tank Levels................. 7 Reactor Building..................................... 7 Fermi I Licenm Extension. . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 l

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7 PREPACE This annual report is issued by the Detroit Edison Company in conpliance with the provisions of the United States Nuclear Regulatory Commission, Provisional Operating licenm No. DPR-9, as amended, and is intended to provide a stamary of the status and events at the deconmissioned Enrico Fermi Atomic Power Plant during the past twelve (12) months.

II RETIREMENT SPNIUS Primary System The primary system, established during deconmissioning, and consisting of the reactor vessel, primary sodi m piping, primary shield tank, machinery dome, primary sodium service systs and secondary soditun systen extending out to welded pipe caps remains blanketed with carbon dioxide. This was done to pro;ide a passivating atmosphere for any soditan remains. A continuous supply of carbon dioxide maintains this cover gas at approxi-mately 2 inches of water coltmn pressure.

Sodium Storage _Tpnks During the final quarter of 1984, 1344 drums of primary sodium were shipped to Argonne National Laboratory - West. A 1 to 5 psig Carbon Dioxide cover gas is maintained on the 3 drained primary Sodium Storage Tanks.

A#ni.ni_strative and Surve_il_1pnce Procedures Tabulations in Section VII of the detailed Inspection, Surveillance operating and Reporting Procedures were modified to reflect personnel changes at Enrico Fermi I.

III HEAUIE PHYSICS Personnel Expo _s_ur,e An average of seventy '(70) thermoltuninescent dosimeters were processed monthly. None indicated an exposure greater than 10 mRen.

Enviannuant.al Surveys A total of twenty (20) environmental sample analyses of rm surface water, raw city water and sediment was reported during this period. Sanple

- analyses covered the period from June,1985 through June,1986.

Anomalous high values were obtained for Cobalt-60 and Celi m-137 in the Reactor Channel sanple collected April 24, 1986. An analysis was performed l on an aliquot of the sample with similar values. No Cobalt-60 was found in sanples taken up stream in the Reactor Channel for the Fermi 2 environmental survey of the same period. These values are given in the Periodic Test Activities,Section IV.

Sediment re-sanpling was conducted at the original spot and three other locations upstream on June 13, 1986. Results of the analyses for these samples were negative for Co-60 and are added to the previous values in Section IV.

Other than Cs-137, no other man-made isotopes were detected in sediment. l' As previously indicated, since it is present in global fallout, the occasional detection of Cs-137 in environmental media at the concentrations we reported is not unusual.

l Thus, the evidence available to us indicates that the CO-60 activity l reported to us could have resulted from sanple cont aination, but was not a consequence of discharges from the Fermi couplex.

IV Periodic Test Activities Weekly Tests and inspections

1. Water Intrusion Alarm - Continuity tests of the water intrusion alarm circuits for FARB, lower Reactor Building and biological shield wall areas, were conducted as required by Technical Specification. No discrepancies were encountered during this reporting period.

Monthly Inspect _i_on_s j 1. Controlled Area Inspections - Visual inspection of fence, gates, bors (locked), operation of waste sunp punp and liquid levels

. of MK 7-8-9 and 15'in the FARB were conducted within specified

. intervals.- No discrepancies were found during this report period.

i Quarterly Tests

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1. Smea_r_ Surveys - The Reactor Building and FARB were checked for presence of gansna radiation and transferable contamination. The results of these smear surveys indicated no decontamination procedures were required.

4 1 .

+m'e-- r --w-- - - - - - - - - - -++.--w-re-wrre+-m --r m w. c ewww r--we-e=-ws>= m --m we emm

• e w-+-e ee w o n e e -e . e w w- w -e t + w- e we r + w-- w e+w - op -m-w--w+w++w-'

- - Typical Snear Test V91ues in dun /100cm2 Date REACIOR BUILDING 09/18/85 All Snears < 1000 12/11/85 All Snears < 1000 03/10/86 All Snears < 1000 05/20/86 All Snears < 1000 Date FUEL AND REPAIR BUILDING (FARB) 09/18/85 - All Scears ~ ' ~ ~--- - < 1000 12/11/85 All Snears < 1000 03/10/86 All Snears < 1000 05/15 to 29/86 All Snears < 1000 Seal-Annual Tests Water Intrusion Alarms - Both of the required semi-annual functional tests of the water intrusion detectors in the FARB, lower Reactor Building and biological shield wall were conducted; one on 11/13/85 and the other on 6/3/86. No discrepancies were found.

Environnental Surveys Raw Water Beta Activity Sedinent Ganuna Activity

- - Results of the analyses for gross bets on seven (7) water sanples.

Gross Beta Sample Descript_i_og Lab Code. (DCi/L)

Drinking Water Inlet, EF-1 9/29/85 SPW-1763 3.110.8 S. Lagoon 9/29/85 1764 2.4+0.7 Monroe Drinking Water 9/29/85 1765 2.210.7 Detroit Drinking water 9/29/85 1766 2.010.6 Reactor Chan. Water 9/25/85 1767 2.510.6 Swan Creek Water 9/25/85 1768 4.811.2 Lake Water 9/29/85 1778 2.710.7 The error given is the probable counting error at 95% confidence level.

Date Gross Beta Location Collected Lab Code (pCi/L)

City of Detroit (BW) 04-21-86 SPW-2267 <2.2 City of Monroe (RCW) 04-22-86 2268 <2.2 Fermi 1 Water Plant (LW) 04-22-86 2269 3.211.3 South Lagoon (BN) 04-23-86 2270 <2.3 Swan Creek (RW) 04-24-86 2271 2.811.3 Lake Erie Intake Canal (LW) 04-22-86 2272 2.8 1.3 Reactor Channel 04-24-86 2273 3.0il.3 The error given is the probable counting error at 95% confidence level.

Less than values (<) are based on 4.66 sigma counting error for back-ground I

sanple.

(RW) - Raw Water (LW) - Lake Water (RG) - Raw City Water

SEDIMENT GN9tA ACPIVI_TY Sanple description and Activity (pCi/kg dry weight)

Sample Description S. Creek Reactor Channel S. Lagoon Fermi Site Lab Code SPS-1769 SPS-1770 SPS-1771 Collection Date 09-25-85 09-25-85 09-29-85 Units pCi/kg (dry) pCi/kg (dry) pCi/kg (dry)

K-40 86101477 176001391 9304i262 Mn-54 <23.9 <34.1 <24.8 Co-58 <29.3 <41.9 <31.8 Co-60 <23.5 <33.5 <23.4 Zn-65 <77.2 <92.7 <55.1 Nb-95 <48.8 <59.4 <34.6 Cs-134 <33.3 <41.0 <26.9 Cs-137 <22.4 182.7116.0 <24.3 The error given is the probable counting error at 95% confidence level.

Less than values (<) are based on 4.66 sigma counting error for back-ground sanple.

Sample Description and Concentration (pCi/kg dry weight)

Location South Lagoon Reactor Channel Swan Creek Date Collected 04-22-86 04-24-86 04-24-86 Lab Code SPS-2274 SPS-2275 SPS-2276 K-40 132001204 14510i278 8254195 Mn-54 <18.7 <26.8 <7.7 Fe-59 <68.3 <90.0 22.7 Co-58 <21.3 <29.3 <7.5 Co-60 <18.8 63.8ill.2 <7.8 Zn-65 <48.2 <68.7 <21.0 Zr-Nb-95 <26.3 <35.2 <8.6 Cs-134 <22.1 <32.6 <8.6 Cs-137 <17.8 932122 2513 l

- Below are the results of the analyses for ganna-emitting isotopes on four (4) sediment sanples collected June 13, 1986, Fermi-1 program.

Sample _Descriptionand_ Concentration (DCi/kadrf_weighil__

Reactor Reactor Reactor Location Channel Channel Channel Overflow End Midway Culvert Canal Lab Code SPS-2479 SPS-2480 SPS-2481 SPS-2482 K-40 14750i381 1790011020 <792.7 123001865 Mn-54 <22.8 <55.7 <22.6 <55.4 Fe-59 <69.4 <135.0 <70.0 <122.0 00-58 <22.0 <52.4 <24.5 <56.2 Co-60 <27.4 <52.3 <25.6 <51.9 Zn-65 <66.8 <149.0 <60.1 <l50.0 Zr-Nb-95 <24.7 <62.3 <23.8 <58.2 Cs-134 <34.4 <66.7 <36.0 <64.3 Cs-137 699125 483150 364120 556iS6 The error given is the probable counting error at 95% confidence level. Less than (<) values are based on 4.66 sigma counting error for background sanple.

Carbon Dioxide Cover Gas Pressure The semi-annual test of the Hi and Lo Pressure alarm settings were success-fully coupleted on 11/22/85 and 5/13/86. Set points were within the limits established and no adjustments were required.

Annual Test.s Qrbon Dioxide Cover Gas Pressure Relief Valve The annual test of the carbon dioxide cover gas pressure relief valve setting was successfully completed on 6/2/86. The relief actuation occurred at 4.6 PSIG.

V Review Comnittee Members of the Revi_ew C_ogn_iltee E. P. Griffing - Chairman R. S. Lenart - Custodian W. T. Maveal J. E. Meyers M. A. Nelson E. H. Newton E. M. Page R. G. Rateick N. M. Ewbank J. P. Bobba W. D. Gilbert R. C. Drouillard

• • *- The ccanittee et on July 2,1986. Formal minut:s of these neetings are on file.

Audit Subcognitt;ee Present members of the Audit Subcumittee are: Mr. M. A. Nelson and Mr. E. M. Page. The subcomittee met at the facility on January 1,1986 and June 13, 1986, for inspection of the facility and review of records and procedures. Memorandums containing their findings are on file. The Review Comittee reviewed the findings of the sub Comittee Audit, and the comittee meeting minutes are on fil?.

VI Noteworthy Items Site Survey A couplete radiological survey and estimates of radionuclide inventory, and collection of exposure data over the last 13 years have been completed in response to an NFC request for additional information.

Slightly radioactive steam by-pass pipe frcxn Fermi 2 was cut up, sealed and stored in the FARB repair pit for decay to background. Because of the low background and lack of contamination, the FARB machine shop was converted to a thermo--luminescent dosimeter irradiator facility.

MK 7-8-9-15 Liquid Was_t_e_T_ank__Leyels The ground area west of the Fuel and Repair Building was covered with concrete and the old laundry pit near the Health Physics Building slab has been filled with cement. Since this has been completed in late August, 1984, there has been no increase in the MK 7-8-9 and 15 tank levels.

Reactor Buildi_ng The smoke detectors in the Reactor Building were checked.

Fermi I License Extension The Detroit Edison request for a forty (40) year licenm extension is under review by the NRC.

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"A Detroit r- -

Edison EiIE *#

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July 31, 1986 IT-86-0291 Director of Nuclear Reactor Regulation Attention: Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing Nuclear Pegulatory Caraission Washington, D.C. 20555

Reference:

Fermi I NRC Docket No. 50-16 IBC License No. DPR-9

Subject:

Enrico Femi I Decommissioned Atomic Power _ Plant, Annual _Repo_r_t

Dear Mr. Zwolinski:

Pursuant to Section I.8 (Reporting Requirenents) of the Technical Specifications for teendnent 8 to Provisional Operating License No.

DPR-9, enclosed are ten copies of Report EF-132 for the year ending June 30, 1986 for the deccmissioned Enrico Fermi Unit I Atanic Power Plant.

Yours Very Truly, A

b <c Robert S. Lenart Custodian Enrico Fermi I Decommissioned Plant RSL/kal cc: Mr. W. A. Rogers Mr. P. B. Erickson Mr. J. Eckert (Monroe County OCP)

Mr. D. Hahn (State Health Department)

USNRC Document Control Desk Washington, D.C. 20555 hO IIe

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