ML20133H121: Difference between revisions
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Reactor Building on June 22, 1985 the smoke detectors in the Reactor Building were checked. | Reactor Building on June 22, 1985 the smoke detectors in the Reactor Building were checked. | ||
All 4 cable tray detectors were operational. | All 4 cable tray detectors were operational. | ||
Fermi I License extension The current Fermi I license expires on June 30, 1985. In a letter dated May 17, 1985 Detroit Edison has requested that the license be extended 40 years. | Fermi I License extension The current Fermi I license expires on June 30, 1985. In a {{letter dated|date=May 17, 1985|text=letter dated May 17, 1985}} Detroit Edison has requested that the license be extended 40 years. | ||
100/R101/7.10 072585 | 100/R101/7.10 072585 | ||
Latest revision as of 01:19, 10 August 2022
ML20133H121 | |
Person / Time | |
---|---|
Site: | Fermi ![]() |
Issue date: | 06/30/1985 |
From: | Griffing E, Lenart R, Maveal W DETROIT EDISON CO. |
To: | Zwolinski J Office of Nuclear Reactor Regulation |
References | |
EF-131, NP-85-838, NUDOCS 8508090198 | |
Download: ML20133H121 (12) | |
Text
__ -
3
. THE DETROIT EDISON COMPANY
! Enrico Fermi Unit I Decommissioned r l
l i Atomic Power Plant Docket No. 50-16 l
i License No. DPR-9 4
I j Report for i
i Year beginning July 1, 1984 and ending June 30, 1985 i
EF-131 l
l Prepared by: / luf%L
/
[ /Yl2Uf Wayne T. Maveal Date: 9-Jd'25
' Custodian Delegate i
Approved by: k. (vd k MSC Dates f ~ /"N i Robert S. Lenartf .
j Custodian Approved by:
Date:
V Edward P.' Grif f fng i
l Chairman, Review Committee i
100/R101/7.1 ;
072585 j 8500090198 850630 %@Y '
j (DR ADOCK 05000016 eor ,ja
TABLE OF CONTENTS Page
- 1. PREFACE.......................................... 1 II. RETIREMENT STATUS................................ 1 P rima ry Sy s t em . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Primary Sodium Storage...................... 1 Administrative and Surveillance Procedures.................................. 1 III. HEALTH PHYSICS................................... 1 Personnel Exposure.......................... 1 Environmental Surveys....................... 2 IV. PERIODIC TEST ACTIVITIES......................... 2 Weekly Test and Inspections................. 2 Wa te r In t rusion Ala rm. . . . . . . . . . . . . . . . . . 2 Sodium................................. 2 Monthly Inspections......................... 2 Controlled Area Inspections............ 2 Quarterly Test.............................. 2 Smear Surveys.......................... 2 Reactor Building.................. 3 Fuel and Repair Building.......... 3 Semi-Annual Tests........................... 3 Wa te r Int rusion Ala rms . . . . . . . . . . . . . . . . . 3 Raw Water Beta Activity................ 4 Sediment Gamma Ac t ivity. . . . . . . . . . . . . . . . 5 Carbon Dioxide Cover Cas Pressure. . . . . . 6 100/R101/7.2 061385
TABLE OF CONTENTS Page 2 Page Annual Tests................................ 6 Carbon Dioxide Cover Gas Pressure Relief Valve........................... 6 V. REVIEW COMMITTEE................................. 6 List of Members............................. 6 Audit Subcommittee.......................... 6 VI. NOTEWORTHY ITEMS................................. 6 i
Sodium Familiarization........................... 6 MK 7-8-9-15 Liquid Was te Tank Levels . . . . . . . . . . . . . 7 Input from NRC/ Fermi 1 Annual Report............. 7 f
a 1
f 100/R101/7.3 072484
I PREFACE This annual report is issued by the Detroit Edison Company in compliance with the provisions of the United States Nuclear Regulatory Commission, Provisional Operating License No. DPR-9, as amended, and is intended to provide a summary of the status and events at the decommissioned Enrico Fermi Atomic Power Plant during the past twelve (12) months.
II RETIREMENT STATUS Primary System The primary system, established during decommissioning, and consisting of the reactor vessel, primary sodium piping, primary shield tank, machinery dome, primary sodium service system and secondary sodium system extending out to welded pipe caps remains blanketed with carbon dioxide. This was done to provide a passivating atmosphere for any sodium that remains. A continuous supply of carbon dioxide maintains this cover gas at approxi-mately 2 inches of water column pressure.
Primary Sodium Storage During the period of October 29, 1984 to November 12, 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 primary Sodium Storage tanks.
Administrative and Surveillance Procedures Sections VI and VII of the Detailed Inspection, Surveillance, Operating and Reporting Procedures were reviewed and updated as follows: Since the ship-l ment of the 1344 drums of Primary Sodium to Argonne National Laboratories -
l West on November 12, 1984, the weekly surveillance procedure to inspect the l Primary Sodium storage drums and the quarterly surveillance procedure to l perform the smear survey of the Primary Sodium drum storage area has been i discontinued.Section VII, Tables 3 through 5 were changed to reflect j personnel changes at Enrico Fermi I.
l III j HEALTH PHYSICS Personnel Exposure There are seventy-one (71) thermoluminascent dosimeters processed monthly.
Records indicate no exposures greater than 10 MREM.
1 i
_1 i
100/R101/7.4 072585
Environmental Surveys A total of twenty (20) environmental sample analysis of raw surface water, raw city water and sediment were reported during this period. Sample analysis covered the period from June,1984 through June,1985. The results of these samples were within the normal range experienced in the past. These values are given in the Periodic Test Activities,Section IV.
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. L
- 2. Sodium - On November 12, 1984 the last of 1344 drums of Primary Sodium were shipped to Argonne National Laboratories - West. The surveillance of inspecting the drums for leakage was discontinued.
Monthly Inspections
- 1. Controlled Area Inspections - Visual inspection of fence, gates, doors (locked), operation of sump pump and liquid level of MK 7-8-9 and 15 in the FARB were conducted within specified intervals. No discre-pancies were found during this reporting period.
Quarterly Tests
- 1. Smear Surveys - The Reactor Building and FARB were checked for ,
presence of gamma radiation and transferable contamination. The l results of these smear surveys indicated no decontamination procedures were required.
I 100/R101/7.5 072585
Typical Smear Test Values in dpm/100cm2 Date REACTOR BUILDING 09/11/84 All Smears < 1000 12/15/84 All Smears < 1000 03/14/85 All Smears < 1000 J 06/11/85 All Smears < 1000 Date FUEL AND REPAIR BUILDING (FARB) 09/11/84 All Smears < 1000 12/15/84 All Smears < 1000 03/14/85 All Smears < 1000 6/11/85 All Smears < 1000 Semi-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 12/16/84 and the other on 5/19/85. No discrepancies were found.
Environmental Surveys Raw Water Beta Activity Sediment Gamma Activity i
l 100/R101/7.6 072485
RAW WATER GAMMA ACTIVITY Cross Beta Date Location Lab Code (pCi/1)
\
9/22/84 So. Lagoon-Fermi (RW) SPW-1356 < 2.9 9/22/84 Water Plsnt (LW) -1358 < 2.9 9/22/84 Intake" Canal (RCW) -1359 < 2.9 9/22/84 Monroe-Intake (RCW) -1360 < 2.9 9/22/84 Detroit City Water (RW) -1361 < 2.9 9/25/84 Swan Creek (RCW) -1357 < 2.9 9/25/84 Reactor Channel '
-1362 < 2.9 Less than (L.T.) values are based on 4.66 sigma error for background sample.
4/11/85 So. Lagoon SPW-1598 3.1 + 1.4 4/11/85 Fermi.11 Water, Plant -1599 2.2][1.3 4/11/85 Monroe Intake -1600 2.6 + 1.3 4/11/85 Detroit Water Intake -1601 3.07: 1.3 4/11/85 S. Creek Ind. (1500) -1602 4.1 i: 1.4 4/11/85 S. Creek Ind. (1530) -1603 3 . 5 I: 1.4 4/11/85 EF-2 Intake -1604 2.7][1.3 The error given is the probable counting error at 95% confidence level.
(RW) - Raw Water (LW) - Lake Water (RCW) - Raw City Water 4
s 100/R101/7.7 072585
l SEDIMENT CAMMA ACTIVITY Sample Description and Activity (pCi/kg dry weight)
Sample Description South Lagoon Reactor Channel Swan Creek Date Collected 9-22-84 9-25-84 9-25-84 Lab Code SPS-1365 SPS-1364 SPS-1363 K-40 9740 + 636 13600 + 827 6660 + 502 Mn-54 <- 31 < 45 < 24 Co-58 < 42 < 56 < 36 Co-60 < 31 < 43 <-26 Zn-65 < 112 < 138 < 84 Zr-95 < 80 < 102 < 62 Nb-95 < 60 < 79 < 46 Cs-134 < 41 < 59 < 30 Cs-137 < 28 166 + 33 < 23 Sample Description South Lagoon S. Creek S. Creek Lab Code SPW-1597 SPW-1595 SPW-1596 Date Collected 4-5-85 at 1110 4-8-85 at 1515 4-8-85 at 1545 Units (pCi/kg)-
K-40 13100 + 560 9300 + 495 14900 + 583 Mn-54 < 27.2 < 24.6 -< 33.5 Co-58 < 29.5 < 25.5 < 34.4 Co-60 < 26.5 < 24.0 < 34.7 Zn-65 < 94.9 < 71.8 < 118.0 Nb-95 < 34.5 < 29.8 < 45.0 Cs-134 < 36.8 < 27.0 < 46 6 Cs-137 < 25.8 < 21.1 212 + 26.7 The error given is the probable counting error at 95% confidence level. Less the (L.T.) values are based on 4.66 sigma counting error for background sample.
100/R101/7.8 072585'
Carbon Dioxide Cover Gas Pressure The semi-annual test of the Hi and Lo Pressure alarm settings were success-fully completed on 5/15/84 and 11/27/84 and 5/13/85. Setpoints were within the limits established and no adjustments were required.
Annual Tests Carbon Dioxide Cover Gas Pressure Relief Valve The annual test of the carbon dioxide cover gas pressure relief valve setting was successfully completed on 6/5/85. The relief actuation occurred at 4.6 PSIG.
V Review Committee Members of the Review Committee E. P. Griffing - Chairman R. S. Lenart - Custodian W. D. Gilbert W. T. Maveal J. E. Meyers M. A. Nelson E. H. Newton E. M. Page R. G. Rateick N. M. Ewbank J. P. Bobba The committee met on July 23, 1985. Formal minutes of these meetings are on file.
Audit Subcommittee Present members of the Audit Subcommittee are: Mr. M. A. Nelson and Mr. E. M. Page. The subcommittee met at the facility on December 20, 1984 and June 9, 1985 for inspection of the facility and review of records and procedures. Memorandums containing their findings are on file. The Review Committee reviewed the findings of the sub Committee Audit, and.the Committee meeting minutes are on file.
VI Noteworthy Items Sodium Familiarization - Frenchtown Fire Department Prior to the shipment of the 1344 drums of Primary Sodium to Argonne National Laboratories - West a sodium familiarization class was conducted with the Frenchtown Fire Department on August 18, 1984.
Following is an outline of the activities:
o Classroom presentation on the characteristics of sodium, fighting sodium fires and operational precautions, and radiological concerns.
.100/R101/7.9 072485
o Demonstration of the Sodium / water reaction, and use of Class D fire extinguishers.
o Toured EF-1 site and explained the methods used to load the drummed sodium on the trucks and the area the loading would take place.
MK 7-8-9-15 Liquid Waste Tank Levels 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.
Input from NRC/ Fermi 1 Annual Report - Sodium Shipment Authorization to ship the Low Specific Activity sodium drums to Argonne Nationul Laboratories - West (ANL-W Site, Scoville, Idaho) was received October 11, 1984 from George C. Grisaffe, Assistant Director for Admini-stration and Contract Management of the Clinch River Breeder Reactor Project. Tri-State Motor Transit Company was selected to transport the drums from Fermi i to the ANL-W new storage building which was scheduled for completion on November 2, 1984. Instructions for reporting each shipment to the Michigan State Police were prepared on October 15, 1984.
Organization of Detroit Edison emergency response teams was initiated on October 19, 1984 under Nuclear Operations Emergency Action Order 1-84,
" Response Activities for Sodium (LSA) Shipment Accident." The first shipment lef t Fermi 1 on October 29, 1984. Seventeen trucks were used to transport 1344 drums. The last truck was received at ANL-W on November 12, 1984. All records of the sodium handling operations were sent to the Detroit Edison Company General Offices vault for 5 year storage.
Reactor Building on June 22, 1985 the smoke detectors in the Reactor Building were checked.
All 4 cable tray detectors were operational.
Fermi I License extension The current Fermi I license expires on June 30, 1985. In a letter dated May 17, 1985 Detroit Edison has requested that the license be extended 40 years.
100/R101/7.10 072585
,Wayns H. JTne
. Vee Pgesident Nuclear Ocerafons
[A9 Fermi-2
- 6400 North Dme Hgh say ISOn (N<mport.Mchgan4846 Nucleer 313)586 4150 operations August 1, 1985 NP-85-038 Director of 1;uclear Reactor Regulation Attention: Iir. John A. Zwolinski, Chief Operating Reactors Branch no. 5 Division of Licensing Uuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Zwolinski:
Reference:
Fermi I URC Docket No. 50-16 URC License No. DPR-9
Subject:
Enrico Fermi I Decommissioned Atonic Power Plant Annual Reoort
Dear Mr. Zwolinski:
Pursuant to Section I.0 (Reporting Requirements) of the Technical Specifications for Amendment 8 to Provisional Operating License No. DPR-9, enclosed are ten copies of Report EF-131 for the year ending June 30, 1985 for the decomnissioned Enrico Fermi Unit I Atomic Power Plant.
Yours very truly, Robert S. Lenart Custodian Enrico Fermi I Deconmissioned Plant cc: Mr. P. !i. Byron lir. P. B. Erickson Mr. J. Eckert (Ilonroe County OCP)
Iir. D. Hahn (State Health Department)
USNRC Docuuent Control Desk Washington, D.C. 20555
'I s
Y Ilr.* John A. Zvolinchi August 1, 19US lie-65-1016 Page 2 bcc: F. E. Agosti J. P. Eobba L. P. Bregni J. E. Conen O. K. Earle 17 . !! . Eubank J. II . Flynn ~
- 11. D. Gilbert E. P. Griffing
- 17. II . Jens R. S. Lenart U. T. Ilaveal J. E. :leyers
?!. A. ?!elson E. II . lieuton S. II . !!oetzel G. R. Overbeck E. 11. Page A. Papadopoulos T.D. Phillips T. Randazzo R. G. Rateick G. 21 . Tiabey A. E. Uegele i
l Approval Control O. I: . Earle (Dethesda Office)
Secretary's Office (2412 UCB)
':RR Chron File l'OC Satellite Service Center A