View source for NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with

{{Adams
| number = ML20211G602
| issue date = 06/30/1999
| title = Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with
| author name = Gipson D, Goodman L
| author affiliation = DETROIT EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000016
| license number = 
| contact person = 
| case reference number = CON-NRC-99-0088
| document report number = NUDOCS 9908310301
| title reference date = 08-27-1999
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 9
}}

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Douglas R. Gipson Senior Vice President, Nuclear Generation
      .                                           Fermi 2 6400 North Dixie Hwy., Newport, Michigan 441re
              .                                   Tel: 734.5M.5201 Fax; 734M6.4172 Detnsit Edison August 27,1999 NRC-99-0088 i
U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D. C. 20555

==Reference:==
Fermi 1 NRC Docket No. 50-16                                                                      I NRC License No. DPR-9                                                                     i

==Subject:==
Enrico Fermi Atomic Power Plant, Unit 1 Annual Reoort Year Ending June 30.1999 Pursuant to Section I.8 (Reporting Requirements) of the Technical Specifications for Provisional Operating License No. DPR-9, enclosed is the annual report for the year ending June 30,1999 for the SAFSTOR Fermi I facility.
Should you have any questions, please contact Lynne S. Goodman, Director Fermi 1 at 734-586-1205.
1 Sincerely, i
l Enclosure                                                                                            '
hs b   I cc: NRC Regional Administrator, Region III S.W. Brown NRC Resident Inspector- Fermi 2 P. Lee, NRC Region III D. Minaar(State ofMichigan) r        9908310301 990827 PDR  ADOCK 05000016 R                    PDR A DTE Energy Company

    ,                                                             l l
        .                                                         l USNRC-August 27,1999 NRC-99-0088 Page 2 bc:  G. Cerullo P. ' Fessler .
D.R. Gipson
              - L.S. Goodman P. Marquardt J.E. Moyers J.E. Conen L. Craine W. Colonnello D. Ferencz R.A. Janssens E.F. Kokosky R. Laubenstein E.F. Madsen R.H. McLenon J.E. Meyers R. Nearboof W. O'Connor, Jr.
E.M Wilds D.R. Williams Fermi 1 Staff Information Management (116 NOC) - Fermi 1 Records NRR Chron File (Licensing)
NRC Notebook (Fermi 1) 1

Fermi 1 Annual Report 1999 Enclosure to NRC-99-0088
  . Page 1 of 7 DETROIT EDISON COMPANY ENRICO FERMI ATOMIC POWER PLANT, UNIT 1 Docket No. 50-16 License No. DPR-9 Annual Report for Period July 1,1998 through June 30,1999 i
Approved by:               ~
Date            ff dy' ne n S. Goodman Custodian i

Fermi 1 Annual Report 1999 Enclosure to NRC-99-0088 Page 2 of 7 ENRICO FERMI ATOMIC POWER PLANT. UNIT I ANNUAL REPORT JULY L 1998 THROUGH JUNE 30.1999                                             l l
1.0    PREFACE This provides a summary of the activities carried out and the results of the facility surveillance program at the shutdown Enrico Fermi Atomic Power Plant, Unit 1, during the twelve (12) months ending June 30,1999.
In summary, all required activities were conducted in accordance with the Operating License and     3 Technical Specifications. One LER was reported during the 98-99 year. Fermi 1 is currently in        l SAFSTOR status; however, the Industrial Safety Improvement Program has commenced.
Information peitaining to industrial improvement activities is included in the Industrial Safety   i Improvement Program section of this report.
2.0    SAFSTOR STATUS 2.1    Summary of SAFSTOR Status 2.1.1  Primary Sodium System The primary sodium system, as established during the shutdown, remains blanketed with carbon dioxide. This was done to provide a passivating atmosphere for any remaining sodium. A continuous supply of carbon dioxide maintains this cover gas between the range of 1/2" W.C.G.      !
and 2 psig.
2.1.2  Sodium Storage Tanks                                                                               !
I A one to five psig nitrogen cover gas pressure is maintained on the three essentially empty        i primary sodium storage tanks.
2.1.3  Out of Service Eauipment All established allowable equipment out of service times has been met during this reporting period according to Technical Specifications.
2.2    Ilealth Physics                                                                                      l 2.2.1  Personnel Exposure From July 1,1998, through June 30,1999, all personnel monitored in Fermi 1 wore their Fermi 2 TLDs (Thermoluminescent Dosimeters) and DRDs (Direct Reading Dosimeters). All visitors were appropriately escorted and wore temporary DRDs for dosimetry.
The total dose by TLD attributed to Fermi 1 was 163 millirem for this reporting period.              l l
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Fermi 1 Annual Report 1999 Enclosure to NRC-99-0088
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23      Surveillance Program l
23.1    Environmental Surveys Environmental monitoring samples were not obtained during this period as a result of the implementation of Amendment No. I1. No liquid radiological releases occurred during this
            ' period. License Amendment iI discontinued radiological monitoring until discharge of liquid radiological effluents is commenced.
23.2    Weekly Tests and Inspections e    Water Intrusion Alarm - Continuity tests of the water intrusion alarm circuits for the waste water sump in the Fuel and Repair Building (FARB) and Biological Shield Wall Annulus were conducted as required by Technical Specifications.
On July 6,1998, the Fuel and Repair Building hot sump water intrusion alarm locked in during the performance of this surveillence. The water level was verified to be below the alarm set point (below the sump grating). To fix the problem a relay switch in the circuitry j was replaced.                                                                                1 e    Cover Gas Pressure -- Weekly checks on the cover gas pressure in the primary system and primary sodium storage tanks were performed. No discrepancies were encountered during        j this reporting period.
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              . General Area --No reportable discrepancies occurred during July 1,1998 through June 30, 1999.
233     Monthly Inspections Protected Area Inspections - Visual inspcetions were conducted within the specified intervals of the fences, gates, and doors (locked); the water level in the sumps from the top access of all active sumps; and the liquid levels of the MK 7,8,9, and 15 liquid waste storage tanks. During    {
monthly surveillances, the acceptance criteria were met.                                          j 23.4    Ouarterly Surveillances 4
Radiological Surveys - The Reactor Building, and the Fuel and Repair Building (FAR.B) were        j checked for presence of gamma radiation and beta, gamma and alpha contamination. The results      )
2 of the quarterly contamination surveys indicated <500 dpm/100 cm beta / gamma and < 20            l dpm/100 cm' alpha. No changes were observed in radiation or contamination levels.                 j i
23.5 Semiannual Tests I
              . Water Intrusion Alarm --The required semiannual functional tests of the water intrusion      !
detectors in the FARB and the Biological Shield Wall Annulus were conducted within the       j specified intervals; no discrepancies were found.                                            !
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Fermi 1 Annual Report 1999 Enclosure to NRC-99-0088
. Page 4 of 7 Carbon Dioxide Cover Gas Pressure - The semiannual tests of the high and low-pressure alarm settings were successfully completed within specified intervals. Setpoints were within the limits established and no adjustments were required.
2.3.6  Annual Tests Carbon Dioxide Cover Gas Pressure Relief Valve - During the annual check of the Primary System cover gas pressure relief valve in the Reactor Building the valve operated at 4.99 psig, which met the Technical Specification criteria of approximately 5 psig.
3.0    INDUSTRI AL SAFETY IMPROVEMENT PROGRAM                                                            j During the past year the Fermil Industrial Safety Improvement Project continued. The nuclear portion of the project will improve Fermi 1 industrial safety by removing hazardous materials,    ;
including but not limited to, sodium, asbestos and NaK. Significant progress was made in the asbestos abatement, preparations for removing sodium residues from the secondary sodium l
j system, and in removing unused electrical equipment from service. More than 200,000 pounds j
of asbestos waste have been shipped from the Protected Area. The project is currently scheduled   j through the year 2000 and a reassessment of its scope is planned for late this year.              1 3.1    License Event Report 99-001 On .iune 4,1999, Fermi 1 staff notified the NRC Region ill that the Protected Area access gate was left unlocked. A walk down of the Protected Area verified that no unauthorized personnel were within and no damage or missing equipment was identified. Corrective action was taken and the Fermi i Manual was updated to prevent another incident.
3.2    Secondary Sodium System                                                                           I
                                                                                                             )
All of the Secondary Sodium pipe and Secondary Sodium Service pipe located within the Steam Generator Building have been dismantled and caustic residues removed or stored for treatment of residual sodium. Caustic residues have been washed and cleaned out of piping in the sodium galleries. Pipe penetrations have been sealed preventing water from entering the secondary sodium tank rooms. Sampling for tritium exposure was performed during sodium pipe cutting activities.
3.3    Radiolonical Surveys During the period of July 1,1998 through June 30,1999, one additional area was identified with a greater than normal building background dose rate. This area was previously not accessible but was monitored due to the asbestos abatement in the reactor building basement. The area is identified in Table 3.1.

.                                                                                                             1 Fermi 1 Annual Report 1909                                                                              -
Enclosure to NRC-99-0058                                                                                l
  . Page 5 of 7
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l 3.1 Radiological Survey Results                                    l RADIOLOGICAL          : CONTACT        30cm DOSE            i LAREA/ LOCATION                    SURVEY # -       IDOSE RATE           RATE-             !
(mrem /hr)      (mrem /hr)          !
Reactor Building Basement            Ol868-R99              35                6              !
Outside Primary Shield Wall in Sump 3.5    Radiological Shipments                                                                           j W
i During the reported time, potentially radiologically contaminated asbestos and other waste       !
materials were shipped to GTS Duratech for processing., The waste materials were contained in    {
strong tight containers, weighing 12,800 lbs. with a volume of 1351.50 ft'. A total of 171,954   i pounds were shipped.                                                                             !
W 3.6    Radiological Effluents                                                                           l Two radiological gaseous effluent releases occurred on 3-11-99, during a planned evolution.
While cutting a supply pipe to the East Secondary Sodium Cold Trap, a concentration of 5.88E -
8 microcuries per milliliter of organic tritium was detected. The maximum dose to an offsite     l I
member of the public due to this release was 1.77E -6 mrem, Committed Effective Dose Equivalent, CEDE. The second release was during venting operations of the East Secondary Sodium Cold Trap, when a concentration of 3.13E -8 microcuries per milliliter of organic tritium was detected. The maximum dose to an offsite member of the public from this release was 9.45E f
             -7 mrem, CEDE. Both of the gaseous effluent releases were below the Technical Specification       I air dose limit of 10 mrad of gamma radiation and 20 mrad of beta radiation, per year.             i l
4.0    COMPLETED WORK                                                                                    l 4.1    10 CFR 50.59 Safety Evaluation                                                                    l l
The following safety evaluations were approved during this report period:
98 029 Rewire Water Intrusion Alarm System SE-98-029 was written to evaluate the rewiring of the Fermi 1 Water Intrusion Alarm system.
The rewiring would :emove and/or abandon, in place, the associated electronics, housing, and      j cabling to the #3 sensor for the Lower Reactor Building. Amendment 11 removed the monitor for the Lower Reactor Building from the Technical Specifications. Spurious alarms led to the decision to disconnect the alarm. The work for this Safety Evaluation has been completed under Design Change 98-028 and was performed under Work Request EF1-98-172.

Fermi 1 Annual Report 1999                                                                                      l Enclosure to NRC-99-0088
  .- Page 6 of 7                                                                                                     l l
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98-027 Modify Access Point to Reactor Building This evaluation discussed provisions needed to supply efficient air supply for the asbestos abatement project of the lower level of the Reactor Building; the metal mesh door is being used         1 to control access to the Reactor Building rather than the airlock that was used. The mesh door has been padlocked closed with a padlock that requires the same key as the padlock on the air lock door. The air supply needs to be large to properly filter the air and to supply a negative pressure to the lower level of the Reactor Building.
98-026 Security Access Control                                                                         )
This is a general Safety Evaluation, which allows the decrease or removal of the 24-hour security      1 at the Fermi Drive gate. The security in the Fermi 2 Protected Area does meet the criteria of the      !
Fermi i Technical Specification; Fermi 2 is within the Fermi 1/ Fermi 2 perimeter, which is within the owner-controlled boundary.
1 98-025 Remove FARB Hot Sump Pumps                                                                     j SE-98-025 will remove the two permanent sump pumps from the hot sump in the FARB. The two pumps contain small amounts of a special nuclear material (SNM), plutonium. These two pumps will be removed from the Fermi i site because they are inoperable and to rid Fermi i of the SNM. A temporary sump pump has been lowered into the hot sump to perform the necessary operations.                                                                                           :
                                                                                                                   )
98-011 Cutting Secondary Sodium Piping This Safety Evaluation addresses the SAFSTOR status of Fermi 1. Secondary sodium pipe has             j been cut and removed to be cleaned of sodium residue in the future and to allow access to the secondary sodium tanks. This Safety Evaluation also addressed the very small amounts of tritium that may be released by the removal of the pipe.
4.2      Desien Channes                                                                                         l l
The following design changes were implemented during this report period:
99-005 Bypass Lighting Cabinet LC1 12 Loads                                                             l The electrical cabinet, which serves Technical Specifications sump pumps #3, #4, #5, and #1 I was the only active equipment remaining in the Ventilation Building. The building itself is in a state of disrepair and would at least require re-roofing to ensure that the lighting cabinet remains dry. Relocating lighting cabinet LCl-12 allows the abandonment of the Ventilation Building.
99 004 Remove Abandoned Transformers from Reactor Building Removed the transformers and associated disconnect switches from the Reactor Building which were previously used to supply power for heating sodium containing equipment.
This Design Change was approved in March of 1999 and was in progress at the end of the reporting period.

Fermi 1 Annual Report 1999 Enclosure to NRC-99-0088
  .- Page 7 of 7 l
98 019 Generic Changes to Abandoned Equipment Generically covered the removal of abandoned equipment and disconnecting abandoned electrical circuits around areas to be worked which are not identified in the Fermi i design basis documents. Any work performed will be documented in the specific work request package, and         !
the identified representative drawings appropriately marked up and attached to the work request    l to show the work performed.
98 017 De energize FARB Rooms and Reactor Building Lower Level Permanently de-energized all power to the lower level of the Reactor Building and the FARB         ;
steam cleaning and transfer tank rooms for the safety of the asbestos abatement workers. All power was verified as de-energized and the cables cut from each area for removal.
98-015 Remove Abandoned Reactor Building Annulus Small Bore Piping Removed selected small bore piping,3-inches or less, from the Reacto Huilding Annulus upper elevation which is verified not to contain unreacted sodium at the pir     <ations to be cut. Some of the small-bore piping is potentially contaminated and may contain sodium (away from cut area) or caustic residue. The pipe is about 35 feet above the Reactor Building annulus floor.
98-014 Remove Ventilation from Primary Sodium Storage Tank Room Removed the ventilation system from the primary sodium storage tank room, including the            ,
blower, blower motor and the ductwork. Also removed ventilation ductwork and miscellaneous non-supporting steel from primary cold trap room, inert gas tank room, and inert gas valve room.
98-013 Cut 3"IIIX Seal Drain Leak- off Pipe in North Room of West Sodium Gallery Cut and capped the Intermediate Heat Exchanger (IHX) Seal Drain Leak- off lines just inside of the north room of the West Sodium Gallery. Remove the IHX seal drain leak- off lines, secondary sodium lines, inert gas lines, stand pipe equalizer, cable trays, etc. from the East and West Sodium Galleries. This Design Change was approved during the reporting period but the work is yet to be finished.
5.0    AUDIT SUBCOMMITTEE l
The Audit Subcommittee inspected the physical facility and reviewed the Technical                    l Specification surveillance records twice during the reporting period. Deviations and observations were recorded and provided to the Review Committee. All audit reports are maintained on file.}}