NRC-98-0127, Annual Rept for Period 970701-980630
| ML20237E856 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/30/1998 |
| From: | Gipson D, Goodman L DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-98-0127, CON-NRC-98-127 NUDOCS 9809010231 | |
| Download: ML20237E856 (11) | |
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Douglas R. Gipson Senior Vice President, Nuclear Generation fermi 2 6400 North Dixie He, Newport, Michigan 481f,6 Tel: 313.586.5201 Fax:313.586.4172 Detroit Edison August 27,1998 NRC-98-0127 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk
. Washington, D. C. 20555
Reference:
Fermi i NRC Docket No. 50-16 l NRC License No. DPR-9
Subject:
Enrico Fermi Atomic Power Plant, Unit 1 Annual Report Year Endine June 30.1998 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 30,1998 for the SAFSTOR Fermi i facility.
Should you have any questions, please contact Lynne S. Goodman, Director Fermi 1 at 734-586-1205.
Sincerely, Enclosure cc: NRC Regional Administrator, Region III )
S. W. Brown i G. A. Harris j
P. Lee, NRC Region III j
D. R. Hahn (State of Michigan) 9909010231 980630 ADOCK 05000016:
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A IrfE Energy Company
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O-USNRC
. - August 27,1998 NRC-98-0127 Page 2 l
bc: G. Cerullo P. Fessler l
D.R. Gipson L.S. Goodman l L.K. Layton l P. Marquardt j J.E. Moyers l J.E. Conen l L. Craine '
J. Couillard R.R. Eberhardt, Jr.
D. Ferencz ;
W.D. Gilbert R.A. Janssens E.F. Kokosky R. Laubenstein E.F. Madsen R.H. McLenon J.E. Meyers .
R.A. Newkirk '
W. O'Connor, Jr.
E.M. Page !
K.W. Sessions E.M Wilds D.R. Williams
- NRC Notebook (Fermi 1) l
Fermi 1 Annual Report 1998 l Enclosure to NRC-98-0127 i Page 1 of 9
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DETROIT EDISON COMPANY ENRICO FERMI ATOMIC POWER PLANT, UNIT 1 Docket No. 50-16 License No. DPR-9 Annual Report for Period July 1,1997 through June 30,1998 Approved by: M Date N E/[9P lynne SS Goodman Custodian i
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Fermi 1 Annual Report 1998 Enclosure to NRC-98-0127 Page 2 of 9 ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 ANNUAL REPORT JULY L 1997 TIIROUGH JUNE 30,1998 1.0 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. It is intended to provide 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 30,1998.
In summary, all required activities were conducted in accordance with the Operating License and Technical Specifications. One voluntary LER was written on tritium detected in secondary sodium residues. Fermi 1 is currently in SAFSTOR status; however, an Industrial Safety Improvement Program was initiated during this period. Information pertaining to industrial improvement activities is included in the Industrial Safety Improvement Program section of this report.
2.0 SAFSTOR STATUS 2.1 Summarv 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 Storane Tanks A one to five psig nitrogen cover gas pressure is maintained on the three drained primary sodium storage tanks.
2.1.3 Out-of-Service Eaulpment All established allowable equipment out-of-service times were kept during this reportable period according to Technical Specifications.
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!* 1 Fermi 1 Annual Report 1998 I Enclosure to NRC-98-0127 Page 3 of 9 i l
- j l -- 2.2 Health Physics l l
2.2.1 Personnel Exposure From July 1,1997, through June 30,1998, 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.
There was no dose attributed to Fermi I for this reporting period.
23 Surveillance Procram i
23.1 Environmental Surveys The Technical Specifications no longer require radiological environmental monitoring until discharge ofliquid radiological effluents is commenced. No liquid radiological releaser.
occurred during this period.
l 23.2 WeekIV 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 ;
l Annulus were conducted as required by Technical Specifications, j l I Throughout the weekly surveillance the acceptance criteria were met except for the l following situation:
On July 8,1997, the water intrusion alarm was not tested due to an outage on an electrical bus. During the outage, the out-of-service time was tracked and the areas were visually inspected per Technical Specifications.
i l e Cover Gas Pressure -- Weekly checks on the cover gas pressure in the primary system and j l primary sodium storage tanks were performed. No discrepancies were encountered during ;
this reporting period,
- e. General Area --- On December 1,1997, the water in the " hot" sump (potentially j radioactive) appeared to have lowered approximately 1". Investigation determined this was i not a problem. Over time, evaporation losses are exceeding inleakage since roofleaks have ;
been repaired.
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Fermi 1 Annual Report 1998 Enclosure to NRC-98-0127 Page 4 of 9 233 Monthly inspections Protected Area Inspections --- Visual inspections 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 surveillance, the acceptance criteria were met. On January 12,1998, the air line to the FARB had very low flow. By blowing down the line, the pressure increased and the waste tank levels were obtained.
23.4 ' Ouarterly Surveillance Radiological Surveys --- The Reactor Building, and the Fuel and Repair Building (FARB) were checked for presence of gamma radiation and loose beta, gamma and alpha contamination. .The results of the quarterly contamination surveys indicated <500 dpm/100 cm2beta / gamma. No ;
changes were observed in radiation or loose contamination levels. J 23.5 Semiannual Tests e 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 specified intervals; no discrepancies were 'ound.
- During a post maintenance test following detector calibration, the Reactor Building Biological Shield Wall Annulus water intrusion alarm did not function. Investigation on November 3,1997, revealed that there was corrosion on the probe ends. The probe ends were cleaned and the test was completed satisfactorily.
- 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.
23.6 Annual Tests i Carbon Dioxide Cover Gas Pressure Relief Valve --- During the annual check of the Primary l System cover gas pressure relief valve in the Reactor Building the valve operated at 5.5 psig, which met the Technical Specification criteria of approximately 5 psig, but was above the procedure established setpoint limit. A 72-hour out-of-service time period was initiated for the
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.. cover gas system while a new valve was obtained and calibrated. The valve was replaced and tested within the 72-hour time limit. l i
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N Fermi 1 Annual Report 1998 Enclosure to NRC-98-0127 Page 5 of 9
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3.0 INDUSTRIAL SAFETY IMPROVEMENT PROGRAM i'
Detroit Edison has initiated an Industrial Safety Improvement Program to improve industrial safety and the physical plant condition. The major activities being performed on the nuclear portion of the plant are to remove asbestos and sodium residues from plant systems. The plant will remain in SAFSTOR. The NRC was informed of Detroit Edison's plans on October 2,1997.
3.1 Public Meetine A public meeting was held by the NRC on Fermi l's plans in response to the 1996 Decommissioning Rule. The meeting took place on April 22,1998, at the Monroe County Courthouse.
3.2 Voluntary Lleense Event Report On May 8,1998, Detroit Edison voluntarily submitted a Licensee Event Report (LER) to the NRC with regard to a small amount of tritium detected in secondary sodium samples from the Steam Generator Building. Sodium samples taken in January 1998 were analyzed by Argonne National Laboratory-West. Verbal notification of tritium in the residual secondary sodium was made to NRC Region III.
Air samples of the Steam Generator Building were analyzed and no tritium was detected.
Radiation surveys of the Steam Generator Building show doses are currently at background levels and no loose surface contamination is present. As a safety measure, signs were posted to require personnel to contact Radiation Protection before cutting any piping that may contain tritium.
3.3 10 CFR 50.59 Safety Evaluation The following safety evaluations were approved or changes they covered implemented during this reporting period:
97-003 SE-97-003 was written to evaluate changes to the Fermi 1 Administrative and Surveillance Procedures Manual. Fermi 1 access control procedure was revised to 1) allow an authorized individual to transfer the Protected Area key to another authorized individual after Radiation Protection verifies the second individual as authorized and logs the transfer, 2) clarify that authorized individuals are not limited to Fermi 2 personnel, 3) change wording in list of possible duties of Custodial Agents from " issue key" to "be issued key," and 4) include requirements previously included in Fermi 2 procedures for unescorted access authorization and Protected Area ;
key control log. No Audit Subcommittee requirements were changed, though details were added. l There were no new sources of activity or new methods of releasing the radioactive material at )
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Fermi 1 in any of the changes. Therefore, no new types of accidents were created by these l changes. No changes deviated from the Fermi 1 Technical Specifications and no systems, components or structures are affected by these changes. Changes still result in only pre-authorized individuals being allowed access. Thus, the margin of safety is not reduced as defined in the Fermi 1 Technical Specifications.
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l Fermi 1 Annual Report 1998 l Enclosure to NRC-98-0127 i l Page 6 of 9 1
1 .97-006 l This evaluation addresses the heels of residual sodium remaining in the secondary sodium storage tanks located in the Steam Generator Building and covers a postulated accident created by a reaction of sodium and water. Sodium reacting with water will produce caustic sodium hydroxide (NaOII), hydrogen (H )2 and heat. The release of hydrogen may combust because of this highly exothermic reaction, causing an explosion. A postulated accident analysis and scenario were evaluated for the sodium reaction, as well as the potential impact of sodium hydroxide aerosol on the Fermi 2 Control Room. The postulated secondary sodium accident scenario was determined not to affect the Fermi 2 structures and systems or cause concentrations
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above the allowable limit in the Fermi 2 control room. Based on the evaluation, the offsite chemical release will result in concentrations at the site boundary less than the respiratory l protection level and does not affect the environment. The consequences at Fermi 1 are bounded by previously evaluated Fermi 1 accidents and since a catastrophic event must occur for this scenario to result, the existence of the secondary sodium does not increase the probability of an accident. There were no adverse impacts on Fermi 2.97-007 & 97-008 These evaluations address the removal and shipment off-site of sodium-potassium (NaK) instrument lines. Safety evaluation 97-007 addresses the removal of fifteen NaK-filled instrument lines from the Steam Generator (SG) building and safety evaluation 97-008 addresses the removal of ten NaK-filled instrument lines from the Waste Gas (WG) building. All NaK was contained in a 1/8" armor covered capillary tube between the transmitter housing and the diaphragm of the process seal element. For removal of the NaK lines in the SG building and the WG building, the process seal element connection to the process piping was cut, then the cut lines were covered with plastic and taped. The capillary lines were disconnected from the transmitter housings, slid out the bottom of the housing, and the NaK lines were removed and disposed of. The NaK was not radioactive and there was only a small amount of NaK in each line. The lines had previously been abandoned in place. Appropriate measures were taken in case of a small Na/NaK spill with the potential for a reaction with water to ensure this did not affect the environment or create a different type of accident.97-011 ;
This evaluation addresses changes to the Fermi 1 Manual. The Protected Area Drawing was j revised and the manual changed to specify that the Waste Gas Basement Sump is serving an area outside the Protected Area and so this is not a Technical Specification required sump. The i I
sump surveillance for the cutup pool and decay pool were eliminated while the pools are dry and so the sumps are inactive in accordance with Fermi 1 Technical Specifications. The changes do not present a safety hazard or affect any postulated accident since the dose levels measured in the Waste Gas Building are comparable to background readings and this area does not allow l access to the Protected Area. These manual changes will not affect the environment or reduce !
the margin of safety for Fermi 1 Technical Specifications because (1) the modifications to the Fermi 1 Manual will not change effluents from the site, and (2) the Waste Gas Building basement is outside the Protected Area and the sump covering it does not fall within the scope of the Technical Specifications surveillance.
Fermi 1 Annual Report 1998 Enclosure to NRC-98-0127 Page 7 of 9 98-005 This evaluation addresses the opening of unused, sealed accesses to the sodium tunnel and West Sodium gallery to allow entry. The change does not present a safety hazard or any postulated accident since all residual sodium is located inside sealed piping and another entrance to the tunnel / gallery exists that is not sealed closed. The change does not affect the environment as presently described for Fermi i SAFSTOR or reduce the margin of safety for Fermi 1 Technical Specifications because radioactive material is enclosed within the sodium tunnel piping and opening the manholes do not create any radioactive effluents. The manholes are located in the Protected Area, therefore, access is controlled via the Tech Specs and this change does not reduce the margin of safety for Fermi 1.
3.4 Desien Chances The following design changes were approved or implemented during this reporting period:
97-004 The retaining wall between the Inert Gas Building and the Control Building was deteriorating.
To prevent further deterioration, five buttress supports were designed to hold the existing wall in place and ensure structural stability. The five buttresses were added on the west side of the wall and additional drain holes were opened to relieve the water pressure behind the wall.97-005 Modifications were made to the NaK sump tank connections to enable a safe, visual examination of the NaK sump tank internals for any signs of unreacted NaK. A pipe was cut to allow the introduction of a fiberscope into the tank for viewing and videotaping. Three revisions were made to the design change to revise the equipment needed and to add measures because of an unexpected pressure buildup during the first attempt to inspect the tank.98-003 The entrance to the Reactor Building annulus was blocked by waste gas piping and bellows seal test tubing. The sections of piping and tubing were removed to improve access to the RB Annulus for surveillance should normal testing methods fail and for other entries.98-006 Tc facilitate the asbestos abatement of the Inert Gas Tunnel, uninsulated, abandoned piping up to and including piping in the Waste Gas Building basement was removed. Piping that contained sodium during plant operation was not cut.98-007 To facilitate the asbestos abatement of the Reactor Building lower level, an equipment decay tank will be modified. The cover plate will be removed and two openings cut in the tank wall at the elevation of the RB 1ower level floor. These modifications are being made to provide personnel and equipment access. This design change was not implemented during this period; however, this design change is a part of the ongoing asbestos abatement project.
d Fermi 1 Annual Report 1998 Enclosure to NRC-98-0127 Page 8 of 9
.98-006 To facilitate the asbestos abatement, all power to the primary sodium (Na) storage tank room, cold trap room , inert gas tunnel, Na tunnel, and Na galleries was de-energized.
3.5 Radioloulcal Surveys During the period of July 1,1997 through June 30,1998, two additional areas were identified '
with greater than normal building background dose rates. These dose rates were identified during the Industrial Safety Improvement Program. The areas are identified in Table 3.1.
3.1 Radiological Survey Results CONTACT DOSE RATE 30cm DOSE RATE .
1 AREA / LOCATION (mrem /hr) (mrem /hr) ' ,
Inert Gas North Valve Room 2 0.25 l Reactor Building Outside Secondary 1.5 <0.01 I Shield Wall 3.6 Radiological Shipments l
All shipments leaving the Fermi 1 site were shipped in accordance with DOT and NRC l
regulations. The following materials were shipped from Fermi ! during the report period:
Material Description Radiological Destination - . Volume . Weight - Activity Category (ft).
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- l Asbestos with Scientific Ecology 1352 12800 1.42 E+00 Miscellaneous Metals Group, Inc.
10CFR Part 61 B&W Nuclear !
Smear Samples Environmental 2 10 3.18 E-04 Services, Inc.
Sodium Samples Argonne National 1 2 1.08 E-04 Laboratory-West
- These shipments were categorized as Radioactive Material, Excepted Package, Limited Quantity of Material in addition to other requirements regulated under 49CFR.
- Characterization based upon past 10CFR Part 61 analysis.
} Fermi 1 Annual Report 1998
! Enclosure to NRC-98-0127-Page 9 of 9 4.0 . AUDIT SUBCOMMITTEE The Audit Subcommittee inspected the physical facility and reviewed the Technical 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.
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