NRC-97-0091, Annual Rept for Period 960701-970630
| ML20217Q289 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/30/1997 |
| From: | Gipson D, Goodman L DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-97-0091, CON-NRC-97-91 NUDOCS 9709020246 | |
| Download: ML20217Q289 (8) | |
Text
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- Inoudan 11. Gpbon keniar Vice hesiderd, Nut lear Generatbin I
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, f.P0 North thsie lla)., Newport, Mu higan 441rti
. Tel. 313 Tatto1 in: a1:lfa 4l72 Detroit Edison August 25,1997 NRC 97-0091
] U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D. C. 20555
Reference:
Fermi i NRC Docket No. 50-16 NRC License No. DPR 9 1
Subject:
Enrico Fenni Atomic Power Plant, Unit 1 Annual Report Year Endine June 30.1997 Pursuant to Section 1.8 (Reporting Requirements) of the Technical Specifications for Provisional Operating License No. DPR 9, enclosed is the annual report for the year ending June 30,1997 for the SAFSTOR Fenni i facility.
j Should you have any questions, please contact Lynne S. Goodman, Director Fenni 1 at 313 586-1205.
i Sinceirly, Enclosure ec: . S.W. Brown NRC Regional Administrator ,
D. Nelson, NRC Region til Director, Monroe County Emergency Management Division I 9709020246 970630 llM N N MRI N EH, PDR ADOCK 05000016 115
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Fermi 1 Annual Report 1997 Enclosure to NRC 97 0091 Page 1, of 7 4
DETROIT EDISON COMPANY ENRICO FERMI ATOMIC POWER PLANT, UNIT I Docket No. 5016 1.lcense No. DPR-9 l
l l
! Annual Report for Period July 1,1996 through June 30,1997 Approved by: _
N w Date / 7 Lynne S. Goodman Custodian l
Fenni 1 Annu 1 Report 1997 Enclosure to NRC 97 0091 Page 2 of 7 4
ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 ANNUAL REPORI JULY 1.1996 TilROUGli JUNE 30.1997 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, and 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 30,1997.
In summary, all required activities were conducted in accordance with the Operating License and Technical Specifications. One LER was written on a cover gas pressure switch. No adverse effects on the environment were identified by the radiological environmental monitoring surveillance program.
2.0 SAFSTOR STATUS 2.1 Primary Sudium Sgtem 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.
2.2 Sodium Stornee Tanks A one to five psig nitrogen cover gas pressure is maintained or the three drained primary sodiu.n storage tanks.
2.3 Fermi I License Amendment The NRC issued Amendment No. I1 to the Possession Only License, No. DPR 9, for Fenni 1 on January 15,1997.' This amendment was implemented in February 1997 and
! revised the Penni 1 Technical Specifications by: 1) establishing allowable equipment out of service times; 2) reducing the frequency of radiological environmental monitoring and
, eliminating a raw water sampling location; and 3) eliminating the moisture intrusion monitoring for the Reactor Building lower level.
Fenni 1 Annual Report 1997 Enclosure to NRC 97 0091 Page 3 of 7 2.4 Fermi 1 Decommissioning Evaluation Detroit Edison completed a study during the second quarter of 1997 to determine whether
, it would be advantageous to perfonn the fmal decommissioning of Fermi 1 now, rather than wait until the year 2025. The conclusion was that the plant will remain in SAFSTOR for now, with efforts focused on industrial safety improvements and the physical plant condition. The mabr activities to be performed on the nuclear portion of the plant will be to remove asbestos and sodium residues from plant systems.
i 3.0 llEALTil PIIYSICS 3.1 Personnel Exposure i From July 1,1996, through June 30,1997, all personnel monitored in Fermi 1 wore their Fermi 2 TLDs (Thennoluminescent Dosimeters) and DRDs (Direct Reading Dosimeters).
All visitors were appropriately escorted and wore temporary DRDs for dosimetry.
A total of 2 millirem were attributable to Fermi I during the reporting period.
4.0 SURVEll I ANCE PROGRAM 4.1- Environstatal Sua veys-During the second half of 1996, environmental monitoring samples were obtained for the Fenni 1 Radiological Environmental Monitoring Program. These samples consisted of surface water, raw city potable water, and sediments.
Radiological environmental monitoring was discontinued in 1996 as a result of the implementation of Amendment No.11. The change suws that environmental surveillances are not required until discharge ofliquid radiological effluents is commenced. Shouhl a discharge occur, environmental monitoring will be initiated.
.The water samples for gross beta activity are shown in Table 4.1. Sample results were similar to the results from recent years. The Swan Creek sample is historically higher L ' than the other samples due to the turbidity of Swan Creelt.
As shown in Table 4.2, the South Lagoon and Swan Creek sediment samples indicated small amounts of Cs 137. The Cs-137 levels are consistent with background radioactivity levels detected in previous years and prior to reactor operation due to past atmospherie nuclear testing. ' Naturally occurring isotopes of potassium, radium, thorium and beryllium were also detected in the sediment samples. No radioactivity due to activities associated with Fermi 1 or operation of Femd 2 were detected in the environment.
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Fermi 1 Annual Report 1997 :
Enclosure to NRC-97-0091 -
Page 4 of 7
-4 4.1 Environmental Surveys (Cont'd)
During the decommissioning evaluation study mentioned in Section 2.4, soil borings were taken at selected locations and cnalyzed fo: gamma emitters. No radionuclides other than those of naturally occurring radioactive materials were detected in the samples.
- 4.2 Weekly Tuts and Inspections ,
4.2.1 - 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. Continuity tests of the
-lower Reactor Building alami were conducted until Amendment No. I1 was
, implemented. 2 I-Amendment No. I1, discussed in Section 2.3, eliminated water intrusion monitoring in -
the Reactor Building lower level starting in 1997 because of the wate exclusion design of the building itself. The emendment also allowed moisture intrusian alarms to be out of service for up to 30 days with weekly moisture verification of the area.
4.2.2 Cover Gus Pressure --- We#y checks on the cover gas pressure in the primary system and primary sodium storage tanks were performed. No discrepancies were encountered -
during this reporting period.
4.3 Monthly laispectiuns Protected AresLlR5DEtiARE --- Visual inspections were conducted within the specified I 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. No discrepancies were found during this reporting period, except for a maliunctioning tank level indicator. The low side of the level transmitter was drained and the transmitter recalibrated.
- 4.4 Ouarterly Tests Radiobelcal Surveys -- The Reactor Building, and :be Fuel and Repair Building (FARB) were checked for presence of gamma radiation and loose contamination. The 2
results of the quarterly contamination sc. veys indicated <500 dpm/100 cm beta / gamma.
No changes were observed in radiation or loose contamination levels.
M Semlannual Tests 4
4.3.1 Water Intmsion Al.irm --- The required semiannual functional tests oi sne water intrusion detectors ir. the FARB, lower Reactor Building, and the Biological Shield Wall Annuh is were en~1ucted within the specified irervals; no discrepancies were found. The lower Reactor th ' ding test was discontinued ,a 1997 (Section 4.2.1).
m
Fermi 1 Annual Report 1997 Enclosure to NRCo97-0091-Page 5 of 7 4,1 WATER SAMPI ES. GROSS BETA ACTIVITY x Sample Location: "r Data = : Activity (pCi/ liter) :
Swan Creek 10/08/96 1.30E+1 + /- 2.00E+0 South Lagoon 10/08/06 6.80E+0 +/- 1.20E+0 Reactor Channel 10/10/96 9.60E+0 +/- 1.40E+0 Lake Water #3 10/08/96 3.90E+0 +/- 1.00E+0 Detroit (raw water) 10/14/96 3.80E+0 +/- 9.00E-1 Fermi (raw water) 10/17/96 4.70E+0 +/- 1.10E+0 Monroe (raw water) 10/14/96 5.40E+0 +/- 1.10E+0 l
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- l. TABLE 4.2 SEDIMENT SAMPLES. GAMMA ACTIVITY *. pCi/kg DRY WEIGLIT I S" Nuclidey J South Lagoon;::6-Nov-56 : :. Swan Creek t10-Oct-96 ^ Neactor Channel 10-Oct-96 M(pCl/kg dry)t
- M(pCl/kd'diy)s t(pCi/kg diy))
Mn 54. < 4.00E+1 < 3.00E+1 < 2.00E+1 - l
~~
Co-58 < - 4.00E+1 < 4.00E+1 < 2.00E+1 Fe-59 < 1.00E+2 < 1.00E+ 2 -< 5.00E+1 <
Co-60 < 5.00E+1 < 4.00E+1 < 2.00E+1 Zn-65 - < - 1.00E+2 - < 1.00E+2 < 4.00E+1
- Zr/Nb-95 < 5.00E+1 < 5.00E+1 < 2.00E+1 Cs 134 < 5.00E+1 < 4.00E+1 < 2.00E+1 Cs-137 3.50E+2 +/- 5.00E+1 1.14 E+2 +/- 2.90E+1 < 2.00E+1
- Excluding naturally occurring isotopes
. The +/- error is based on a two sigina counting error The < "less than" is the MDA and is based on 4.66 sigma i
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Fenni l Annual Report 1997 Enclosure to NRC-97-0091 Page 6 of 7 4.5.2 Carbon Dloride cover Gas Pressure --- One semiannual test on Septc.nber 17,1996 revealed that the high pressure switch in the primary system could not be calibrated.- A crackc d litting that allowed leakage caused the problem so the fitting and high pressure switch were replaced. The low pressure switch was unaffected by this occurrence, LER 96-002 was submitted for this condition prohibited by the Technical Specifications, Section 1.8. The high pressure switch on the CO2 cover gas system was removed from the system for approximately 45 minutes during the replacement of the fitting. This did not adversely affect the CO2 system's ability to maintain adequate pressure in the primary system. However, the Fermi 1 Technical Specifications did not provide out of service times for this event, until Amendment No I1 was implemented.
4.6 Annual Tests l
l- Carbon Dioxide Cover _ Gas Pressure Relief Valve --- The annual test of the carbon dioxide cover gas pressure relief valve setting was successfully complete! within the prescribed interval.
5.0 10 CFR 50.59 SAFETY EVALUATION Transfer of Radioactive Liould Waste-SE-96-002 was written to provide a generic basis that will allow radioac,tive liquid waste that collects in the sump in the Fermi 1 Fuel and Repair Building to be pur ped to the -
Mark 15,9,8, and 7 liquid waste tanks and stored until such time as the quantity is suffeient to make it prudent to process in an acceptable manner. The potential offsite effects are less than previously evaluated since the potential fraction of the maximum permissible concentration (MPC) of radioactive effluents at the Monroe Water Intake is bounded by the fraction of the MPC presented in the Supplemental Environmental Information for Amendment No. 9 and discussed by the NRC in Amendment No. 9 of the Possession-Only License No. DPR-9 for Fermi 1. The results of the 10 CFR 50.59 review shows that pumping the radioactive liquid from the sump to one of the liquid waste tanks for storage is not an unreviewed safety question.
Fermi 1 Annuel Report 1997 Enclosure to NP.C 97-0091 Page 7 of 7.
6.0 OTIIER DESIGN CII ANGES J-Cover Gas System Pressure Gauge A design change, Change Request No.97-002, was written and implemented to change the Fermi 1 N 2cover gas system pressure gauge on the primary sodium storage tanks.
The design change replaced the Ashcroft range 0-60 psig gauge, with I psig subdivisions, that was no longer serviceable. An Ashcroft Model 1379,0-60 psi pressure gauge with 1/2 psi subdivisions replaced the 1 psig subdivision gauge that is now unavailable. Since the tanks are pressurized to only a few (1-5) psig, tiie 1/2 psi subdivisions will make it easier '1 read the gauge. The ability to pressurize the primary sodium tanks was not adverse.y affected by this gauge change.
A second design change, mentioned in the 1995 Annual Report, was implemented this period to change the indicator lamps on the water intrusion alarm system.
7.0 AUDIT SUBCOMMITTEE l 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.