ML18033B641
| ML18033B641 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1990 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18033B638 | List: |
| References | |
| NUDOCS 9103050328 | |
| Download: ML18033B641 (16) | |
Text
RIVISED PAGES FOR FIRST HALF 1989 FIRST HALF OF 1990 9l03050328 91022S
Page ll of 16 ENCLOSURE 2 CORRECTED EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1989 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Fission Gases Unit Third guarter Fourth guarter Krypton-85m Krypton-85 Krypton-87 Krypton-88 Xenon-133 Xenon-135m Xenon-135 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci
<4.82E-01
<1.62E+02
<1.30E+00
<1.61E+00
<1.50E+00
<1.59E+00
<4.69E-01
<3.84E+00
<5.93E-01
<2.21E+02
<1.54E+00
<2.16E+00
<1.62E-01
<3.18E+00
<5.81E-01
<6.41E+00 otal or Period Ci
<1.73E+02
<2.36E+02 Iodines Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci
<2.72E-04
<1.33E-03
<1.89E+00'6.34E-04
<2.89E-03
<4.79E+00 Total for Period Ci
<1.89E+00
<4.79E+00 3 ~
Particulates Sr-89 1 Sr-90 1 Cs-134 Cs-137 Ba-140 La-140 Co-60 Ci Ci Ci Ci Ci Ci
<5.34E-06
<2.03E-06
<3.20E-04
<2.65E-04
<9.27E-04
<2.85E-04 3.70E-06*
<8.79E-05
<2.13E-05
<4.51E-04
<7.99E-04
<1.42E-03
<9.21E-04 1.54E-04 Total for Period 1 Predicted estimation of releases.
Ci Ci 3.70E-06*
1.08E-02
- Revision 1.54E-04 6.64E-02
Page 9 of 16 ENCLOSURE 2 CORRECTED EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19891 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Summation of All Releases Unit First guarter Second Quarter
% Error A.
Fission and Activation Gases l.
Total Releases Ci
<3.02E+02
<3.92E+02 45 2.
Average Release Rate for Period mCi/sec
<3.84E+01
<4.63E+Ol B.
3.
Percent of T.S. limit2 Iodines 1.
Total Iodine-131 Ci
<3.21E-04
<6.59-04 36 2.
Average Release Rate for Period mCi/sec
<4.09E-05
<7.78E-05 3.
Percent of T.S. Limit Particulates 1.
Particulates with half-lives
>8 days Ci 3.70E-06*
1.54E-04 35 D.
2.
Avg. release rate for period 3.
Percent of T.S. limit 4.
Gross alpha radioactivity Tritium 1.
Total release Ci 6.33E-02*
3.59E-01 1.59E-06 1.36E-06 Ci 1.22E-02 6.73E-02 mCi/sec 4.71E-07*
1.82E-05 21 2.
Average release rate for period mCi/sec 1.55E-03 7.95E-03 3.
4.
5.
Percent of T.S. limit Ground level release Elevated release Ci 6.33E-02 3.59E-01 1.08E-02 6.64E-02 1.46E-03 9.30E-04 1 Reporting period 189 days.
2 The dose rate limit for noble gases shall be
< 500 mrem/year to the total body and t
< 3000 mrem/year to the skin and the dose rate limit for I-131, I-133, H-3, and particulates with g eight day half lives shall be
< 1500 mrem/year to any organ.
- Revision
Page 7 of 16 ENCLOSURE 2 CORRECTED EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1990 LIQUID EFFLUENTS,SUMMATION OF ALL RELEASES Unit First Second guarter guarter E Error A.
Fission and Activation Products 1.
Total Releases Curies 2.46E-02 6.91E-02 9
B.
2.
Average Diluted Concentration During Period 3.
Percent of Applicable Limit (1.00E-7 mCi/ml)
Tritium 1.
Total Releases mCi/ml 1.46E-09 4.70E-09
- 1. 46E+00
- 4. 70E+00 Curies 5.24E-02 6.03E-02 2.
Average Diluted Concentration During Period 3.
Percent of Applicable Limit (3E-03 mCi/ml)
Dissolved and Entrained Noble Gases>
1.
Total Releases mCi/ml 3.10E-09 4.10E-09 1.03E-04 1.37E-04 Curies 2.
Average Diluted Concentration During Period'Ci/ml D.
3.
Percent of Applicable Limit (2E-04 mCi/ml)
Gross Alpha Radioactivity 1.
Total Releases Curies 1.53E-04 2.
Average Diluted Concentration During Period mCi/ml 9.04E-12 E.
Volume of Waste Release (Before dilution)
F.
Volume of Dilution Water for Period Liters Liters 4.45E+06 3.68E+06 1.69E+10 1.47E+10 10 G.*
Total CCW flow for Six Months 116 gigagallons Includes Ze-133, Xe-135, and others.
- Revision
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1990
Page 2 of 6 ENCLOSURE 3
INOPERABLE RADIOLOGICAL EFFLUENT INSTRUME ATIO REPORT This report is to comply with Browns Ferry Nuclear Plant (BFN) Technical Specifications (TS) Sections 3.2.D.2 and'3.2.K.2.
TS Sections 3.2.D.2 and 3.2.K.2 require the exertion of best efforts to return inoperable radiological effluent monitoring instrumentation to an operable status within 30 days.
Failure to return the inoperable instrument to an operable status requires a
description in the next Semiannual Radioactive Effluent Release Report.
This report covers the period from July 1 through December 30, 1990.
During the reporting period:
All units at BFN were defueled, and A large number of effluent instrumentation were inoperable for extended periods as part of planned facility modifications.
In accordance with notes to BFN TS Tables 3.2.D and 3.2.K, compensatory sampling measures were initiated to monitor environmental effluent streams during all periods of instrumentation inoperability.
The airborne radiological effluent instrumentations that were inoperable for periods greater than 30 days included:
Offgas posttreatment monitors and associated sample flow abnormal alarms:
1-RM-90-265, 1-RM-90-266, and 1-PA-90-262 2-RM-90-265, 2-RM-90-266, and 2-PA-90-262 3-RM-90-265, 3-RM-90-266, and 3-PA-90-262 Main stack monitors and associated sample flow abnormal alarms:
0-RM-90-147 and 0-RM-90-148 0-FA-90-150
- Reactor, turbine, and radwaste building ventilation monitor systems:
1-RM-90-249, 1-RM-90-250, and 1-RM-90-251 2-RM-90-249, 2-RM-90-250, and 2-RM-90-251 3-RM-90-249, 3-RM-90-250, and 3-RM-90-251 9-RM-90-252 Control room recorders in panel 1-9-44
Page 3 of 6 ENCLOSURE 3
Winterization periods for the building ventilation monitors, continuous air onitors (CAMs), 1-, 2-, 3-RM-90-249, and -251, are not included in this eport.
Winterization periods are part of normal operations required to maintain building heat.
In the winterization mode, the CAMs are placed in an "out-of-service" status with the ventilation streams isolated.
The liquid radiological effluent instrumentations that were inoperable for a period greater than 30 days included:
Residual heat removal (RHR) service water monitors:
1-RM-90-133 and 1-RM-90-134 2-RM-90-133 and 2-RM-90-134 3-RM-90-133 and 3-RM-90-134 Liquid radwaste effluent flow loop, O-FR-77-60.
Page 4 of 6 ENCLOSURE 3 Offgas Posttreatment Monitors, General Electric (GE)
Stack Monitor, and Associated Sample Flow Annunciators Limitin Conditions of 0 erations LCO Numbers 10 and 1
2 BFN TS Table 3.2.K requires the offgas posttreatment noble gas monitors, the GE main stack monitors, and their associated abnormal sample flow annunciator channels to be operable at all times.
Contrary to this requirement, the following instrumentations were inoperable for periods greater than 30 days as a direct result of facility modifications work:
O-RM-90-147, O-RM-90-148, and 0-FA-90-150 1-RM-90-265, 1-RM-90-266, and 1-PA-90-262 2-RM-90-265, 2-RM-90-266, and 2-PA-90-262 3-RM-90-265, 3-RM-90-266, and 3-PA-90-262 On July 20, 1990, all inputs to the main stack were isolated under Hold Order 0-980-508.
This stack isolation was necessary to modify the stack dilution
- fans, dampers, and associated electrical controls for all three units.
All monitors and instruments will be returned to service following completion of field work and postmodification testing.
dditionally, on December 22, 1989, the offgas sample flow abnormal nnunciator, 2-PA-90-262, was declared inoperable following normal surveillance testing.
In turn, the inoperable status of the pressure annunciator resulted in inoperability determinations of both offgas posttreatment
- monitors, 2-RM-90-265 and 2-RM-90-266.
A Maintenance Request (MR) 1020850 was written to troubleshoot and correct the annunciator.
The root cause for the failed annunciator was traced to a defective offgas sample pump.
MR 1029002 was written to replace the sample pump and the work was completed in July, 1990.
Before the monitor and annunciator operability could be established, all inputs to the main stack were isolated as described above.
Once the stack dilution fan modification has been completed, operability testing of this monitor will be scheduled.
The project return to service is in early 1991.
Effluent releases via the main stack were not permitted during the inoperable period.
This was accomplished by isolating all inputs to the main stack and maintaining status control under Hold Order 0-980-508.
4 J
Page 5 of 6 ENCLOSURE 3
Building Ventilation CAMs CO umbe s
Var ous BFN TS Table 3.2.K requires the reactor,
- turbine, and radwaste building ventilation monitors, their associated
- alarms, and control room recorders to be operable during releases via those pathways.
Contrary to this requirement, the following instrumentations were inoperable for periods greater than 30 days as a direct result of facility modifications work:
1-RM-90-249, 2-RM-90-249, 3-RM-90-249, 0-RM-90-252 Control room 1-RM-90-250, and 1-RM-90-251 2-RM-90-250, and 2-RM-90-251 3-RM-90-250, and 3-RM-90-251 recorders in panel 1-9-44 On October 31, 1990, all building monitors were removed from service as part of Design Change Notice (DCN) W1073B, which upgraded the entire building ventilation monitoring system.
Under W1073B each Nuclear Measurement Corporation monitor was replaced with a microprocessor based Eberline monitor.
Additionally, two independent control modules with recorders were installed in the Unit (U)l control room in panel 1-9-44.
During the modification, all turbine building vents were isolated which in turn eliminated the requirement for compensatory sampling measures.
Appropriate compensatory sampling measures were established for the reactor and radwaste uilding ventilation monitors.
Return to service is projected for early 1991.
Liquid Radwaste Effluent Flow Loop, 0-FR-77-60 LCO umber' 3
BFN TS Table 3.2.D requires the liquid radwaste effluent flow loop, O-FR-77-60, to be operable during releases via the radwaste system.
Contrary to this requirement, the flow loop was inoperable during the entire reporting period.
Manual compensatory measures were observed during all liquid releases during the reporting period.
The flow loop was declared technically inoperable on June 21,
- 1989, due to inaccuracies between the flow transmitter as compared to the actual tank levels.
DCN H4536A was written to replace the dual channel flow instrumentation with a single channel digital instrumentation.
All field work and associated postmodification testing has been completed.
TS change 279 was approved by Plant Operations Review Committee on October 2, 1990.
The design package and associated approvals were sent to Nuclear Engineering for design package closure.
As of December 31, 1990, BFN had not received notification of closure action.
Page 6 of 6 ENCLOSURE 3
RHR Service Water Monitors LCO Numbers 1
2 and 1
BFN TS Table 3.2.D requires the RHR service water monitors, 1-RM-90-133, 1-RM-90-134, 2-RM-90-133, 2-RM-90-134, 3-RM-90-133, and 3-RM-90-134, to be operable during the operation of an RHR loop with its associated RHR service water system in service.
Contrary to this requirement, the 6 monitors were inoperable for periods greater than 30 days.
It should be noted that three of the monitors (1-RM-90-133, 3-RM-90-133, and 3-RM-90-134) are not required to be operable to support U2 power operations.
The RHR service water piping associated with these monitors has been physically cut and capped as a positive isolation boundary between the required U2 RHR service water equipment (includes one loop of the Ul RHR system) and the nonrequired Ul/3 RHR service water equipment.
Monitor 1-RM-90-134 has been out of service due to seismic concerns which are being resolved under DCN H3949.
A hold order has been placed to isolate and to remove from service the RHR service water piping associated with this monitor.
The monitor should be returned to service upon completion of DCN H3949.
As a result of problems related to sample pump automatic starting circuitry, U2 RHR service water'onitor, 2-RM-90-133, was declared inoperable on eptember 24, 1989.
After an investigation, it was determined that the utomatic pump start time delay logic does not allow for charging the RHR service water headers.
Additionally, it was discovered that this deficiency was applicable to all RHR service water monitors.
DCN W9363A was written to correct the problem.
The anticipated design closure and monitor return to service date is in early 1991.