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{{#Wiki_filter:* consumers Power POW ERIN& MICHlliAN"S PRO&RESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 26, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 PM Donnelly Safety and Licensing Director DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT -JULY THROUGH DECEMBER 1992 Enclosed is the Semi-Annual Radioactive Effluent Release and Waste Disposal report for the Palisades plant covering the period from July through December 1992. 10 CFR 50.36a has been changed (effective October 2, 1992), to require the Radioactive Effluent Release and Waste Disposal Report be submitted to the NRC once every twelve months instead of semi-annually.
{{#Wiki_filter:consumers
However, we are submitting a report covering the last six months of 1992 to provide for continuity with the information that was transmitted for the first six months of the year. This will be the last semi-annual report. In the future, we will submit an Annual Radioactive Effluent Release and Waste Disposal Report. The semi-annual report contains references to technical specifications sections.
* Power                                                 PM Donnelly Safety and Licensing Director POWERIN&
These sections were removed from the technical specifications in Amendment 154 that became effective January 1, 1993.
MICHlliAN"S PRO&RESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 26, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JULY THROUGH DECEMBER 1992 Enclosed is the Semi-Annual Radioactive Effluent Release and Waste Disposal report for the Palisades plant covering the period from July through December 1992.
Safety and Licensing Director CC: Administrator Region III, USNRC Resident Inspector, Palisades Enclosure l) __
10 CFR 50.36a has been changed (effective October 2, 1992), to require the Radioactive Effluent Release and Waste Disposal Report be submitted to the NRC once every twelve months instead of semi-annually. However, we are submitting a report covering the last six months of 1992 to provide for continuity with the information that was transmitted for the first six months of the year.
-------(r __ 9_3_0_3_0_9-Q025 921231 PDR ADOCK 05000255 R PDR A CM5 ENERGY COMPANY
This will be the last semi-annual report. In the future, we will submit an Annual Radioactive Effluent Release and Waste Disposal Report.
* Enclosure 1 Consumers Power Company Palisades Plant Docket 50-255 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1992 February 26, 1993 18 Pages I '!
The semi-annual report contains references to technical specifications sections. These sections were removed from the technical specifications in Amendment 154 that became effective January 1, 1993.
PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July -December 1992 This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Palisades Nuclear Plant during the period of July 1, 1992 through December 31, 1991. The report format is detailed in Plant Technical Specification 6.9.3.lA.
          ~!?,#
Palisades was tripped off-line several times during this reporting period. The following is a summary of the plant operating status between July 1, 1992 and December 31, 1992: July 1992 The plant began the month at full power, but tripped off-line on 7/01/92 at 1232 due to Turbine Control System problems.
Safety and Licensing Director CC: Administrator Region III, USNRC Resident Inspector, Palisades Enclosure l) __Q1'L~~----- -------
The appropriate repairs were made and the plant was placed back on-line on 7/04/92 at 0223. The plant remained on-line until 7/24/92 when it tripped due to low line voltage during a test of the Safety Injection System which caused the Turbine Control System to trip the turbine. A new uninterruptible power supply was installed and the plant was placed back line on 7/29/92 at 0632. August 1992 The plant began the month at full power, but tripped off-line on 8/14/92 at 0017 due to a failed air line to a feedwater regulating valve. In addition, due to problems with the Turbine Control System, the plant was not placed back on-line until 8/17/92 at 1749. The plant was taken back off-line during a heat balance test at 25% power on 8/17/92 at 2017 due to a large turbine hydraulic fluid leak. The p 1 ant was p 1 aced back on-1 i ne on 8/18/92 at 0230. The p 1 ant ran until 8/25/92 when it tripped off-1 i ne due to a failed so 1 enoi d in the preferred AC Bus powering engineering safeguards system electrical loads coupled with an undetected blown fuse. Again, repairs were made and plant was placed back on-line on 8/27/92 at 0417. September 1992 The plant began the month at full power, but was de-escalated on 9/18/92 and then taken off-line on 9/19/92 at 0953 to facilitate the investigation of a personnel injury accident.
9_3_0_3_0_9-Q025 921231 r __
The plant was placed back on-line on 9/28/92 at 0622 following the completion of the accident investigation and repairs to various valves due to turbine overspeed testing. October 1992 The plant began the month at full power, but tripped off-line on 10/30/92 at 0700 hours due to Turbine Control System problems.
(  PDR     ADOCK 05000255 R                             PDR A CM5 ENERGY COMPANY
November 1992 The plant began the month off-line.
* Enclosure 1 Consumers Power Company Palisades Plant Docket 50-255 I
The plant made several modifications to the Turbine Control System and the plant was placed back on-line on 11/08/92 at 2002. The plant operated at full power the remainder of the month.
SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE '!
December 1992 The plant operated at full power the entire month. 1. Supplemental Information A. Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Table HP 10.5-1 (Attachment 1). B. Abnormal Releases On November 9, 1992, there were two noble gas incursions into the Auxillary Building.
AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1992 February 26, 1993 18 Pages
Radiation monitor RIA-1809 alarmed on High Alarm and tripped V-14B and V-10 ventilation fans during each occurrance.
 
In addition, the friskers on 590' Auxillary Building pegged high for a period of time and the continuous area monitor showed a large spike. The root cause of this event(s) was identified as a valve, MV-WG603, being inadvertantly left partially open on the Vacumn Degasifier system. The identified valve was closed by the Operations Department.
PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July - December 1992 This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Palisades Nuclear Plant during the period of July 1, 1992 through December 31, 1991. The report format is detailed in Plant Technical Specification 6.9.3.lA. Palisades was tripped off-line several times during this reporting period. The following is a summary of the plant operating status between July 1, 1992 and December 31, 1992:
The details of this event are recorded in a Deviation Report, D-Pal-92-265.
July 1992 The plant began the month at full power, but tripped off-line on 7/01/92 at 1232 due to Turbine Control System problems. The appropriate repairs were made and the plant was placed back on-line on 7/04/92 at 0223. The plant remained on-line until 7/24/92 when it tripped due to low line voltage during a test of the Safety Injection System which caused the Turbine Control System to trip the turbine. A new uninterruptible power supply was installed and the plant was placed back on-line on 7/29/92 at 0632.
The amount of noble gas released was quantified through our RGEM Stack Gas System weekly analysis.
August 1992 The plant began the month at full power, but tripped off-line on 8/14/92 at 0017 due to a failed air line to a feedwater regulating valve. In addition, due to problems with the Turbine Control System, the plant was not placed back on-line until 8/17/92 at 1749. The plant was taken back off-line during a heat balance test at 25% power on 8/17/92 at 2017 due to a large turbine hydraulic fluid leak.
The results showed a release of 7.12E-Ol curies of XE-133 and is documented in batch card 92-046-ST.
The p1ant was p1aced back on-1i ne on 8/18/92 at 0230. The p1ant ran until 8/25/92 when it tripped off-1 i ne due to a failed so 1enoi d in the preferred AC Bus powering engineering safeguards system electrical loads coupled with an undetected blown fuse. Again, repairs were made and plant was placed back on-line on 8/27/92 at 0417.
C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents is provided in Attachment
September 1992 The plant began the month at full power, but was de-escalated on 9/18/92 and then taken off-line on 9/19/92 at 0953 to facilitate the investigation of a personnel injury accident. The plant was placed back on-line on 9/28/92 at 0622 following the completion of the accident investigation and repairs to various valves due to turbine overspeed testing.
: 5. D. Radioactive Effluent Monitoring Instrumentation:
October 1992 The plant began the month at full power, but tripped off-line on 10/30/92 at 0700 hours due to Turbine Control System problems.
: 1) Waste Gas Decay Tank Vent Flow Indicator (FI-1121)
November 1992 The plant began the month off-line. The plant made several modifications to the Turbine Control System and the plant was placed back on-line on 11/08/92 at 2002.
Technical Specification 3.24.2.l(b) requires that when a radioactive gaseous effluent monitoring instrument channel becomes inoperable, best efforts must be made to return the instrument to operable status within 30 days and if unsuccessful, report the incident in the next Semi annua 1 Radioactive Effluent Report. Technical Specification-Table 3.24-2.l(b) further stipulates that radioactive effluent releases may continue to be made with less than the required amount of operable channels providing that the flow rate is estimated at least once per 24 hours for continuous releases or fours for batch releases.
The plant operated at full power the remainder of the month.
On September 29, 1992, it was determined that the flow indicator, FI-1121 was inoperable.
 
As required per Health Physics Procedure HP 6.6, if FI-1121 is inoperable during Waste Gas Decay Tank batch releases, releases may continue provided *the flow rate is estimated by the Primary Side Auxiliary Operator at least every four hours during batch rel eases. These calculations were performed , as necessary, for batch releases during the period of September 29,1992 and December 11, 1992. The root cause of the problem appears to be the fact that when a flow is applied to the rotameter the "float pin" oscillates violently which resulted in the "float pin" bending. The float pin was straightened and an adjustment to PCV-1123 was made. In addition, Instrument  
December 1992 The plant operated at full power the entire month.
& Control ordered new parts for the flow indicator.
: 1. Supplemental Information A. Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Table HP 10.5-1 (Attachment 1).
The flow indicator was declared operable on December 11, 1992. The corrective solution to this reliability problem is to replace the instrument with a new flow indicator with a wider flow range. This corrective action has been turned over to the Instrument  
B. Abnormal Releases On November 9, 1992, there were two noble gas incursions into the Auxillary Building. Radiation monitor RIA-1809 alarmed on High Alarm and tripped V-14B and V-10 ventilation fans during each occurrance.
& Control System Engineering Group per work order 24204932.
In addition, the friskers on 590' Auxillary Building pegged high for a period of time and the continuous area monitor showed a large spike.
During the period of inoperabil ity, all of the Technical Specification sampling requirements as stated in Table 3.24-2(1.b) were met. A detailed report of the work performed on FI-1121 is documented in work order 24202520.
The root cause of this event(s) was identified as a valve, MV-WG603, being inadvertantly left partially open on the Vacumn Degasifier system. The identified valve was closed by the Operations Department.
: 2) Main Steam Gross Gamma Activity Monitors (RIA 2323 and 2324) the main steam line radiation monitors remained inoperable from July 1, 1992 to August 28, 1992 due to EEQ concerns as described in our January 1992 -June 1992 Semi-Annual Effluent Report. A discussion between Palisades Licensing, the NRC Project Manager and the Senior Resident Inspector was held as a result of our need to remove our preplanned alternate method of monitoring (Jordan Radguns) to install our new more reliable backup monitors, which would replace the Jordan Radguns. An agreement was made that pending the NRC review for our request for exemption to the requirements of RG 1.97 for these instruments, we can consider the main steam 1 ine monitors operable and take the action we consider appropriate to replace the Jordan Radguns. The main steam line monitors were declared on August 28, 1992 and the new backup monitors were installed.
The details of this event are recorded in a Deviation Report, D-Pal-92-265. The amount of noble gas released was quantified through our RGEM Stack Gas System weekly analysis. The results showed a release of 7.12E-Ol curies of XE-133 and is documented in batch card 92-046-ST.
: 2. Gaseous Effluents Table HP 10.5-2 (Attachment
C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents is provided in Attachment 5.
: 2) lists and summarizes radioactive effluents released during the reporting unidentified beta was 1.50E-03%
D. Radioactive Effluent Monitoring Instrumentation:
of the total release. all gaseous period. The
: 1)     Waste Gas Decay Tank Vent Flow Indicator (FI-1121)
: 3. Liquid Effluents Table HP 10.5-3 (Attachment
Technical Specification 3.24.2.l(b) requires that when a radioactive gaseous effluent monitoring instrument channel becomes inoperable, best efforts must be made to return the instrument to operable status within 30 days and if unsuccessful, report the incident in the next Semi annua 1 Radioactive Effluent Report. Technical Specification- Table 3.24-2.l(b) further stipulates that radioactive effluent releases may continue to be made with less than the required amount of operable channels providing that the flow rate is estimated at least once per 24 hours for continuous releases or fours for batch releases.
: 3) lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was l.04E-03%
On September 29, 1992, it was determined that the flow indicator, FI-1121 was inoperable. As required per Health
of the total .release.
 
The Sr-89 and Sr-90 values reported for the third quarter liquid effluent is an average of the first, second and fourth quarter T-91 batch analysis results. The third quarter T-91 batch sample (92-021-R) was not sent to our vendor for analysis and has consequently been determined to be lost. A Deviation Report D-PAL-93-014 was generated to identify and evaluate this violation of Technical Specification Section 4.24.3.1.a and Table 4.24.3. 4. Solid Waste There were no solid waste shipments from July 1 to December 31, 1992 (Table HP 10.5-4, Attachment 4). 5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follows: A. The offsite air doses at the site boundary (0.48 SSE) due to noble gases were 9.31E-06 millirad beta and l.lOE-07 millirad gamma for the third quarter; and 4.96E-05 millirad beta and l.56E-05 gamma for the fourth quarter. The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta occurred during the fourth quarter, being 3.54E-05 millirads beta and for gamma during the fourth quarter being l.12E-05 millirads gamma. B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate and iodine) was the child bone for the third and fourth quarters.
Physics Procedure HP 6.6, if FI-1121 is inoperable during Waste Gas Decay Tank batch releases, releases may continue provided
Doses were l.OlE-02 and l.17E-02 millirem, respectively.
              *the flow rate is estimated by the Primary Side Auxiliary Operator at least every four hours during batch rel eases. These calculations were performed , as necessary, for batch releases during the period of September 29,1992 and December 11, 1992.
C. Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50 miles from the site boundary were: 6.86E-03 person-Rem and 6.51E-06 millirem for the third quarter; and 7. 79E-03 person-Rem and 7. 39E:..06 mi11 i rem for the fourth quarter. D. The maximum total body dose to an individual in unrestricted rel ated exposure pathways was 7.21E-04 millirem (adult) and 7.51E-04 millirem (adult) for the third and fourth quarters, respectively.
The root cause of the problem appears to be the fact that when a flow is applied to the rotameter the "float pin" oscillates violently which resulted in the "float pin" bending. The float pin was straightened and an adjustment to PCV-1123 was made.
In addition, Instrument &Control ordered new parts for the flow indicator. The flow indicator was declared operable on December 11, 1992.
The corrective solution to this reliability problem is to replace the instrument with a new flow indicator with a wider flow range. This corrective action has been turned over to the Instrument & Control System Engineering Group per work order 24204932.
During the period of inoperabil ity, all of the Technical Specification sampling requirements as stated in Table 3.24-2(1.b) were met.
A detailed report of the work performed on FI-1121 is documented in work order 24202520.
: 2) Main Steam Gross Gamma Activity Monitors (RIA 2323 and 2324) the main steam line radiation monitors remained inoperable from July 1, 1992 to August 28, 1992 due to EEQ concerns as described in our January 1992 - June 1992 Semi-Annual Effluent Report.
A discussion between Palisades Licensing, the NRC Project Manager and the Senior Resident Inspector was held as a result of our need to remove our preplanned alternate method of monitoring (Jordan Radguns) to install our new more reliable backup monitors, which would replace the Jordan Radguns. An agreement was made that pending the NRC review for our request for exemption to the requirements of RG 1.97 for these instruments, we can consider the main steam 1ine monitors operable and take the action we consider appropriate to replace the Jordan Radguns.
The main steam line monitors were declared operabl~ on August 28, 1992 and the new backup monitors were installed.
: 2. Gaseous Effluents Table HP 10.5-2 (Attachment 2) lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 1.50E-03% of the total release.
: 3. Liquid Effluents Table HP 10.5-3 (Attachment 3) lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was l.04E-03% of the total .release.
The Sr-89 and Sr-90 values reported for the third quarter liquid effluent is an average of the first, second and fourth quarter T-91 batch analysis results. The third quarter T-91 batch sample (92-021-R) was not sent to our vendor for analysis and has consequently been determined to be lost. A Deviation Report D-PAL-93-014 was generated to identify and evaluate this violation of Technical Specification Section 4.24.3.1.a and Table 4.24.3.
: 4. Solid Waste There were no solid waste shipments from July 1 to December 31, 1992 (Table HP 10.5-4, Attachment 4).
: 5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follows:
A. The offsite air doses at the site boundary (0.48 SSE) due to noble gases were 9.31E-06 millirad beta and l.lOE-07 millirad gamma for the third quarter; and 4.96E-05 millirad beta and l.56E-05 gamma for the fourth quarter. The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta occurred during the fourth quarter, being 3.54E-05 millirads beta and for gamma during the fourth quarter being l.12E-05 millirads gamma.
B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate and iodine) was the child bone for the third and fourth quarters. Doses were l.OlE-02 and l.17E-02 millirem, respectively.
C. Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50 miles from the site boundary were: 6.86E-03 person-Rem and 6.51E-06 millirem for the third quarter; and 7. 79E-03 person-Rem and 7. 39E:..06 mi11 i rem for the fourth quarter.
D. The maximum total body dose to an individual in unrestricted water-rel ated exposure pathways was 7.21E-04 millirem (adult) and 7.51E-04 millirem (adult) for the third and fourth quarters, respectively.
The maximum organ doses were l.24E-03 millirem (teenage bone) for the third quarter and l.31E-03 millirem (both teenage and child bone) for the fourth quarter.
The maximum organ doses were l.24E-03 millirem (teenage bone) for the third quarter and l.31E-03 millirem (both teenage and child bone) for the fourth quarter.
E. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50 miles from the site boundary were: 2.75E-03*
 
person-Rem and 2.62E-06 millirem for the third quarter; and 2.86E-03 person-Rem and 2.72E-06 millirem for the fourth quarter. 6. Process Control Program (PCP}
E. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50 miles from the site boundary were: 2.75E-03* person-Rem and 2.62E-06 millirem for the third quarter; and 2.86E-03 person-Rem and 2.72E-06 millirem for the fourth quarter.
* No changes were made to the Process Control Program. 7. Offsite Dose Calculation Manual (ODCMl No changes were made to the Offsite Dose Calculation Manual.
: 6. Process Control Program (PCP}
v ATTACHMENT I Consumers Power Company Pali sades Pl ant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES July -December 1992 February 26, 1993 I Page I
* No changes were made to the Process Control Program.
* A. B. TABLE HP 10.5-1 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . BATCH RELEASES July 1. 1992 to December 31. 1992 GASEOUS Units 3rd Qtr 4th Qtr Number of Releases 3 5 Total Release Time Minutes 1785 1330 Maximum Release Time Minutes 1065 453 Average Release Time Minutes 595 266 Minimum Release Time Minutes 270 137 LIQUID Units 3rd Qtr 4th Qtr Number of Releases 1 1 Total Release Time Minutes 473 550 Maximum Release Time Minutes 473 550 Average Release Time Minutes 473 550 Minimum Release Time Minutes 473 550 ATTACHMENT 2 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS  
: 7. Offsite Dose Calculation Manual (ODCMl No changes were made to the Offsite Dose Calculation Manual.
-SUMMATION OF RELEASES July -December 1992 February 26, 1993 3 Pages A. B. c. D. E. F. PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS  
 
-SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 FISSION AND ACTIVATION GASES Units 3rd Otr 1. Total release Ci l.OBE-01 2. Averaae release rate for oeriod uCi/sec 1.36E-02 3. Percent of annual ava MPC 3 6.50E-06 IODINES 1. Total Iodine Ci 5.17E-05 2. Averaae release rate for aeriod uCi/sec 6.51E-Of 3. Percent of annual ava MPC 3 5. 86E-OE PARTICULATES
v ATTACHMENT I Consumers Power Company Pali sades Pl ant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES July - December 1992 February 26, 1993 I Page
: 1. Particulates with half-life  
 
>8 davs Ci 2.95E-05 2. Averaae release rate for aeriod uCilsec 3.72E-06 3. Percent of annual ava MPC % 1.
I
: 4. Gross aloha radioactivitv Ci 2.0lE-05 TRITIUM 1. Total Release Ci 1.39E+OC 2. Averaae release rate for oeriod uCi/sec l.75E-Ol 3. Percent of annual ava MPC % l.25E-04 1. Beta Air dose at Site Boundary Due to Noble Gases lTS 3.24.5.2al mRads 9.31E-06 2. Percent limit % 9.31E-05 3. Gamma Air dose at Site Boundary due to Noble Gases lTS 3.24.5.2a mRads 1. lOE-07 4. Percent limit 3 2.20E-OE 1. Maximum Organ Dose to Public Based on Critical Receptors  
* TABLE HP 10.5-1 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
<TS 3. 24. 5. 3 l mRem l.OlE-02 2. Percent of limit % l.35E-Ol *NOTE: Data is reported for 1-131 and I-133 only. Est Tota 1 4th Otr Error 3 1. 03E+OO 1.30E-01 6.60E+OO 6.lBE-05 1. 59E-05
                              . BATCH RELEASES July 1. 1992 to December 31. 1992 A. GASEOUS                     Units     3rd Qtr 4th Qtr Number of Releases                       3       5 Total Release Time         Minutes   1785     1330 Maximum Release Time       Minutes   1065     453 Average Release Time       Minutes     595     266 Minimum Release Time       Minutes     270     137 B. LIQUID                       Units     3rd Qtr 4th Qtr Number of Releases                       1       1 Total Release Time         Minutes     473     550 Maximum Release Time       Minutes     473     550 Average Release Time       Minutes     473     550 Minimum Release Time       Minutes     473     550
* 2.0lE-06 2.82E+Ol 1. 84E-06 3.69E-05 4.64E-06 N/A 2.00E-05 2.00E-05 1. 53E+OO l.92E-Ol l.37E-04 4.96E-05 4.96E-04 1. 56E-05 3.12E-04 l.17E-02 l.56E-Ol I. 2. FISSION GASES Argon-41 Krypton-SS Krypton-85m Krypton-S7 Krypton-SS Xenon-13lm Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-138 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS
 
-SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 UNITS 3rd QUARTER Ci <LLD Ci l.07E-Ol Ci <LLD Ci <LLD Ci <LLD Ci <LLD Ci . 4.92E-04 Ci <LLD Ci 2.37E-04 Ci <LLD Ci <LLD Total for Period Ci l.OSE-01 IODINES UNITS 3rd QUARTER Iodine-131 Ci 2.62E-05 Iodine-132 Ci <LLD *Iodine-133 Ci 2.SSE-05 Iodine-134 Ci <LLD Iodine-135 Ci <LLD Total for Period Ci 5.17E-05 4th QUARTER <LLD 3.77E-02 <LLD <LLD <LLD <LLD 9.95E-Ol <LLD <LLD <LLD  
ATTACHMENT 2 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES July - December 1992 February 26, 1993 3 Pages
<LLD I. 03E+OO 4th QUARTER S.25E-06 <LLD 7.67E-06 <LLD <LLD l.59E-05
 
: 3. PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS
PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 Est Tota 1 A. FISSION AND ACTIVATION GASES               Units       3rd Otr   4th Otr    Error 3
-SUMMATION OF RELEASES PARTICULATES
: 1. Total release                           Ci         l.OBE-01 1. 03E+OO
* UNITS 3rd QUARTER Manganese-54 Ci <LLD Cobalt-58 Ci <LLD Iron-59 Ci <LLD Cobalt-60 Ci <LLD Zinc-65 Ci <LLD Strontium-89 Ci 8.lOE-07 Selenium-90 Ci 5.15E-07 Molybdenum-99 Ci <LLD Cesium-134 Ci <LLD Cesium-137 Ci <LLD Cerium-141 Ci <LLD Cerium-144 Ci <LLD Chromium-SI Ci <LLD Net Unidentified Ci 2.82E-05 Beta Total Ci 2.95E-05
: 2. Averaae release rate for oeriod         uCi/sec     1.36E-02 1.30E-01    6.60E+OO
* Particulates with half lives >8 days. 4th QUARTER <LLD <LLD <LLD <LLD , <LLD l.18E-06 4.85E-07 <LLD <LLD 2.70E-06 <LLD <LLD <LLD 3.25E-05 3.69E-05 ** Particulates with half-lives
: 3. Percent of annual ava MPC           3           6.50E-06 6.lBE-05 B. IODINES
<8 days; not reflected in overall isotopic totals ATTACHMENT 3 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REeORT LIQUID EFFLUENTS
: 1. Total Iodine                           Ci         5.17E-05 1. 59E-05      *
-SUMMATION OF RELEASES July -December 1992 February 26,,1993 2 Pages I . A. B. c. D. E. F. G. H. -----------------PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS
: 2. Averaae release rate for aeriod         uCi/sec     6.51E-Of 2.0lE-06    2.82E+Ol
-SUMMATION OF ALL RELEASES July 1, 1992 to December 31, 1992 FISSION AND ACTIVATION PRODUCTS Units 3rd Otr 1. Total release (Not including
: 3. Percent of annual ava MPC           3           5. 86E-OE 1. 84E-06
*tritium.
: c. PARTICULATES
oases. alohal Ci 1.37E-03 2. Average diluted concentration durina oerfod uCi/ml 4.14E-11 3. Percent of MPC % 2.23E-03 TRITIUM 1. Total Release Ci 2.33E+Ol 2. Average diluted concentration durina oeriod uCi/ml 7.04E-07 3. Percent of MPC % 2.35E-02 DISSOLVED AND ENTRAINED GASES 1. Total Release Ci <LLD 2. Average diluted concentration durina oeriod uCi/ml N/A 3. Percent of MPC % NIA GROSS ALPHA RADIOACTIVITY
: 1. Particulates with half-life
{Total Rel easel Ci 1.93E-07 VOLUME OF WASTE RELEASED <Prior to Dilutionl Liters 1.65E+05 VOLUME OF DILUTION WATER USED DURING PERIOD Liters 3.31E+10 MAXIMUM DOSE COMMITMENT
          >8 davs                             Ci         2.95E-05 3.69E-05
-WHOLEBODY mRem 7.21E-04 Percent of TS 3.24.4.la  
: 2. Averaae release rate for aeriod         uCilsec     3.72E-06 4.64E-06    N/A
% 4.81E-02 MAXIMUM DOSE COMMITMENT  
: 3. Percent of annual ava MPC             %           1. 73E-O~ 2.00E-05
-ORGAN mRem 1. 24E-03 Percent of TS 3.24.4.la Organ limit % 2.48E-02 Est Total 4th Otr Error % 9.llE-04 2.75E-11 9.70E+OO 2.64E-03 2 .13E+Ol 6.44E-07 4.00E+OO 2.lSE-02 <LLD N/A N/A NIA 2.21E-07 1. 70E+05 3.31E+10 7.SlE-04 5.0lE-02 1.31E-03 2.62E-02
: 4. Gross aloha radioactivitv               Ci         2.0lE-05 2.00E-05 D. TRITIUM
: 1. --------PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS July 1. 1992 to December 31. 1992 NUCLIDES RELEASED UNITS 3rd QUARTER Manganese-54 Ci <LLD Cabal t-58 -Ci 5.74E-04 Iron-59 Ci -<LLD Cobalt-60 Ci 2.39E-04 Zinc-65 Ci <LLD Strontium-89 Ci 5.40E-07 Strontium-90 Ci 7.38E-07 Molybdenum-99 Ci <LLD Iodine-131 Ci <LLD Cesium-134 Ci <LLD Cesium-137 Ci 3.43E-04 Cerium-141
: 1. Total Release                       Ci         1.39E+OC 1. 53E+OO
-Ci <LLD Cerium-144 Ci <LLD Net Unidentified Ci 2.12E-04 Beta Fission & Activation Ci 1.37E-03 Product Total Tritium-----Ci -2.33E+Ol Grand Total Ci 2.33E+Ol 4th QUARTER <LLD l.31E-04 <LLD l.73E-04 <LLD 2.89E-07 2.21E-07 <LLD <LLD <LLD 3.52E-04 <LLD <LLD 2.54E-04 9. llE-04 2.13E+Ol 2.13E+Ol ATTACHMENT 4 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE July -December 1992 February 26, 1993 1 Page Waste Source of Class
: 2. Averaae release rate for oeriod         uCi/sec     l.75E-Ol l.92E-Ol
__ _ PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-4 SOLID WASTE JULY l, 1992 TO DECEMBER 31, 1992 Solidification Container Volume *Total *Principal Agent Type (cu ft) Curies Radionuclides NOTE: No solid Radwaste shipments from July 1. 199t to December 31. 1992. *NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.
: 3. Percent of annual ava MPC           %           l.25E-04 l.37E-04 E.
ATTACHMENT 5 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS July -December February 26, 1993 1 Page 
: 1. Beta Air dose at Site Boundary Due to Noble Gases lTS 3.24.5.2al   mRads       9.31E-06 4.96E-05
*
: 2. Percent limit                      %           9.31E-05 4.96E-04
* LOWER LIMITS OF DETECTION (LLDS) FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (uCi/cc)*
: 3. Gamma Air dose at Site Boundary due to Noble Gases lTS 3.24.5.2a     mRads       1. lOE-07 1. 56E-05
Cr-51 3.47E-13 Mn-54 4.47E-14 Co-58 5.22E-14 Co-60 9.24E-14 Fe-59 1. 23E-13 Zn-65 9.80E-14 Se-75 5.69E-14 Cs-134 3.73E-14 Cs-137 7.82E-14 Zr-95 8.88E-14 Sb-125 1. 37E-13 Nb-95 4.92E-14 Liguid Effluents Nuclide . LLD (uCiLcc}**
: 4. Percent limit                       3           2.20E-OE 3.12E-04 F.
Co-58 1. 98E-07 Mn-54 1.05E-07.
: 1. Maximum Organ Dose to Public Based on Critical Receptors
Fe-59 1. 24E-07 Zn-65 2.32E-07 Co-60 1. 29E-08 Cs-134 1. 64E-07 Cs-137 1. 74E-07 I-131 9.69E-08
          <TS 3. 24. 5. 3l                    mRem       l.OlE-02 l.17E-02
: 2. Percent of limit                   %           l.35E-Ol l.56E-Ol
*NOTE:   Data is reported for 1-131 and I-133 only.
 
PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 I. FISSION GASES              UNITS          3rd QUARTER  4th QUARTER Argon-41                    Ci            <LLD          <LLD Krypton-SS                  Ci            l.07E-Ol      3.77E-02 Krypton-85m                  Ci            <LLD          <LLD Krypton-S7                  Ci            <LLD          <LLD Krypton-SS                  Ci            <LLD          <LLD Xenon-13lm                  Ci            <LLD          <LLD Xenon-133                    Ci          . 4.92E-04     9.95E-Ol Xenon-133m                  Ci            <LLD          <LLD Xenon-135                    Ci              2.37E-04    <LLD Xenon-135m                  Ci            <LLD          <LLD Xenon-138                    Ci            <LLD          <LLD Total for Period            Ci            l.OSE-01      I. 03E+OO
: 2. IODINES                  UNITS          3rd QUARTER  4th QUARTER Iodine-131                  Ci              2.62E-05    S.25E-06 Iodine-132                  Ci           <LLD           <LLD
  *Iodine-133                  Ci             2.SSE-05      7.67E-06 Iodine-134                  Ci           <LLD           <LLD Iodine-135                  Ci           <LLD           <LLD Total for Period            Ci             5.17E-05      l.59E-05
 
PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES
: 3. PARTICULATES
* UNITS         3rd QUARTER     4th QUARTER Manganese-54                  Ci           <LLD              <LLD Cobalt-58                    Ci           <LLD              <LLD Iron-59                      Ci           <LLD              <LLD Cobalt-60                    Ci           <LLD             <LLD Zinc-65                      Ci            <LLD           , <LLD Strontium-89                  Ci            8.lOE-07          l.18E-06 Selenium-90                  Ci            5.15E-07          4.85E-07 Molybdenum-99                Ci            <LLD             <LLD Cesium-134                    Ci            <LLD             <LLD Cesium-137                    Ci            <LLD              2.70E-06 Cerium-141                    Ci            <LLD              <LLD Cerium-144                    Ci            <LLD             <LLD Chromium-SI                  Ci            <LLD              <LLD Net Unidentified              Ci            2.82E-05         3.25E-05 Beta Total                        Ci            2.95E-05          3.69E-05
* Particulates with half lives >8 days.
** Particulates with half-lives <8 days; not reflected in overall isotopic totals
 
ATTACHMENT 3 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REeORT LIQUID EFFLUENTS - SUMMATION OF RELEASES July - December 1992 February 26,,1993 2 Pages
 
I.
                        -------   -- -
                                                              ------  -
PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July 1, 1992 to December 31, 1992 Est Total A. FISSION AND ACTIVATION PRODUCTS            Units        3rd Otr  4th Otr    Error %
: 1. Total release (Not including
          *tritium. oases. alohal                Ci          1.37E-03  9.llE-04
: 2. Average diluted concentration durina oerfod                        uCi/ml      4.14E-11  2.75E-11    9.70E+OO
: 3. Percent of MPC                        %            2.23E-03  2.64E-03 B. TRITIUM
: 1. Total Release                        Ci          2.33E+Ol  2.13E+Ol
: 2. Average diluted concentration durina oeriod                        uCi/ml      7.04E-07  6.44E-07    4.00E+OO
: 3. Percent of MPC                        %            2.35E-02  2.lSE-02
: c. DISSOLVED AND ENTRAINED GASES
: 1. Total Release                            Ci          <LLD      <LLD
: 2. Average diluted concentration durina oeriod                        uCi/ml       N/A      N/A        N/A
: 3. Percent of MPC                       %           NIA      NIA D. GROSS ALPHA RADIOACTIVITY
{Total Rel easel                            Ci          1.93E-07  2.21E-07 E. VOLUME OF WASTE RELEASED
      <Prior to Dilutionl                        Liters      1.65E+05  1. 70E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD                              Liters      3.31E+10  3.31E+10 G. MAXIMUM DOSE COMMITMENT - WHOLEBODY        mRem        7.21E-04  7.SlE-04 Percent of TS 3.24.4.la                     %           4.81E-02 5.0lE-02 H. MAXIMUM DOSE COMMITMENT - ORGAN             mRem         1. 24E-03 1.31E-03 Percent of TS 3.24.4.la Organ limit         %           2.48E-02 2.62E-02
 
                                          --------
PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS July 1. 1992 to December 31. 1992
: 1. NUCLIDES RELEASED              UNITS        3rd QUARTER 4th QUARTER Manganese-54                      Ci          <LLD        <LLD Cabal t                      Ci          5.74E-04    l.31E-04 Iron-59                          Ci        - <LLD        <LLD Cobalt-60                        Ci          2.39E-04    l.73E-04 Zinc-65                          Ci          <LLD        <LLD Strontium-89                      Ci          5.40E-07    2.89E-07 Strontium-90                      Ci          7.38E-07    2.21E-07 Molybdenum-99                    Ci           <LLD        <LLD Iodine-131                        Ci           <LLD        <LLD Cesium-134                        Ci           <LLD        <LLD Cesium-137                        Ci           3.43E-04    3.52E-04 Cerium-141                      - Ci           <LLD        <LLD Cerium-144                        Ci          <LLD        <LLD Net Unidentified                  Ci           2.12E-04    2.54E-04 Beta Fission &Activation              Ci           1.37E-03    9. llE-04 Product Total Tritium- -                --   - Ci -         2.33E+Ol    2.13E+Ol Grand Total                      Ci           2.33E+Ol    2.13E+Ol
 
ATTACHMENT 4 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE July - December 1992 February 26, 1993 1 Page
 
PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-4 SOLID WASTE JULY l, 1992 TO DECEMBER 31, 1992 Waste        Source of          Solidification    Container    Volume  *Total    *Principal Class  --------~W~a=s~te;:;____      Agent            Type      (cu ft) Curies Radionuclides NOTE:      No solid Radwaste shipments from July 1. 199t to December 31. 1992.
*NOTE:      Gamma isotopes are measured quantities; all other isotopes are estimated.
 
ATTACHMENT 5 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS July - December  199~
February 26, 1993 1 Page
 
                        *
* LOWER LIMITS OF DETECTION (LLDS) FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide             LLD (uCi/cc)*
Cr-51               3.47E-13 Mn-54               4.47E-14 Co-58               5.22E-14 Co-60               9.24E-14 Fe-59               1. 23E-13 Zn-65               9.80E-14 Se-75               5.69E-14 Cs-134             3.73E-14 Cs-137             7.82E-14 Zr-95               8.88E-14 Sb-125             1. 37E-13 Nb-95               4.92E-14 Liguid Effluents Nuclide         . LLD (uCiLcc}**
Co-58               1. 98E-07 Mn-54               1.05E-07.
Fe-59               1. 24E-07 Zn-65               2.32E-07 Co-60               1. 29E-08 Cs-134             1. 64E-07 Cs-137             1. 74E-07 I-131               9.69E-08
* From typical stack and/or waste gas decay tank release analysis.
* From typical stack and/or waste gas decay tank release analysis.
typical liquid release analysis.}}
*~From typical liquid release analysis.}}

Revision as of 18:02, 21 October 2019

Semiannual Radioactive Effluent Release & Waste Disposal Rept for Period of July Through Dec 1992. W/930226 Ltr
ML18058B685
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/31/1992
From: Donnelly P
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303090025
Download: ML18058B685 (20)
v • d • e


Text

consumers

  • Power PM Donnelly Safety and Licensing Director POWERIN&

MICHlliAN"S PRO&RESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 26, 1993 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JULY THROUGH DECEMBER 1992 Enclosed is the Semi-Annual Radioactive Effluent Release and Waste Disposal report for the Palisades plant covering the period from July through December 1992.

10 CFR 50.36a has been changed (effective October 2, 1992), to require the Radioactive Effluent Release and Waste Disposal Report be submitted to the NRC once every twelve months instead of semi-annually. However, we are submitting a report covering the last six months of 1992 to provide for continuity with the information that was transmitted for the first six months of the year.

This will be the last semi-annual report. In the future, we will submit an Annual Radioactive Effluent Release and Waste Disposal Report.

The semi-annual report contains references to technical specifications sections. These sections were removed from the technical specifications in Amendment 154 that became effective January 1, 1993.

~!?,#

Safety and Licensing Director CC: Administrator Region III, USNRC Resident Inspector, Palisades Enclosure l) __Q1'L~~----- -------

9_3_0_3_0_9-Q025 921231 r __

( PDR ADOCK 05000255 R PDR A CM5 ENERGY COMPANY

  • Enclosure 1 Consumers Power Company Palisades Plant Docket 50-255 I

SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE '!

AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1992 February 26, 1993 18 Pages

PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July - December 1992 This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Palisades Nuclear Plant during the period of July 1, 1992 through December 31, 1991. The report format is detailed in Plant Technical Specification 6.9.3.lA. Palisades was tripped off-line several times during this reporting period. The following is a summary of the plant operating status between July 1, 1992 and December 31, 1992:

July 1992 The plant began the month at full power, but tripped off-line on 7/01/92 at 1232 due to Turbine Control System problems. The appropriate repairs were made and the plant was placed back on-line on 7/04/92 at 0223. The plant remained on-line until 7/24/92 when it tripped due to low line voltage during a test of the Safety Injection System which caused the Turbine Control System to trip the turbine. A new uninterruptible power supply was installed and the plant was placed back on-line on 7/29/92 at 0632.

August 1992 The plant began the month at full power, but tripped off-line on 8/14/92 at 0017 due to a failed air line to a feedwater regulating valve. In addition, due to problems with the Turbine Control System, the plant was not placed back on-line until 8/17/92 at 1749. The plant was taken back off-line during a heat balance test at 25% power on 8/17/92 at 2017 due to a large turbine hydraulic fluid leak.

The p1ant was p1aced back on-1i ne on 8/18/92 at 0230. The p1ant ran until 8/25/92 when it tripped off-1 i ne due to a failed so 1enoi d in the preferred AC Bus powering engineering safeguards system electrical loads coupled with an undetected blown fuse. Again, repairs were made and plant was placed back on-line on 8/27/92 at 0417.

September 1992 The plant began the month at full power, but was de-escalated on 9/18/92 and then taken off-line on 9/19/92 at 0953 to facilitate the investigation of a personnel injury accident. The plant was placed back on-line on 9/28/92 at 0622 following the completion of the accident investigation and repairs to various valves due to turbine overspeed testing.

October 1992 The plant began the month at full power, but tripped off-line on 10/30/92 at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> due to Turbine Control System problems.

November 1992 The plant began the month off-line. The plant made several modifications to the Turbine Control System and the plant was placed back on-line on 11/08/92 at 2002.

The plant operated at full power the remainder of the month.

December 1992 The plant operated at full power the entire month.

1. Supplemental Information A. Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Table HP 10.5-1 (Attachment 1).

B. Abnormal Releases On November 9, 1992, there were two noble gas incursions into the Auxillary Building. Radiation monitor RIA-1809 alarmed on High Alarm and tripped V-14B and V-10 ventilation fans during each occurrance.

In addition, the friskers on 590' Auxillary Building pegged high for a period of time and the continuous area monitor showed a large spike.

The root cause of this event(s) was identified as a valve, MV-WG603, being inadvertantly left partially open on the Vacumn Degasifier system. The identified valve was closed by the Operations Department.

The details of this event are recorded in a Deviation Report, D-Pal-92-265. The amount of noble gas released was quantified through our RGEM Stack Gas System weekly analysis. The results showed a release of 7.12E-Ol curies of XE-133 and is documented in batch card 92-046-ST.

C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents is provided in Attachment 5.

D. Radioactive Effluent Monitoring Instrumentation:

1) Waste Gas Decay Tank Vent Flow Indicator (FI-1121)

Technical Specification 3.24.2.l(b) requires that when a radioactive gaseous effluent monitoring instrument channel becomes inoperable, best efforts must be made to return the instrument to operable status within 30 days and if unsuccessful, report the incident in the next Semi annua 1 Radioactive Effluent Report. Technical Specification- Table 3.24-2.l(b) further stipulates that radioactive effluent releases may continue to be made with less than the required amount of operable channels providing that the flow rate is estimated at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for continuous releases or fours for batch releases.

On September 29, 1992, it was determined that the flow indicator, FI-1121 was inoperable. As required per Health

Physics Procedure HP 6.6, if FI-1121 is inoperable during Waste Gas Decay Tank batch releases, releases may continue provided

  • the flow rate is estimated by the Primary Side Auxiliary Operator at least every four hours during batch rel eases. These calculations were performed , as necessary, for batch releases during the period of September 29,1992 and December 11, 1992.

The root cause of the problem appears to be the fact that when a flow is applied to the rotameter the "float pin" oscillates violently which resulted in the "float pin" bending. The float pin was straightened and an adjustment to PCV-1123 was made.

In addition, Instrument &Control ordered new parts for the flow indicator. The flow indicator was declared operable on December 11, 1992.

The corrective solution to this reliability problem is to replace the instrument with a new flow indicator with a wider flow range. This corrective action has been turned over to the Instrument & Control System Engineering Group per work order 24204932.

During the period of inoperabil ity, all of the Technical Specification sampling requirements as stated in Table 3.24-2(1.b) were met.

A detailed report of the work performed on FI-1121 is documented in work order 24202520.

2) Main Steam Gross Gamma Activity Monitors (RIA 2323 and 2324) the main steam line radiation monitors remained inoperable from July 1, 1992 to August 28, 1992 due to EEQ concerns as described in our January 1992 - June 1992 Semi-Annual Effluent Report.

A discussion between Palisades Licensing, the NRC Project Manager and the Senior Resident Inspector was held as a result of our need to remove our preplanned alternate method of monitoring (Jordan Radguns) to install our new more reliable backup monitors, which would replace the Jordan Radguns. An agreement was made that pending the NRC review for our request for exemption to the requirements of RG 1.97 for these instruments, we can consider the main steam 1ine monitors operable and take the action we consider appropriate to replace the Jordan Radguns.

The main steam line monitors were declared operabl~ on August 28, 1992 and the new backup monitors were installed.

2. Gaseous Effluents Table HP 10.5-2 (Attachment 2) lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 1.50E-03% of the total release.
3. Liquid Effluents Table HP 10.5-3 (Attachment 3) lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was l.04E-03% of the total .release.

The Sr-89 and Sr-90 values reported for the third quarter liquid effluent is an average of the first, second and fourth quarter T-91 batch analysis results. The third quarter T-91 batch sample (92-021-R) was not sent to our vendor for analysis and has consequently been determined to be lost. A Deviation Report D-PAL-93-014 was generated to identify and evaluate this violation of Technical Specification Section 4.24.3.1.a and Table 4.24.3.

4. Solid Waste There were no solid waste shipments from July 1 to December 31, 1992 (Table HP 10.5-4, Attachment 4).
5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follows:

A. The offsite air doses at the site boundary (0.48 SSE) due to noble gases were 9.31E-06 millirad beta and l.lOE-07 millirad gamma for the third quarter; and 4.96E-05 millirad beta and l.56E-05 gamma for the fourth quarter. The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta occurred during the fourth quarter, being 3.54E-05 millirads beta and for gamma during the fourth quarter being l.12E-05 millirads gamma.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate and iodine) was the child bone for the third and fourth quarters. Doses were l.OlE-02 and l.17E-02 millirem, respectively.

C. Integrated total body doses to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50 miles from the site boundary were: 6.86E-03 person-Rem and 6.51E-06 millirem for the third quarter; and 7. 79E-03 person-Rem and 7. 39E:..06 mi11 i rem for the fourth quarter.

D. The maximum total body dose to an individual in unrestricted water-rel ated exposure pathways was 7.21E-04 millirem (adult) and 7.51E-04 millirem (adult) for the third and fourth quarters, respectively.

The maximum organ doses were l.24E-03 millirem (teenage bone) for the third quarter and l.31E-03 millirem (both teenage and child bone) for the fourth quarter.

E. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50 miles from the site boundary were: 2.75E-03* person-Rem and 2.62E-06 millirem for the third quarter; and 2.86E-03 person-Rem and 2.72E-06 millirem for the fourth quarter.

6. Process Control Program (PCP}
7. Offsite Dose Calculation Manual (ODCMl No changes were made to the Offsite Dose Calculation Manual.

v ATTACHMENT I Consumers Power Company Pali sades Pl ant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES July - December 1992 February 26, 1993 I Page

I

  • TABLE HP 10.5-1 PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

. BATCH RELEASES July 1. 1992 to December 31. 1992 A. GASEOUS Units 3rd Qtr 4th Qtr Number of Releases 3 5 Total Release Time Minutes 1785 1330 Maximum Release Time Minutes 1065 453 Average Release Time Minutes 595 266 Minimum Release Time Minutes 270 137 B. LIQUID Units 3rd Qtr 4th Qtr Number of Releases 1 1 Total Release Time Minutes 473 550 Maximum Release Time Minutes 473 550 Average Release Time Minutes 473 550 Minimum Release Time Minutes 473 550

ATTACHMENT 2 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES July - December 1992 February 26, 1993 3 Pages

PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 Est Tota 1 A. FISSION AND ACTIVATION GASES Units 3rd Otr 4th Otr Error 3

1. Total release Ci l.OBE-01 1. 03E+OO
2. Averaae release rate for oeriod uCi/sec 1.36E-02 1.30E-01 6.60E+OO
3. Percent of annual ava MPC 3 6.50E-06 6.lBE-05 B. IODINES
1. Total Iodine Ci 5.17E-05 1. 59E-05 *
2. Averaae release rate for aeriod uCi/sec 6.51E-Of 2.0lE-06 2.82E+Ol
3. Percent of annual ava MPC 3 5. 86E-OE 1. 84E-06
c. PARTICULATES
1. Particulates with half-life

>8 davs Ci 2.95E-05 3.69E-05

2. Averaae release rate for aeriod uCilsec 3.72E-06 4.64E-06 N/A
3. Percent of annual ava MPC  % 1. 73E-O~ 2.00E-05
4. Gross aloha radioactivitv Ci 2.0lE-05 2.00E-05 D. TRITIUM
1. Total Release Ci 1.39E+OC 1. 53E+OO
2. Averaae release rate for oeriod uCi/sec l.75E-Ol l.92E-Ol
3. Percent of annual ava MPC  % l.25E-04 l.37E-04 E.
1. Beta Air dose at Site Boundary Due to Noble Gases lTS 3.24.5.2al mRads 9.31E-06 4.96E-05
2. Percent limit  % 9.31E-05 4.96E-04
3. Gamma Air dose at Site Boundary due to Noble Gases lTS 3.24.5.2a mRads 1. lOE-07 1. 56E-05
4. Percent limit 3 2.20E-OE 3.12E-04 F.
1. Maximum Organ Dose to Public Based on Critical Receptors

<TS 3. 24. 5. 3l mRem l.OlE-02 l.17E-02

2. Percent of limit  % l.35E-Ol l.56E-Ol
  • NOTE: Data is reported for 1-131 and I-133 only.

PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES July 1. 1992 to December 31. 1992 I. FISSION GASES UNITS 3rd QUARTER 4th QUARTER Argon-41 Ci <LLD <LLD Krypton-SS Ci l.07E-Ol 3.77E-02 Krypton-85m Ci <LLD <LLD Krypton-S7 Ci <LLD <LLD Krypton-SS Ci <LLD <LLD Xenon-13lm Ci <LLD <LLD Xenon-133 Ci . 4.92E-04 9.95E-Ol Xenon-133m Ci <LLD <LLD Xenon-135 Ci 2.37E-04 <LLD Xenon-135m Ci <LLD <LLD Xenon-138 Ci <LLD <LLD Total for Period Ci l.OSE-01 I. 03E+OO

2. IODINES UNITS 3rd QUARTER 4th QUARTER Iodine-131 Ci 2.62E-05 S.25E-06 Iodine-132 Ci <LLD <LLD
  • Iodine-133 Ci 2.SSE-05 7.67E-06 Iodine-134 Ci <LLD <LLD Iodine-135 Ci <LLD <LLD Total for Period Ci 5.17E-05 l.59E-05

PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES

3. PARTICULATES
  • UNITS 3rd QUARTER 4th QUARTER Manganese-54 Ci <LLD <LLD Cobalt-58 Ci <LLD <LLD Iron-59 Ci <LLD <LLD Cobalt-60 Ci <LLD <LLD Zinc-65 Ci <LLD , <LLD Strontium-89 Ci 8.lOE-07 l.18E-06 Selenium-90 Ci 5.15E-07 4.85E-07 Molybdenum-99 Ci <LLD <LLD Cesium-134 Ci <LLD <LLD Cesium-137 Ci <LLD 2.70E-06 Cerium-141 Ci <LLD <LLD Cerium-144 Ci <LLD <LLD Chromium-SI Ci <LLD <LLD Net Unidentified Ci 2.82E-05 3.25E-05 Beta Total Ci 2.95E-05 3.69E-05
  • Particulates with half lives >8 days.
    • Particulates with half-lives <8 days; not reflected in overall isotopic totals

ATTACHMENT 3 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REeORT LIQUID EFFLUENTS - SUMMATION OF RELEASES July - December 1992 February 26,,1993 2 Pages

I.

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PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July 1, 1992 to December 31, 1992 Est Total A. FISSION AND ACTIVATION PRODUCTS Units 3rd Otr 4th Otr Error %

1. Total release (Not including
  • tritium. oases. alohal Ci 1.37E-03 9.llE-04
2. Average diluted concentration durina oerfod uCi/ml 4.14E-11 2.75E-11 9.70E+OO
3. Percent of MPC  % 2.23E-03 2.64E-03 B. TRITIUM
1. Total Release Ci 2.33E+Ol 2.13E+Ol
2. Average diluted concentration durina oeriod uCi/ml 7.04E-07 6.44E-07 4.00E+OO
3. Percent of MPC  % 2.35E-02 2.lSE-02
c. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci <LLD <LLD
2. Average diluted concentration durina oeriod uCi/ml N/A N/A N/A
3. Percent of MPC  % NIA NIA D. GROSS ALPHA RADIOACTIVITY

{Total Rel easel Ci 1.93E-07 2.21E-07 E. VOLUME OF WASTE RELEASED

<Prior to Dilutionl Liters 1.65E+05 1. 70E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 3.31E+10 3.31E+10 G. MAXIMUM DOSE COMMITMENT - WHOLEBODY mRem 7.21E-04 7.SlE-04 Percent of TS 3.24.4.la  % 4.81E-02 5.0lE-02 H. MAXIMUM DOSE COMMITMENT - ORGAN mRem 1. 24E-03 1.31E-03 Percent of TS 3.24.4.la Organ limit  % 2.48E-02 2.62E-02

PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-3 LIQUID EFFLUENTS July 1. 1992 to December 31. 1992

1. NUCLIDES RELEASED UNITS 3rd QUARTER 4th QUARTER Manganese-54 Ci <LLD <LLD Cabal t Ci 5.74E-04 l.31E-04 Iron-59 Ci - <LLD <LLD Cobalt-60 Ci 2.39E-04 l.73E-04 Zinc-65 Ci <LLD <LLD Strontium-89 Ci 5.40E-07 2.89E-07 Strontium-90 Ci 7.38E-07 2.21E-07 Molybdenum-99 Ci <LLD <LLD Iodine-131 Ci <LLD <LLD Cesium-134 Ci <LLD <LLD Cesium-137 Ci 3.43E-04 3.52E-04 Cerium-141 - Ci <LLD <LLD Cerium-144 Ci <LLD <LLD Net Unidentified Ci 2.12E-04 2.54E-04 Beta Fission &Activation Ci 1.37E-03 9. llE-04 Product Total Tritium- - -- - Ci - 2.33E+Ol 2.13E+Ol Grand Total Ci 2.33E+Ol 2.13E+Ol

ATTACHMENT 4 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE July - December 1992 February 26, 1993 1 Page

PALISADES PLANT/SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE HP 10.5-4 SOLID WASTE JULY l, 1992 TO DECEMBER 31, 1992 Waste Source of Solidification Container Volume *Total *Principal Class --------~W~a=s~te;:;____ Agent Type (cu ft) Curies Radionuclides NOTE: No solid Radwaste shipments from July 1. 199t to December 31. 1992.

  • NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.

ATTACHMENT 5 Consumers Power Company Palisades Plant SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS July - December 199~

February 26, 1993 1 Page

  • LOWER LIMITS OF DETECTION (LLDS) FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (uCi/cc)*

Cr-51 3.47E-13 Mn-54 4.47E-14 Co-58 5.22E-14 Co-60 9.24E-14 Fe-59 1. 23E-13 Zn-65 9.80E-14 Se-75 5.69E-14 Cs-134 3.73E-14 Cs-137 7.82E-14 Zr-95 8.88E-14 Sb-125 1. 37E-13 Nb-95 4.92E-14 Liguid Effluents Nuclide . LLD (uCiLcc}**

Co-58 1. 98E-07 Mn-54 1.05E-07.

Fe-59 1. 24E-07 Zn-65 2.32E-07 Co-60 1. 29E-08 Cs-134 1. 64E-07 Cs-137 1. 74E-07 I-131 9.69E-08

  • From typical stack and/or waste gas decay tank release analysis.
  • ~From typical liquid release analysis.
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