ML18065B199
| ML18065B199 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/31/1997 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18065B198 | List: |
| References | |
| NUDOCS 9804070014 | |
| Download: ML18065B199 (19) | |
Text
ENCLOSURE CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 1997 ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT 182 Pages
PALISADES NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY - DECEMBER 1997 This report provides information relating to radioactive effluent releases and solid radioactive waste shipments at the Palisades Nuclear Plant during the period of January 1, 1997 through December 31, 1997. The report is required by 10 CFR 50.36a(a)(2) and Plant Technical Specification 6.6.3.
Plant Operating History Palisades was taken off line January 5, 1997, to repair a broken connector in the main generator isophase bus. The plant was returned to service at 14:00 on January 6, 1997. Later that same day, the plant was shut down to repair main steam isolation valves and replace a primary coolant pump seal. The plant was returned to service January 15, 1997. The plant was taken off line on January 23, 1997, due to high temperature indications in the flexible connectors on the Z-phase of the main generator, and was returned to service on February 8, 1997. The Plant was taken off line from February 17 to February 19, 1997, to repair a hydrogen leak on the main generator. On September 30, 1997, the plant was taken off line due to increased primary coolant system leakage. Repairs were made to a weld on the primary coolant pump bleed-off line, and the plant was returned to service on October 15, 1997. Palisades was on line for the remainder of 1997.
- 1.
Supplemental Information A.
Batch Releases Information relating to batch release of gaseous and liquid effluents is provided in Attachment 1.
B.
Abnormal Releases RV-1114 Release (C-PAL-97-1142)
On August 12, 1997, at 13:08 an abnormal release of Noble Gas occurred in the vicinity of Waste Gas Compressor C-50A, through an improperly gagged relief valve (RV-1114).
While maintenance was being performed on compressor C-50A, a Chemistry technician took a sample of the Volume Control Tank gases.
1
C.
D.
- 1.
This sampling activity pressurized the Waste Gas Surge Tank (WGST) with radioactive gases. In conjunction with the WGST being pressurized, Mechanical Maintenance had used an incorrect tool to gag RV-1114. This resulted in the release of radioactive gases from the WGST into the Waste Gas Compressor Room, which were ultimately released through the Plant Stack System (as detected by the stack gas monitor). A conservative estimate determined that a total of 7.34E-01 Curies were released. The release was quantified and documented in Stack Gas Record 97-033.
Lower Limits of Detection (LLD's) for gaseous and liquid effluents are provided for specific radionuclides in Attachment 2.
Radioactive Effluent Monitoring Instrumentation:
Service Water Monitor, RIA-0833, Out Of Service For 49 Days.
The ODCM, Appendix A, Table C-1, requires that when a radioactive liquid 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 Radioactive Effluent Release Report. The ODCM, Appendix A, Table C-1, further stipulates that effluent releases via the RIA-0833 pathway may continue to be made with less than the required number of operable channels providing that, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, grab samples are collected and analyzed for radioactivity for principle gamma emitters and 1-131.
On October 21, 1997, RIA-0833 was declared inoperable due to erratic readings with spiking up to 4000 cpm over background. At this time it was decided to replace the RIA-0833 monitor per work order (WO) 24711552 and Functional Equivalent Substitution (FES) FES-97-047, rather than trouble shoot the existing system. Over the next 20 days, a new digital monitor with corresponding detector were installed and wired in place. On November 11, 1997, the installation phase was complete and the system
- rendered functional. However, during the calibration stage, the detector was damaged and a new detector had to be procured, causing a five day delay.
The monitor was calibrated successfully on November 28, 1997. All associated modification documentation and procedural revisions were completed by December 8, 1997, when the RIA-0833 monitor was returned to operable status.
During the period of RIA-0833 inoperability, all of the ODCM 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sampling and analysis requirements as stated in Table C-1 were met.
2
- 2.
Gaseous Effluents lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 1.35E-04% of the total release.
Gaseous effluents released during 1997 were a factor of 3 lower than those of 1996. This decrease is directly related to the reduced noble gas activity in the primary coolant system. The reduced noble gas activity is a direct result of the improved fuel integrity over fuel cycle 13.
- 3.
Liguid Effluents
- 4. lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 9.43E-05% of the total release.
Overall liquid effluents released during 1997 were 60% higher than those of 1996.
Liquid release volumes during 1997 were similar to those of 1996. However, the effectiveness of the demineralizer for processing liquid waste was reduced during the first quarter of 1997 because the resin bed could not be changed out. The resin bed could not be replaced due to problems associated with the resin transfer system and holdup tank. The liquid processing system was restored to optimal status during the second quarter of 1997.
Solid Waste summarizes all solid radwaste classification, sources, volume shipped, curie, and nuclide content. All radwaste shipments were made to Barnwell Waste Management Facility in Barnwell, South Carolina.
- 5.
Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The quarterly values for curies released were input for each nuclide and summarized as follows:
A.
The offsite air doses at the site boundary (0.48 mi SSE) due to noble gases were:
First Quarter -
4.15 E-04 millirad beta and 1.36 E-04 millirad gamma Second Quarter -
1.85 E-04 millirad beta and 6.35 E-05 millirad gamma 3
Third Quarter -
Fourth Quarter -
2.93 E-04 millirad beta and 1.02 E-04 millirad gamma 4.48 E-04 millirad beta and 1.56 E-04 millirad gamma The maximum noble gas offsite air dose to the nearest residence (0.50 mi S) for beta and gamma occurred during the fourth quarter, being 3.00 E-04 millirads beta and 1.05E-04 millirads gamma.
B.
The most restrictive organ in terms of 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 first quarter, and the child thyroid for the second, third and fourth quarters. Doses were:
First Quarter -
Second Quarter -
Third Quarter -
Fourth Quarter -
1.14 E-02 millirem 3.28 E-03 millirem 4.46 E-03 millirem 3.45 E-03 millirem 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, respectively:
First Quarter -
Second Quarter-Third Quarter -
Fourth Quarter -
1.36 E-02 person-Rem and 1.17 E-05 millirem 1.00 E-02 person-Rem and 8.62 E-06 millirem 1.17 E-02 person-Rem and 1.01 E-05 millirem 9.49 E-03 person-Rem and 8.18 E-06 millirem D.
The maximum total body dose to an individual in unrestricted water-related exposure pathways was:
First Quarter -
Second Quarter-Third Quarter -
Fourth Quarter -
4.50 E-03 millirem (adult) 6.22 E-04 millirem (adult) 7.24 E-04 millirem (adult) 8.33 E-08 millirem (adult)
The maximum organ doses were:
First Quarter -
Second Quarter-Third Quarter -
Fourth Quarter -
7.32 E-03 millirem (teenage liver) 9.91 E-04 millirem (teenage liver) 1.14 E-03 millirem (teenage liver) 8.33 E-08 millirem (adult) 4
E.
The calculated organ dose for the fourth quarter was the same value as the whole body dose for all organs, since the only isotope released in this quarter was tritium.
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, respectively:
First Quarter -
Second Quarter-Third Quarter -
Fourth Quarter -
1.68 E-02 person-Rem and 1.45 E-05 millirem 2.59 E-03 person-Rem and 2.23 E-06 millirem 3.05 E-03 person-Rem and 2.63 E-06 millirem 9.56 E-07 person-Rem and 8.24 E-10 millirem
- 6.
There was no revision to the Process Control Program in 1997.
- 7.
Offsite Dose Calculation Manual (ODCM) contains the ODCM, Revision 11, along with the safety evaluation per the requirements of Technical Specification 6.5.1.c.3.
There were several changes to the ODCM during this reporting period as a result of use of the 1996 Land Use Survey. The Land Use Survey is utilized to ensure that the impact of effluent dose is accurate. These changes (detailed in #'s 1-3 below) will maintain the level of radioactive effluent control required by 10 CFR 20.1301, 4 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and do not affect any monitor or release set point calculations.
- 1)
- 2)
- 3)
Update of Table 1.4, 1996 Palisades Land Use Census Update of Table 1.4a; 1996 Palisades Land Use Census - Critical Receptor Items Update of Table 1.9; 1997 Palisades Gaseous Design - Objective Annual Quantities 5
ATTACHMENT 1 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January - December 1997 1 Page
A.
B.
TABLE HP 10.5-1 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT BATCH RELEASES January 1. 1997 to December 31. 1997 GASEOUS Units 1st Qtr 2nd Qtr Number of Releases 8
4 Total Release Time Minutes 917 487 Maximum Release Time Minutes 160 165 Average Release Time Minutes 115 122 Minimum Release Time Minutes 65 71 LIQUID Units 1st Qtr 2nd Qtr Number of Releases 3
1 Total Release Time Minutes 1222 443 Maximum Release Time Minutes 463 443 Average Release Time Minutes 407 443 Minimum Release Time Minutes 378 443 3rd Qtr 4th Qtr 3
10 313 983 141 150 104 98 80 58 3rd Qtr 4th Qtr 1
0 564 N/A 564 N/A 564 N/A 564 N/A
ATTACHMENT 2 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE REPORT LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS January - December 1997 1 Page
LOWER LIMITS OF DETECTION (LLDs} FOR PALISADES EFFLUENTS Gaseous Effluents Nuclide LLD (uci/cc)*
Cr-51 1.77E-13 Mn-54 2.46E-14 Co-58 2.86E-14 Fe-59 6.00E-14 Co-60 4.19E-14 Stack Gas Analysis Zn-65 3.96E-14 97-005-St Se-75 1.78E-14 Nb-95 2.23E-14 Zr-95 4.01 E-14 Mo-99 6.40E-14 Sb-125 3.05E-14 1-131 2.80E-14 1-133 4.13E-14 r*
Cs-134 2.19E-14 Cs-137 2.19E-14 Ce-141 2.04E-14 Ce-144 9.73E-14 Liquid Effluents Nuclide LLD (uci/I)**
Mn-54 6.62E-08 Fe-59 1.91 E-07 Co-58 5.55E-08 Co-60 8.76E-08 Zn-65 1.46E-07 Liquid Batch Release Mo-99 5.56E-07 97-001-R 1-131 9.01E-08 Cs-134 5.97E-08 Cs-137 1.29E-07 Ce-141 1.22E-07 Ce-144 4.69E-07
- From a typical Stack release analysis.
- From a typical Liquid release analysis.
ATTACHMENT 3 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January - December 1997 3 Pages l
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES January 1, 1997 to December 31, 1997 A. FISSION AND ACTIVATION GASES Units 1st Qtr 2nd Qtr 3rd Qtr
- 1. Total release Ci 6.84E+OO 3.09E+OO 4.90E+OO
- 2. Average release rate for period
µCi/sec 8.79E-01 3.93E-01 6.16E-01
- 3. Percent of annual avg EC 3.22E-04 1.51E-04 2.38E-04 B. IODINES
- 1. Total Iodine*
Ci 5.25E-04 8.63E-04
- 1. 34E-03
- 2. Average release rate for period
µCi/sec 6.74E-05
- 1. lOE-04
- 1. 69E-04
- 3. Percent of annual avg EC 2.58E-05 4.27E-05 7.26E-05 C. PARTICULATES
- 1. Particulates with half-life
> 8 days Ci 5.48E-05 6.96E-06
- 1. 92E-05
~- Average release rate for period
µCi/sec 7.04E-06 8.85E-07 2.42E-06
- 3. Percent of annual avg EC 1.28E-04 2.31E-05 1.81E-05
- 4. Gross alpha radioactivity Ci 1.15E-05 1.17E-06 1.16E-06 D. TRITIUM
- 1. Total Release Ci 2.69E+OO 2.76E+OO 3.28E+OO
- 2. Average release rate for period
µCi/sec 3.46E-01 3.51E-01 4.13E-01
- 3. Percent of annual avg EC 6.29E-04 6.38E-04 7.51E-04 E. AIRDOSE AT SITE
- 1. Beta Airdose at Site Boundary Due to Noble Gases (ODCM App A III.C) mrads 4.15E-04 1.85E-04 2.93E-04
- 2. Percent limit 4.15E-03 l.85E-03 2.93E-03
- 3. Gamma Airdose at Site Boundary Due to Noble Gases (ODCM App A III.C) mrads 1.36E-04 6.35E-05 l.02E-04
- 4. Percent limit 2.72E-03 1.27E-03 2.04E-03 F. ORGAN DOSE
- 1. Maximum Organ Dose to Public Based on Critical Receptors (ODCM App A III.D) mrem 1.14E-02 3.28E-03 4.46E-03
- 2. Percent of limit 1.52E-01 4.37E-02 5.95E-02
- NOTE:
Data is reported for I-131 and I-133 only.
Est Total 4th Qtr Error %
7.42E+OO
- 4. 04 9.34E-01 3.67E-04 7.54E-04 6.37 9.48E-05 4.85E-05 5.40E-06 18.37 6.79E-07
- 1. 79E-05 9.14E-07 2.62E+OO 3.30E-01 6.00E-04 4.48E-04 4.48E-03 1.56E-04 3.12E-03 3.45E-03 4.60E-02
- 1.
- 2.
TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS January 1. 1997 to December 31, 1997 FISSION GASES Units 1st Qtr 2nd Qtr Argon-41 Ci
<LLD
<LLD Krypton-85 Ci 1.20E-01
<LLD Krypton-85m Ci
<LLD 4.54E-04 Krypton-87 Ci 8.93E-04 4.59E-04 Krypton-88 Ci
<LLD
<LLD Xenon-131m Ci 6.36E-03 4.00E-04 Xenon-133 Ci 6.71E+OO 3.08E+OO Xenon-133m Ci
<LLD
<LLD Xenon-135 Ci 2.29E-03 3.37E-03 Xenon-135m Ci 4.90E-03 6.51E-03 Xenon-138 Ci
<LLD
<LLD Total for Period Ci 6.84E+OO 3.09E+OO IODINES Iodine-131 Ci 1.45E-04 2.46E-04 Iodine-132 Ci
<LLD
<LLD Iodine-133 Ci 3.80E-04 6.17E-04 Iodine-134 Ci
<LLD
<LLD Iodine-135 Ci
<LLD
<LLD Total for Period Ci 5.25E-04 8.63E-04 3rd Qtr 4th Qtr
<LLD 5.28E-04
<LLD 2.56E-02 4.44E-04 4.98E-04
- 1. 25E-03 8. llE-04
<LLD
<LLD
<LLD 4.91E-02 4.88E+OO 7.28E+OO
<LLD 9.88E-03 4.03E-03 3.61E-02 8.47E-03 1.13E-02 2.44E-03 5.34E-03 4.90E+OO 7.42E+OO 4.58E-04 3.42E-04
<LLD
- 1. OlE-03 8.86E-04 4.12E-04
<LLD
<LLD
<LLD
<LLD 1.34E-03 1. 76E-03
- 3.
PARTICULATES*
Manganese-54 Cobalt-58 Iron-59 Cobalt-60 Zinc-65 Strontium-89 Strontium-90 Molybdenum-99 Cesium-134 Cesium-137 Cerium-141 Cerium-144 TABLE HP 10.5-2 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT Units 1st Qtr 2nd Qtr Ci
<LLD
<LLD Ci 2.13E-05
<LLD Ci
<LLD
<LLD Ci
<LLD
<LLD Ci
<LLD
<LLD Ci 5.80E-07 9.80E-07 Ci 9.85E-07 5.75E-07 Ci
<LLD
<LLD Ci
<LLD
<LLD Ci
<LLD
<LLD Ci
<LLD
<LLD Ci
<LLD
<LLD Net unidentified beta Ci 3.19E-05 5.40E-06 Total 5.48E-05 6.96E-06
- Particulates with half-lives> 8 days.
3rd Qtr 4th Qtr
<LLD
<LLD
<LLD 1.19E-07
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
- 1. 46E-06 6.05E-07 4.45E-07 4.00E-07
<LLD
<LLD
<LLD
<LLD 1.34E-05
<LLD
<LLD
<LLD
<LLD
<LLD 3.86E-06 4.28E-06 1.92E-05 5.40E-06
ATTACHMENT 4 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES January - December 1997 2 Pages
TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January 1. 1997 to December 31. 1997 A. FISSION AND ACTIVATION PRODUCTS Units Ist Qtr 2nd Qtr 3rd Qtr
- 1. Total release (not including tritium. gases.
alpha)
Ci 9.57E-03 8.64E-04 4.90E-04
- 2. Average release rate for period
µCi /me 3.92E-10
- 3. 48E-11
- 1. 95E-ll
- 3. Percent of EC 1.13E-02 1.28E-03 1.37E-03 B. TRITIUM
- 1. Total Release Ci 7.74E+Ol 2.73E+Ol 3.31E+Ol
- 2. Average diluted concentration during period
µCi /me 3.17E-06 1.lOE-06 1.32E-06
- 3. Percent of EC 3.17E-Ol l.lOE-01 1.32E-Ol
. DISSOLVED AND ENTRAINED GASES
- 1. Total Rel ease Ci 0.000 0.000 0.000
- 2. Average diluted concentration during period
µCi !me N/A N/A N/A
- 3. Percent of EC N/A NIA N/A D. GROSS ALPHA RADIOACTIVITY (Total Release)
Ci
- 1. 03E-06 l.92E-07 2.70E-07 E. VOLUME OF WASTE RELEASED (Prior to Dilution)
Liters 4.43E+05
- 1. 48E+05 l.70E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.44E+l0 2.48E+l0 2.51E+l0 G. MAXIMUM DOSE COMMITMENT -
WHOLEBODY mrem 4.50E-03 6.22E-04 7.24E-04 Percent of ODCM App A III.H limit 3.00E-01 4.15E-02 4.83E-02 H. MAXIMUM DOSE COMMITMENT -
ORGAN mrem 7.32E-03 9.91E-04 1.14E-03 Percent of ODCM App A III.H limit l.46E-Ol l.98E-02 2.28E-02 Est Total 4th Qtr Error %
0.000 6.76 N/A N/A 3.SOE-02 1.58E-09 4.01 1.58E-04 0.000 N/A N/A N/A 0.000 0.000 2.40E+l0 8.33E-08 5.55E-06 8.33E-08 l.67E-06
- 1.
TABLE HP 10.5-3 PALISADES PLANT RADIOACTIVE EFFLUENT REPORT LIQUID EFFLUENTS January l, 1997 to December 31, 1997 NUCLIDES RELEASED Units Ist Qtr 2nd Qtr 3rd Qtr Manganese-54 Ci
- 1. 76E-04
<LLD
<LLD Cobalt-58 Ci 4.39E-03 2.48E-04 3.75E-05 Iron-59 Ci
<LLD
<LLD
<LLD Caba lt-60 Ci
<LLD
<LLD Strontium-89 Ci 1.60E-06 4.29E-07 3.06E-07 Strontium-90 Ci
- 1. 03E-05 4.44E-06 2.21E-06 Molybdenum-99 Ci
<LLD
<LLD
<LLD Iodine-131 Ci
<LLD
<LLD
<LLD Cesium-134 Ci 3.86E-04 4.99E-05 5.55E-05 Cesium-137 Ci 1.31E-03 1.80E-04 2.16E-04 Niobium-95 Ci
- 1. 59E-04
<LLD
<LLD Sil ver-110m Ci 8.24E-05
<LLD
<LLD Antimony-125 Ci
- 1. 48E-03 2.23E-04
<LLD Net unidentified beta Ci 1.30E-04 0.000 0.000 Fission & Activation Product Total Ci 9.57E-03 8.64E-04 4.90E-04 Tritium Ci 7.74E+Ol 2.73E+Ol 3.31E+Ol Grand Total Ci 7.74E+Ol 2.73E+Ol 3.31E+Ol 4th Qtr
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0.000 0.000 3.80E-02 3.80E-02
ATTACHMENT 5 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January - December 1997 1 Page
SOLID WASTE January 1. 1997 To December 31, 1997 Waste Source of Solidification Container Volume
- Total
- Principal Class Waste Agent Type (cu ft)
Curies Radionuclides AU DAW N/A LSA 348.2 0.6 Co-60, Cs-137.
Co-58, Cs-134.
Mn-54, Fe-55, Ni-63 AS DAW N/A HIC 195.2 5.9 Same as above AU Evap Bottoms Asphalt LSA
Ni-63 AS Evap Bottoms N/A LSA 614.4 2.5 Same as above B
Resins N/A HIC 202.1 86.8 Co-60, Cs-137, Co-58, Cs-134.
Mn-54, Sb-125.
Resins N/A HIC 202.1 180.8 Same as above c
Irr Hardware N/A Steel 14.6 6077. 0 Co-60, Co-58, Liner Mn-54, Fe-55.
Ni-63 B
Filters N/A HIC 83.4 20.2 Co-60. Mn-54, Cs-134, Ni-63, Cs-137, Fe-55, Ru-106, Ag-llOm, Sbl25, Sr-90 TOTAL 1752.8 6374.3
- NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.