ML18038A663
| ML18038A663 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1989 |
| From: | Joseph Willis NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMP53853, NUDOCS 8909130020 | |
| Download: ML18038A663 (58) | |
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'I D%1BUTION DEMONSTION SYFI'EM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)'CCESSION NBR:8909130020 DOC.DATE: 89/06/30 NOTARIZED: NO FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe AUTH.NAME AUTHOR AFFILIATION WILLIS,J.L.
Niagara Mohawk Power Corp.
RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000220 R
SUBJECT:
"Nine Mile Point Nuclear Station Unit 1 Semiannual Radioactive Effluent Release Rept Jan-June 1989."
DISTRIBUTION CODE:
IE48D COPIES RECEIVED:LTRg ENCL +
SIZE:
CRQ TITLE: 50.36a(a)(2),Semiannual Effluent Release Reports NOTES:
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LI7 Nl'AGARA H O MOHAWK NMP53853 NINE MILE POINT NUCLEAR STATION/P.O. BOX 32 LYCOMING, NEW YORK 13093/TELEPHONE (315) 343-2110 August 30, 1989 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Re:
Nine Mile Point Unit Nl Docket No. 50-220 DPR-63 Gentlemen:
In conformance with the Nine Mile Point Nuclear Station Unit Nl Technical Specifications, we are enclosing the t v t
R~t for the period January 1,
1989 through June 30, 1989.
Included in this report is (a) a summary of liquid, gaseous and solid effluents released from the station during the reporting period (Tables 1-3),
(b) an amendment to the July-December 1988 report for solid effluents (Table 4A), (c) a reference to the Offsite Dose Calculation Manual and Process Control Program (Table 5
and 6),
(d) an explanation of effluent instrument inoperability conditions experienced during the reporting period (Table 7),
and (e) a description of the current operability status of the NMP-1 High Range Stack Monitoring System (Attachment 1).
The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1.
Dose assessments were made in accordance with the NMP-1 Off-Site Dose Calculation Manual.
Distribution is in accordance with Regulatory Guide 10.1, 10CFR50.4(b)(1) and the Technical Specifications.
If you have any questions concerning the attached
- report, please contact John J.
- Blasiak, Chemistry Unit Supervisor, at Nine Mile Point Unit 1
(315) 349-2566.
Very truly yours, J. L. Willis General Superintendent Nuclear Generation JLW/JJB/mad (2291X) xc: Director, Office of Nuclear Reactor Regulation (1)
Director, Office of Inspection and Enforcement (1)
Mr. William T. Russell, Regional Administrator, United States Nuclear Regulatory Commission, Region I, Allendale Rd., King of Prussia, Pennsylvania 19406 (1)
NRC Resident Inspector, Nine Mile Point Nuclear Station Unit 81 (1)
a
NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1989 DOCKET NO.:
LICENSE NO.:
50-220 DPR-63 NIAGARA MOHAWK POWER CORPORATION
0
)
NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT'RELEASE REPORT JANUARY JUNE 1989 SUPPLEMENTAL INFORMATION Facility:
Nine Mile Point Unit 81 Licensee:
Niagara Mohawk Power Corporation 1.
Technical Specification Limits:
A)
Fission and activation gases:
1.
The dose rate limit of noble gases from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrems/year to the total body and less than or equal to 3000 mrems/year to the skin.
2.
The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrads for beta radiation
- and, during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.
BEC) Tritium, Iodines and Particulates, half lives > 8 days:
1.
The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight
- days, released to the environs as part of the gaseous wastes from the
- site, shall be less than or equal to 1500 mrems/year to any organ.
2.
The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half lives greater than 8 days as part of gaseous effluents released from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrems to any organ
- and, during any calendar year to less than or equal to 15 mrems to any organ.
I D)
Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B,
Table II, Column 2 for radionuclides other than dissolved, or entrained noble gases.
For dissolved or entrained noble
- gas, the concentration shall be limited to 2E-04 microcuries/ml total activity.
AD.
Liquid Effluents (Cont'd) 2.
The dose or dose commitment to a
member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5
mrems to any organ, and during any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
2.
Maximum Permissible Concentrations A)
Fission and activation gases:
None specified BEC) Iodines and particulates, half lives > 8 days:
None specified D)
Liquid Effluents:
10CFR 20, Appendix B, Table II, Column 2.
Avg MPC ( January March )
=
no discharges Avg MPC ( April June
)
=
no discharges 3.
Average Energy (Fission and Activation gases Mev)
<<January March:
E> = 0.008 Mev; Eg = 0.235 Mev April June:
No discharges 4.
Measurements and Approximations of Total Radioactivity Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
Fission and Activation Gases:
Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (Intrinsic germanium crystal) or gross activity monitoring (detectors calibrated using NBS traceable Noble Gas sources) and/or grab sampling and isotopic analysis of an isokinetic stack sample stream.
B)
Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges manually or automatically sampled from an isokinetic stack sample stream.
>> Due to source gases used during annual calibration of Noble gas monitors that were released out the stack.
)
4.
I (Cont'd)
C)
Particulates:
Gamma activity released from main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters manually or automatically sampled from an isokinetic sample stream.
Gross alpha activity is found by analysis of particulate filters on a
Zinc Sulfide or gas proportional counter after radon/thorium decay, corrected for self absorption.
For emergency condenser vent batch
- releases, effluent curie quantities are estimated by subtracting activity remaining in the shell side of the emergency condenser after batch release from activity delivered to the shell from Make-Up sources.
Actual isotopic concentrations are found via gamma spectroscopy.
Batch release activities of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to activity concentrations of gamma emitters.
The activity of tritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.
D)
Tritium effluent activity is estimated by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.
E), Liquid Effluents:
Isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
F)
Solid Effluents:
Isotopic contents of waste shipments are determined by gamma spectroscopy, gross alpha and water content analyses of a
representative sample of each batch.
Scaling factors established from primary composite sample analyses conducted off-site are
- applied, where appropriate, to find estimated concentration of non-gamma emitters.
'For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
5.
Batch Releases The following information relates to batch releases of radioactive materials in liquid and gaseous effluents.
A)
Liquid 1.
Number of batch releases:
0 2.
Total time period for batch releases:
3.
Maximum time period for a batch release.'verage time period for a batch release:
5.
Minimum time period for a batch release.'.
Average stream flow during period of release of effluent into a flowing stream:
7.
Total volume of water used to dilute the liquid effluent during release periods 8.
Total volume of water available to dilute the liquid effluent during reporting period 0
0 0
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0
hours 0
hours 0
hours 0
Not Applicable No Discharges 4.54E+01 GL min.
min ~
min.
min.
5'.
(Cont. ),
B)
Gaseous (Emergency Condenser Vents) 1.
Number of batch releases:
0 2.
Total time period for batch releases:
0 3.
Maximum time period for a batch release:
4.
Average time period for a batch release:
5.
Minimum time period for a batch release:
hours 0 min.
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
6.
Abnormal Releases A.
Liquids none B.
Gaseous none
TABLE 1A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION &1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1989 1st QLlhRXJR 2nd EST.TOTAL QiKQER SUER ~
A. l.
2 ~
3.
t' Total release Average release rate for period Percent of Technical Specification Limit Ci i'<i'< 1.52E-04 O.OOE+00 2.5E+01 pCi/sec
>'<>'< 1.95E-05 O.OOE+00 C.
LaU,um 1.
Total iodine-131 2.
Average release rate for period 3.
Percent of Technical Specification Limit Ci pCi/sec Prolonged Unit Outage pCi/sec 1.
Particulates with half-lives >8 days Ci 2.
Average release rate for period 3.
Percent of Technical Specification Limit 4.
Gross alpha radio-activity Ci 7.52E-04 9.67E-05 2.47E-05 k
8.71E-04 3.0E+01 1.12E-04 3.87E-05 2.5E+01 D.
1.
Total release 2.
Average release rate for period 3.
Percent of Technical Specification Limit Ci pCi/sec 2.10E-01 2.10E-01 1.63E+00 1.65E+00 2.5E+01
>'<>'< Due to source gases used during annual calibration that were released out the stack after calibration was completed.
TABLE 1A (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT. NUCLEAR STATION 81 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1989 E ~ v'c t'
t 1st Q1KEKE 2nd QEQKKR v t
)C)C t'v t' 2 ~
3 ~
4.
5.
6.
2.
3.
Percent of Quarterly Gamma Air Dose Limit Percent of Quarterly Beta Air Dose Limit Percent of Annual Gamma Air Dose Limit to Date Percent of Annual Beta Air Dose. Limit to Date Percent of Whole Body Dose Rate Limit Percent of Skin Dose Rate Limit Percent of Quarterly Dose Limit Percent of Annual Dose Limit to Date Percent of Organ Dose Rate Limit t
w't 1.48E-08 O.OOE+00 2.11E-07 7.39E-09 1.05E-07 5.91E-10 2.91E-09 v
O.OOE+00 7.39E-09 1.05E-07 O.OOE+00 O.OOE+00 t
t 2.43E-01 1.23E-01 2.60E-01 2.53E-01 4.95E-03 5.20E-03
>'<>'< Due to source gases used during annual calibration the stack after calibration was completed.
that were released out
I
~
TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl GASEOUS EFFLUENTS-ELEVATED RELEASE Nuclides Released JANUARX JUNE 1989 NCONTINUOUS MODE
~
~
Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci l'c1.31E-04 lClC l'Cl'C l'c2, 1 1 E 05 lClC ltlC ltlC lClt l'ClC ltlC lClC 2 ~
Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci ltl'C l'Cl't ltl'C t'
4.
Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum
~tag Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 5.37E-06 1.34E-06 1.63E-04 5.25E-04 lCl'C lC l'C lClC l'Cl't l'C l'C l'Cl't l'CA l'CA 5.68E-05 ltlt 1.63E+00 5.66E-06 1.62E-06 ltlC 2. 55E-04 5. 23E-04 l'C l'C 7.92E-06 lClC l'Cl'C lClC l'C l'C l'Cl't 7.76E-05 l'Cl'C 1.65E+00 lt 8
l'Cl'C Due to source gases used during annual calibration that were released out the stack after calibration was completed.
No Batch Mode releases occurred during the reporting period.
Less than sensitivity of 1.00E-04 for Noble
- Gases, 1.00E-11 for particulates, 1.00E-12 for Iodines, and 1.00E-06 for tritium as applicable by Technical Specifications.
1
TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl GASEOUS EFFLUENTS-GROUND LEVEL (EMERGENCY CONDENSER VENT) RELEASES JANUARY JUNE 1989 Nuclides Released CONTINUOUS MODE BATCH MODE Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci No discharges No discharges 2.
Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci No discharges No discharges 3.
t' 4.
Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci No discharges No discharges No discharges No discharges
I 4
TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION N1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARX JUNE 1989 ggj t 1st 2nd Qu~~
Qumlax.
Est. Total Exxon~
A.
t.
3.
Total release (not including tritium,
- gases, alpha)
Average diluted con-centration during reporting period Percent of applicable limit Ci pCi/ml None None B. gati m
l.
2.
3.
Total release Average diluted con-centration during reporting period Percent of applicable limit Ci pCi/ml None None C. D'v 1.
2.
3.
Total release Average diluted con-centration during reporting period Percent of applicable limit Ci pCi/ml None None D.
Gr h
t'v't 1.
Total release Ci None None E.
1.
2.
3.
Prior to dilution Volume of dilution water used during release period Volume of dilution water used during reporting period liters None None liters liters 7.62E+09 3.78E+10 2.0E+01
TABLE 2A (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION 81 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1989 ggj t 1st Qum~IW 2nd QQkrr~X F. fc
'm't 2.
3 0 4,
5.
6.
Percent of Quarterly whole Body Dose Limit fo Percent of Quarterly Organ Dose Limit Io Percent of Annual Whole Body Dose Limit to Date Percent of Annual Organ Dose Limit to Date Percent of 10CFR20 Concentration Limit
'lo Percent of Dissolved or Entrained Noble Gas Limit 10
>'< There were no liquid discharges from NMP-1 through the period January June 1989.
10
l
TABLE 2B RADIOACTIVE EFFLUENT RELEASE SEMI-ANNUAL REPORT (1989)
NINE MILE POINT NUCLEAR STATION 81 LIQUID EFFLUENTS RELEASED JANUARY JUNE 1989 BATCH MODE Nuclides Released Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci'i Ci Ci Ci Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-niobium-95 Molybdenum-99 Technetium-99m Barium-lanthanum-140 Cerium-141 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci No Discharges No Discharges Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci E Dissolved or Entrained Gases Ci
l
TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION N1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS rB'Nt Spent Resins m
Curies Solidification Agent Processing Method Container Package Principle Isotopes Non-compressible Dry Activated m
Curies Solidification Agent Processing Method Container Package Principle Isotopes 2.33E+Ol 2.62E+01 None Dewatered HIC Type A Co60, Csl37,
- Csl37, Co60, H3, Mn54, Cs134 Compressible Dry Activated Waste ms Curies Solidification Agent Processing Method Container Package Principle Isotopes Oil ms Curies Solidification Agent Processing Method Container Package Principle Isotopes 8.73E+01 1.02E+00 None Compacted Steel Drums Strong Tight Package
- Co60, Cs137, Ni63 AgllOm, Mn54, 5.10E+00 1.25E-03 Cement Cement Solidification Steel Liner Type A H3, Cs137, Co60
- Fe55, Pu241 12
TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl SOLID MASTE AND IRRADIATED FUEL SHIPMENTS (Continued) t '
i t Est.Total
~l b.
~~B Spent Resins m
Curies Solidification Agent Processing Method Container Package Principle Isotopes 5.83E+00 1.05E+01 None Dewatered HIC Type A
- Co60, C14, Mn54,
- Cs137, Sr90
- 2. 5E+01 Filter Sludge m
Curies Solidification Agent Processing Method Container Package Principle Isotopes c.
gLa~
None 5.10E+00 2.83E+Ol Cement Cement Solidification Steel liner Type A Co60, Csl37,
- Fe55, Mn54, Ni63 2.5K+01 t'
a ~
Spent Resins Filter Sludges Cobalt-60 Cesium-137 Iron-55 Manganese-54 Carbon-14 Nickel-63 Other 10 10 10 10 10 10 10 6.92K+01 1.91E+Ol 3.84E+00 2.60E+00 2.45E+00 1.78E+00 1.03E+00 b.
Non-compressible Dry Activated Waste Cesium-137 Cobalt-60 Tritium Manganese-54 Cesium-134 Other 13 5.94E+01 3.32E+01 5.33E+00 1.07E+00 8.30E-01 1.70E-Ol
TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) 2.
t t
c.
Compressible Dry Activated Waste (Cont'd)
Cobalt-60 Cesium-137 Nickel-63 Silver-110m Manganese-54 Other 70 5.19E+01 3.10E+01 8.33E+00 2.92E+00 2.70E+00 3.15E+00 d.
Oil Tritium Cesium-137 Cobalt-60 Iron-55 Plutonium-241 Other 70 70 10 7.32E+01 1.22E+Ol 5.97E+00 4.70E+00 2.73E+00 1.20E+00 t
't'ruck Truck (Disposition) them-Nuclear Systems Barnwell, South Carolina
- Hanford, WA NONE Below is a
preliminary summary of Solid Waste that was buried by vendor facilities (i.e.,
- ALARON, QUADREZ and SCIENTIFIC ECOLOGY GROUP) during January June 1989.
This waste represents the resultant product of the processing (by the vendor) of NMP-1 radioactive material (eg.
plant trash, equipment, etc.)
shipped to the vendor.
This information will be revised in the July December 1989 Semi-Annual Report.
These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" (i.e.,
Section A of Table 3A) since (a) waste classification and burial was performed by the vendors and (b) NMP-1 Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped offsite during the reporting period."
The radioactive material shipped to processing facilities is not considered
- waste, therefore, the information provided in this section is in addition to that required by the NMP-1 Technical Specifications.
14
TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
(Cont'd) t'v't 2.
t' m~
Ci Principle Isotopes 1.18E+02 2.10E+00
- Co60, Fe55, Mn54, Csl34, Co58 Cobalt-60 Iron-55 Cesium-134 Manganese-54 Cobalt-58 Other 10 lo 10 70 Fo 70 6.49E+01 2.41E+01 5.20E+00 3.40E+00 2.30E+00 1.00E-01 3 ~
t Di iti h'
nt t4 Barnwell, South Carolina 15
TABLE 4A AMENDMENT TO JULY DECEMBER SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)
NINE MILE POINT NUCLEAR STATION 8'1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Table 3A from the July December 1988 Semi-Annual Effluent Release Report is herein amended to include one additional Class B Spent Resin shipment which was inadvertently omitted from the report.
A.
1 t
t f
f t
Est.Total Ex'~~
a.
Spent Resins m~
Curies Solidification Agent Container Package Principle Isotopes 2.82E+Ol 5.56E+01 None HIC Type A
- Co60, Cs137,
- Mn54, Co58
- Fe55, Zn65
- 2. 5E+01 Dry Activated Waste m~
Curies Solidification Agent Containers Package Principle Isotopes 4.0E+Ol 4.26E+01 1.47E-01 None Steel LSA Box and Steel Drums Strong Tight Package Co60, Ni63, AgllOm, Csl37, Mn54, Sbl25 Concentrated Waste m~
Curies Solidification Agent Container Package Principle Isotopes 2.97E+00 2.00E+00 Dow Media Steel Drums Type A
- Csl37, Co60, Fe55 Csl34 3.0E+01 b.
Qla,~>
Spent Resins m
Curies Solidification Agent Container Package Principle Isotopes 1.43E+01 2.38E+02 None HIC Type A Co60, Csl37, Mn54, Co58,
- Fe55, Zn65 2.5E+Ol 16
I
0 TABLE 4A AMENDMENT TO JULY DECEMBER SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1988)
NINE MILE POINT NUCLEAR STATION 81 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) t h'
D
- b. ~<~
(Cont')
Est.Total R~~~
Filter Sludge m~
Curies Solidification Agent Container Package Principle Isotopes c.
Q3~~
5.03E+00 5.00E+01 Cement Steel liner Type A
- Co60, Cs137 Mn54, Ni63 2.5E+01 None t'
a.
Concentrated Wastes Resins Filter Sludges Cobalt-60 Cesium-137 Manganese-54 Cobalt-58 Iron-55 Zinc-65 Nickel-63 Other 7.92E+01 6.55E+00 5.50E+00 2.34E+00 1.80E+00 1.33E+00 1.24E+00 2.04E+00 b.
Dry Activated Waste Cobalt-60 Nickel-63 Silver-110m Cesium-137 Manganese-54 Antimony-125 Cobalt-58 Chromium-51 Zinc-65 Other lo 10 70 10 10 10 lo lo 6.39E+01 1.48E+Ol 6.17E+00 4.46E+00 4.43E+00 1.61E+00 1.37E+00 1.16E+00 1.11E+00 9.90E-01 t
~
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t4 Truck 17 Chem-Nuclear Systems Barnwell, South Carolina
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TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL JANUARY JUNE 1989 The Nine Mile Point N1 Off-Site Dose Calculation Manual (ODCM),
as described in ODOM, Rev.
6, was not revised during the January June reporting period.
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TABLE 6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION 81
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM JANUARY JUNE 1989 The Nine Mile Point Nl Process Control Program (PCP) for waste solidification, as described in Administrative Procedure 3.7, Revision 2,
was not revised during the January-June reporting period.
- However, a periodic review of the procedure was performed during the reporting
- period, but no changes were made.
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TABLE 7 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
NINE MILE POINT NUCLEAR STATION Nl EXPLANATION OF INSTRUMENTATION INOPERABILITY JANUARY JUNE 1989 In accordance with NMP-1 Technical Specifications 3.6.14a and 3.6.14b, Radioactive Effluent Instrumentation which is inoperable for 30 consecutive days within the reporting period must be reported in the Semi-Annual Radioactive Effluent Release Report.
Below is a listing of monitors which technically fall into this category during the January June 1989 reporting period along with a
description of causes for the inoperability
- and, as appropriate, corrective actions taken to resolve the problems.
gag t~i~t r t'v t'igh Range Stack Monitor (RAGEMS)
Modification being performed to upgrade system to be more reliable (See Attachment 1)
Liquid Radwaste Effluent Monitor This monitor was not required to be in service per Technical Specification Table 4.6.14-1 since the discharge line was isolated during the entire reporting period.
Operability should be restored prior to the next liquid discharge.
Liquid Radwaste Flow Device The measuring device is obsolete and needs to be replaced.
A modification request has been submitted to have the device replaced.
If the device is required before the modification is
- complete, Technical Specifications will be met by estimating flow every four hours as specified in Section 3.6.14a of Unit 81 Technical Specifications.
Offgas Radiation Monitor and Emergency Condenser Radiation Monitor Instrumentation These monitors are not required to be operable during outage periods as specified by Unit Nl Technical Specifications Operability will be re-established during unit restart.
Stack Flow Measuring Device In conjunction with modifications to the Radioactive Gaseous Effluent Monitoring Sys-tem (RAGEMS), the stack flow device was inoperable during the entire reporting period.
Total stack flow value was estimated by fan configuration in accordance with Technical Specification Table 3.6.14-2, footnote (d).
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ATTACHMENT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
PROBLEMS WITH THE NMPl STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1989 The previous Semi-Annual Effluent Release Reports provided a status update for each of the specific modifications and changes associated with NMP-1's high range Radioactive Gaseous Effluent Monitoring System (RAGEMS) and normal operation (lower range)
Old GE Stack System (OGESMS).
Progress continues to be made toward the resolution of the system's design deficiencies so that a
more reliable stack monitor'ing system can be obtained.
During the period of RAGEMS inoperability, all stack radiological monitoring requirements, as defined in section 3.6.14b of the Radioactive Effluent Technical Specifications (RETS),
were met using the Old General Electric Stack Monitoring System (OGESMS) and associated grab sampling methods.
- However, in order to complete modification on both the RAGEMS and OGESMS simultaneously, an auxiliary sampling system will be used to meet effluent monitoring requirements under the Limiting Condition of Operation as allowed by Technical Specifications.
Current plans are to continue with stack monitoring system modifications through 1989 and possibly into 1990.
As stated previously, it is still the intent to maintain RAGEMS available during most periods of commercial operation to meet NUREG 0737 monitoring requirements.
OGESMS modifications necessary for system operability will be completed prior to restart; t
t The following is an update of recent modifications and design changes made to date on RAGEMS and
- OGESMS, and a
summary of modifications needed to complete the entire system upgrade:
1.
Developed a
new Piping and Instrument Diagram (P&ID) to convey more detailed information on a
complex system to enhance system operation.
PAID will be updated as modifications progress.
2.
Revise the system's radiation alarming logic to include both the RAGEMS and the OGESMS to facilitate operator response.
This design package was reworked to incorporate a valve alignment switch to remotely place either unit into service.
The design is complete and partially installed.
Installation of the remaining hardware is being staged.
21
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ATTACHMENT 1 (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
PROBLEMS WITH THE NMPl STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1989 3.
Design and install flow alarming capabilities from the RAGEMS unit to the plant's main Control Room.
This design was reworked to incorporate the valve alignment switch identified earlier.
Design is complete and awaiting installation.
Completion is expected prior to plant restart.
4.
Replace RAGEMS'ennelec Count Rate Meter to eliminate the periodic spiking signals.
The new count rate meter was returned to the manufacturer to resolve signal interface concerns with the unit's programmable controller.
The spiking problem has been further addressed by evaluating and redesigning the power supplies to RAGEMS.
Spiking problem should be resolved prior to restart.
5.
Improve operator interface with the system's parameters by increasing the ability to chart/record the system's operation.
The design package is
'complete and awaiting installation.
Installation is expected prior to restart.
A.
Placing the existing OGESMS radiation signals (counts per second) on new recorders.
B.
Addition of new parameters to be recorded (e.g.,
the RAGEMS radiation release
- rate, OGESMS system flow, RAGEMS system flow and total stack flow).
Currently, total stack flow value is estimated by fan configuration in accordance with Technical Specification Table 3.6.14-2, footnote (d).
6.
Install a permanent power supply for the air conditioner in cabinet 84 of RAGEMS.
Installation is complete.
7.
Install cables for future expansion of the system.
Installation is complete.
Design packages which use these cables have been completed and issued.
Termination work is expected to be completed prior to plant restart.
8.
Install remote manual switches override the RAGEMS process complete.
The design package 1989.
Installation is expected to the RAGEMS dilution system to manually computer.
The design of this work is will be issued by the end of September in 1989.
9.
Provide RAGEMS with the capability to isolate the plant's containment vent and purge valves.
OGESMS currently has this isolation capability.
The design of this modification is complete.
Installation is expected prior to restart.
- 10. Replace the flow control loop in RAGEMS.
The design of this work is complete.
Installation is expected prior to restart.
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ATTACHMENT 1 (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)
PROBLEMS WITH THE NMPl STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1989
- 11. Replace the flow control valve and associated controller on OGESMS.
The design is complete with installation expected to be completed prior to restart.
- 12. Install calibration valves, leak test valves and gauges on both RAGEMS and OGESMS.
RAGEMS valves have been installed.
Installation of hardware for OGESMS is being staged.
Additional valves will be installed to facilitate remotely aligning each unit (RAGEMS/OGESMS) from the control room.
Completion is expected prior to restart.
- 13. Redesign particulate and iodine filtration portion of OGESMS to provide filtration redundancy.
Installation is being staged and is expected to be completed prior to restart.
- 14. 'install additional shielding designed to eliminate periodic spikes in the background radiation levels on the OGESMS monitors.
This design is complete.
The design package is expected to be issued in the near future, and installation is expected by the end of 1989.
- 15. Resolve computer software and hardware problems.
This work includes the upgrade of the computer's modem capability.
Presently, this work is in progress and anticipated to be completed in 1989.
- 16. Modify RAGEMS/OGESMS computer input and output signals to provide additional essential input to the Safety Parameter Display System (SPDS).
This work should be completed in 1989.
- 17. Revise the plant's process computer's descriptions and setpoints as they apply to the Stack Gas Monitoring System (OGESMS and RAGEMS).
Completion's expected in 1989.
- 18. Correct leakage problems with RAGEMS 3-way solenoid valves.
The design of this work is complete.
Installation is expected prior to restart.
23
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