ML17056A963
| ML17056A963 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1990 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17056A964 | List: |
| References | |
| NUDOCS 9009110041 | |
| Download: ML17056A963 (68) | |
Text
NINE MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990 DOCKET NO.:
LICENSE NO.:
50-220 DPR-63 NIAGARA MOHAWK POWER CORPORATION 9009ii004i 900830 PDR ADQCK 05000220 R
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N MILE POINT NUCLEAR STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1990
" 'SUPPLEMENTAL"INFORMATION Faci 1 i ty:
Nine Mi 1 e Point Unit ¹1 Licensee:
Niagara Mohawk Power Corporation 1.
Technical Specification Limits:
A)
Fission and activation gases:
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
" '*=ite"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 milli roentgen for gamma radiation and less than or equal to 20 mrads for beta radiation.
BEC) Tritium, Iodines and Particulates, half lives 8 days:
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 wi th 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'5 mrems to any'rgan.
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.
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Liquid Effluents (Con"
)
2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine
'ile 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 BKC) Iodines and particulates, half lives
> 8 days:
None specified D)
Liquid Effluents:
10CFR 20,, Appendix B, Table II, Column 2.
""Avg'MPC'( Jan. - 'March
)
=
no discharges Avg MPC
( April June
)
=
2.99E-3 uCi/ml 3.
Average Energy (Fission and Activation gases - Mev)
Jan.
Mar.
No discharges Apr.
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 byon-line gamma spectroscopic monitoring (intrinsic
'ermanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample), of an isokinetic stack sample stream.
B)
Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled "from an isokinetic stack sample stream.
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(Cont'd) t C)
Pa rticulates:
Activity released from main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream.
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.
0)
Tritium:
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 appli'cation 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:
3 2.
Total time period for batch releases:
14 3.
Maximum time period for a batch release:
4 4.
Average time period for a batch release:
4 5.
Minimum time period for a batch release:
4 6.
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 hours 41 min.
hours 56 min.
hours 53 min.
hours 49 min.
Not Applicable 8.81E+8 Liters 1.81E+ll Liters
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- 5. (Cont.)
8) 6.
Abnormal Releases A.
Liquids none B.
Gaseous none Gaseous (Emergency Condenser Vent) l.
Number of batch releases:
0
'2.'otal time period for batch releases:
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
3.
Maximum time period for a batch release:
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
4.
Average time period for a batch release:
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min.
5.
'inimum time period for a batch release:
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 0 min ~
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TABLE lA SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE'POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1990 A.
Fis'sion 5 Activation ases 1.
Total release 2.
Average release rate for period 3.
Percent of Technical Specification Limit B.
Iodines 1.
Total iodine-131 2.
Average release rate for period 3.
Percent of Technical Specification Limit UNIT Ci uCi/sec Ci uCi/sec 1st 2nd EST.TOTAL QUARTER QUARTER ERROR
'/
Prolonged Unit Outage Particulates'*
1.
Particulates with half-lives
>8 days 2.
Average release rate for period 3.
Percent of Technical Specification Limit 4.
Gross alpha radio-activityy Ci 3.57E-05 4.16E-05 2.5E+01 Ci 6.92E-04 3.85E-04 2.5E+01 uCi/sec 8.90E-OS 4.80E-05 D. Tritium 1.
Total release 2.
Average. release rate for period 3.
Percent of Technical Specification Limit Ci 9.35E-01 1.40E+00 2.0E+01
'Ci/sec, 1.20E-01
. 1.75E-01
'efer to E on next page.
- Results were not received from the offsite vendor as of August 30, 1990.
These numbers include estimates for June 1990.
Actual numbers will be provided in the next semi-annual report.
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TABLE lA (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1
'ASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL
'ANUARY - JUNE 1990 UNIT 1st gUARTER 2nd QUARTER E.
Percent of Technical S ecification Limits (NMP-1 Elevated Release)
Fission and Activation Gases:
2.
3.
'" 4.
Percent of Quarterly Gamma Air Dose Limit Percent of Quarterly Beta Air Dose Limit Percent of Annual Gamma Air Dose Limit to Date
""'Perce'nt<'of '>Annual 'Beta Air Dose Limit to Date Percent of Nhole Body Dose Rate Limit Percent of Skin Dose Rate Limit O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
, Tritium 'odines and Particulates (with half-lives reater than 8 da s):
2 ~
3.
Percent of Quarterly Dose Limit Percent of Annual Dose Limit to Date Percent of Organ Dose Rate Limit 2.26E-01 1.03E-01 1.14E-01 1.77E-01 4.60E-03 2.03E-03
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t TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-ELEVATED RELEASE JANUARY JUNE 1990 Nuclides Released Fission Gases Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-135 Xenon-135m Xenon-137 Xenon-138 "2. 'I'odines Iodine-131 Iodine-133 Iodine-135 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CONTINUOUS MODE¹
'l'""
3.
4.
Parti cul ates 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 linc-65 Iron-55*
Molybdenum Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8.46E-06 1.93E-06 7.60E-05 5.29E-04 7.70E-05 9.35E-01 7.12E-05 9.64E-06 7.92E-05 1.47E-04 7.78E-05 1.40E+00 No batch mode release occurred during the reporting period.
Concentrations are less than lower limits of detection required by Technical Specification i.e.,
1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates and 1.00E-12 uCi/ml for Iodines, respectively).
Results were not received from offsite vendor as of August 30, 1990.
These'numbers included estimates for June 1990.
Actual numbers will be included in the next semi-annual report.
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t TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-GROUND LEVEL (EMERGENCY CONDENSER VENT) RELEASES JANUARY JUNE 1990 Nuc 1 i des Released Fission Gases Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-137 "Xenon'-138 CONTINUOUS MODE d
t ~~dt Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci BATCH MODE tll t ~dt No Releases 2.
3.
4.
Iodines Iodine-131 Iodine-133 Iodine-135 Particulates 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 Chromiu'm-51 Zinc-65 Iron-55 Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
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TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1990 Unit A.
Fission and activation roducts 1st 2nd guarter guarter Est. Total Error Total release (not including tritium,
- gases, alpha)
Average diluted con-centration during reporting period Percent of applicable 1 imit B.
'1. '".'"Tota'1"-re'lease 2.
Average diluted con-centration during reporting period 3.
Percent of applicable 1 imit Ci uCi/ml Ci uCi/ml None None 6.78E-04 2.5E+01 8.13E-12 5.07E-01 2.0E+Ol 6.08E-09 C.
Dissol.ved and entrained ases 1.
2.
3.
Total release Average diluted con-centration during reporting period Percent of applicable limit uCi/ml None None 3.0E+01 D.
Gross al ha radioactivit Total release E.
Volumes None 1.04E-09 3.0E+01 l.
,2.
3.
Prior,to dilution
. Volume of dilution water used during release period Volume of dilution water available during reporting period
.l,i ters None 2.82E+05 1.0E+Ol 1 i ters
- 9. 74E+10
- 8. 34E+10
- 2. OE+Ol 1 i ters
- 8. 81E+08 2.0E+01
- Refer to F on next page.
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TABLE 2A (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REP RT NINE MILE POINT NUCLEAR STATION ¹1
" 'IQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1990 Unit F.
Percent of Technical' ecification Limits 1.
Percent of Quarterly Whole Body Dose Limit 2.
Percent of Quarterly Organ Dose Limit 3.
Percent of Annual Whole Body Dose Limit to Date 4.
Percent of Annual Organ Dose Limit to Date 5.
Percent of 10CFR20 Concentration Limit 6.
Percent of Dissolved or
'" '"Entrain'ed'-tNoble~Gas Limit 1st quarter No Discharges 2nd guarter 8.62E-04 4.91E-04 4.30E-04 2.46E-04 2.03E-04 None 10
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TABLE 28 RADIOACTIV EFFLUENT RELEASE SEMI-ANNUAL RE RT NINE MILE POINT NUCLEAR STATION ¹1 LIQUID EFFLUENTS RELEASED JANUARY JUNE 1990 Nuc1 i des Re 1 eased Strontium-89 Strontium-90 Cesium-134
.Cesium-137 Iodine-131 Cobalt-58 Cobalt-60 Iron-59 Zinc-65
".""Mang'anese-"54 Chromium-51 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci
>> Ci Ci BATCH MODE
~~tt
~d Zirconium-niobium-95 Molybdenum-99 Technetium-99m
~ Barium-lanthanum-140 Cerium-141 Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239
'"Pras'e'odymium-"144 Iodine-135 Dissolved or Entrained Gases
" Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci No Discharges 6.78E-04 5:07E-01
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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1990 A.
10CFR61 Solid Haste Shi ed for Burial (Not irradiated fuel) 1.
Class of Haste a.
Class A
I Spent Resins m3 Curies Solidification Agent Container Package Principle Isotopes
"~Dry"A'ct 1 ve ~Has te m3 Curies Solidification Agent Containers Package Principle Isotopes b.
Class B
Filter Sludge m~
Curies Solidification Agent
'ontainer Package Principle Isotopes c.
Class C
None Januar June
- 1. 51E+01 1.44E+01 None HIC Type A
- Co60, Cs137 Fe55 5.38E+00 1.41E+00 None Steel LSA Box Strong Tight Package Co60, Csl37,
- Mn54, H3 1.36E+01 1.76E+02 Cement Steel liner Type A
Co60, Csl37, H3 Mn54, Ni63, Fe55 Est.Total Error 2.5E+01 4.0E+01 2.5E+01 12
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TABLE 3A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
JANUARY JUNE 1990 2.
Estimate of Ma or Nuclide Com osition (b T
e of Haste) a.
Resins Filter.Sjudges Cobalt-60 Cesium-137 Iron-55 Nickel-63 Manganese-54 Other b.
Dry Active Haste Cesium-137 Cobalt-60
.~ "-'Hydrogen-3
'anganese-54 Cesium-134 Other 3.
Solid Haste Dis osition Number of Shi ments Percent 6.76E+01 1.86E+01 9.40E+00 2.09E+00 1.69E+00 6.20E-01 Percent 5.94E+01 3.32E+01 5.33E+00 1.07E+00 8.29E-01 1.71E-01 Mode Truck Destination Chem-Nuclear Systems Barnwell, South Carolina 13
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TABLE 3A SEMI-AN AL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
JANUARY - JUNE 1990 B.
Irradiated Fuel Shi ments (Disposition)
Number'of Shi ments None Mode Destination C.
,Sol.,id Haste Shi ed to Vendors for Processin and Burial Below is a
summary of Dry Active Haste that was shipped offsite for processing and burial by vendor facilities (i.e.,
ALARON, QUADREX and SCIENTIFIC ECOLOGY GROUP) during January June 1990.
These totals were reported separately from "10CFR61 Solid Haste 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"sol'id waste'(as':defined by 10CFR61) shipped offsite during the reporting period."
The information provided in this section, therefore, is in addition to "that required by the NMP-1 Technical Specifications.
1.
Volume/Activit Summar m3 Curies Principle Isotopes 1.17E+02 3.03E+00
- Co60, Cs137,
- Fe55, Cs134,
- Mn54, H3, C14 2.
Estimate of Ma or Nuclide Com osition*
'"Iron-55 Nickel-63 Hydrogen-3 Manganese-54 Carbon-14 Cesium-134 Other 3.
Solid Haste Dis osition Number of Shi ments 27 4.82E+01 3.86E+01 7.61E+00 1.85E+00 1.03E+00 1.05E+00 9.87E-01 1.65E-01 5.08E-01 Destination Barnwell, South Carolina Hanford, Hashington
.::-*. The Alaron.activity data is being re-evaluated and may/may not need updated in the next semi-annual report.
He conservatively assumed that all the activity sent to Alaron was buried.
This may/may not be the case.
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TABLE 3A SEMI-AN AL RADIOACTIVE EFFLUENT RELEASE PORT NINE MILE POINT NUCLEAR STATION ¹1
"<< =SOLID WASTE AND IRRADIATED.FUEL SHIPMENTS (Continued)
JANUARY JUNE 1990 D.
Sewa e Slud e Shi ed to a Treatment Facilit Center for Processin and Burial Below is a
summary of the sewage sludge which was removed from the site sanitary treatment facility and transferred to a municipal sewage treatment facility, for subsequent drying and disposal by landfill.
This is a site release
- and, therefore, includes the results from Unit 2 activities also.
1.
Volume/Activit Summar Est. Total Error 9.08E+00 5.00E+Ol Curies 9.02E-06 5.00E+01
'2. ""'Estimate 'of:Ma'or Nuclide Comosition Cobalt-60 3.
Solid Waste Dis osition
- Number of Shipments 1
Percent 1.00E+02 Destination Landfill 15
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
ODCM Rev.
7 Section Chan ed Table of Contents page i page 19, section 3.1.1 Description of Change (Justification)
Changed the section headings to be more consistent concerning RAGEMS and OGESMS for clarification purposes.
Added the option of using an off-gas isotopic distribution to determine monitor setpoints from continuous release points to improve conservatisms and accuracy of setpoint calculations.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations None Previous methods used grab samp~l techniques to establish monito~
K-factors.
The new method uses NBS traceable standards which is inherently more accurate and reliable.
page 19, section 3.1.1 page 21, section 3.1.2 page
- 22A, section 3.1.2 Changed the title for the Chemistry
& Radiation Protection Supervision (C8RP) to Chemistry L Radiation Management (CORM)
Added a summation sign to the monitor efficiency factor, to correct a
previous oversight.
Added a monitor efficiency equation to determine efficiencies when the stack release rates are near the lower limit of detection None
- None, since previous methods used the summation.
This change improves the accuracy and reliability of alarm setpoint determinations by using the results from a national standard as a basis for the calculation in lieu of low activity gas sample concentrations.
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TABLE 4 SERI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
ODCM Rev.
7 Section Chan ed page
- 22B, section 3.1.3 page 24, section, 3.1.5 page 26; section 3.1.5.3 page i,ii, Table of Contents Description of Change (Justification)
Added a summation sign.
Rewrote the section to more clearly define the functions of the stack monitoring systems.
This section was revised to more accurately describe the intended functions of the stack monitoring system.
The OGESMS will be used to monitor stack effluents during normal operation and the RAGEMS will be used for accident monitoring.
Deleted the reference to pro-cedures since we are rewri ting the chemistry procedures.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations
- None, since previous methods used the summation.
None This change improves the accuracy of setpoint calculations since OGESMS uses four detectors each of which alarm in the Control Room.
None 17
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 0'1 RECENT CHANGES TO-THE OFFSITE DOSE CALCULATION MANUAL Change No.
10 ODCM Rev.
8*
Section Chan ed page iii, Table of Contents JANUARY JUNE 1990 Description of Change (Justification)
A. Revised the table numbers to include additional liquid dose factors:
B. Added plume shine dose.
factor table.
C. Added immersion dose factor table.
D. Revised the appendices to include liquid dose factor derivation
& plume shine dose factor derivation.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations None pages 12-16, section 2.3.1 This change was done to be consistent with changes in liquid and gaseous dose methodology and, also, for clarification purposes.
A.
Clarified the canal discharge rate during a radwaste liquid release.
The C.
T. Main report, referenced in the
- ODCM, used a discharge rate assuming dilution from two circulating water pumps of 590ft~/sec.
Our dose calculations are based on 295ft3/sec.
which is based on dilution from one circulating water pump.
Using 295ft3/sec.
decreases canal dilution by a Factor of 2, but increases far field dilution.
The net affect on dose calculations is to increase the result.
This is a more conservative approach in case one circulating water pump is inoperable.
- Revision 8 is submitted as partial fulfillment of the audit findings concerning dose calculations from the review of Revision 2 of the Unit 1 Offsite Dose Calculation Manual.
This review was completed on August 22, 1986 by the NRC and its contractor, franklin Research Center.
18
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION Pl RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
12 ODCM Rev.
8 Section Chan ed page 18, section 3.1.2 Description of Change (Justification)
B.
Added the drinking -water and sediment pathways to liquid dose methodology in lieu of using a
conservative safety factor to account for these pathways In addition, we are now calculating doses to all organs instead of the liver and whole body, only.
- However, instead of calculating doses for all age groups, we are calculating for a maximum individual.
This maximum individual is a composite of the highest dose Factor of each age group for each organ and each nuclide.
Changed the immersion air dose factor Mi to a plume shine whole body dose factor Vi,to be consistent with NUREG-0133 methodology.
Previous methodology conservatively used immersion air factors.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations-The net effect of adding new pathways is to increase the doses.
- However, we are still in compliance with discharge limits of 10CFR20 and
By calculating to a maximum individual we are ensured that the highest dose is calculated.
This is not overly conservative since the dose factors did not vary much between the highest age groups of Adult, Teen and Child.
This change improves the accuracy of the setpoint calculations.
19
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
13 14 15 ODCM Rev.
8 Section Chan ed page 28, section 3.2 page 29, section 3.2 page 30, section 3.2 Description of Change (Justification) jp This dose Factor was changed to comply with Reg.
Guide 1.109 methodology in calculating doses from a free standing stack.
This was an NRC audit finding in 1988.
Reworded the beginning paragraph for clarification purposes.
Deleted the reference to using real time meteorological data.
This option was deleted from our environmental program due to difficulties in implementing.
Changed the methodology from calculating dose for all age groups to calculating dose for a maximum individual.
This maximum individual is a
composite of the highest dose factor of each age group for each organ and total body and each nuclide.
This change was done to decrease the number of calculations needed while still being conservative and in compliance with Technical Specification Requirements.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations None The accuracy/rel i abi 1 ity of the dose/alarm setpoint calculations is not affected by this change.
The accuracy/reliability is not affected.
The doses are conservatively higher but still within the limits of 10CFR.50 and 10CFR.20.
20
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
ODCM Rev.
8 Section Chan ed Description of Change (Justification)
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations 16 17 page 31, section 3.2 '
page 32, sectio'n 3.2.1 Reworded the text for clarification purposes and added the emergency condenser vent as a
ground level release when calculating noble gas dose rates.
Changed the noble gas dose rate equations to be consistent with NUREG-0133.
- None, emergency condenser vent releases were previously included in dose calculations, although it was not clearly stated in the ODCM.
The revised equations are more accurate.
18 19 20 21 page 33 section 3.2.1.2 page 34, section 3.2.1.2 page 35, section 3.2.2 page 36, section 3.2.2.1 Changed the tritium, iodines and particulate equations to be consistent with NUREG-0133.
Previous equations used Reg.
Guide 1.109 methodology, which was inconsistent with the Unit 2 ODCM.
In addition, the emergency condenser vent calculation was included as a
ground level release.
Recalculated ihe release rate limit to reflect the new dose factors that resulted when we changed from Regulatory Guide 1.109 to NUREG-0133 methodology.
Reworded text for clarification purposes.
Same description as change No.
16 The new equations are more conservative and are more easily, traceable to NUREG-0133 methodology.
- Again, no change to accuracy/reliability from adding a reference to the emergency condencer vent since previous calculations included the resultant dose.
None None 22 page 37, section 3.2.2.2 Same description as change No.
17 21
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TABLE 4 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
23 24 25 ODCM Rev.
8 Section Chan ed page 38, section 3.2.2.3 page 39, section 3.3 page 40, section 3.3 Description of Change (Justification)
Added the noble gas plume air dose as a contribution to the maximum individual dose=at the critical receptor to be
'onsistent with sectioris 3.2.1 and 3.2.2, satisfying requirements of NUREG-0133.
Previous calculations used immersion dose factors to be conservative.
In addition we reworded the text for clarification purposes.
Reworded the text for clarification purposes.
Reworded the text to include an explanation of a maximum individual and the corresponding critical receptors of site boundary and residence.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations The dose equations are more
- accurate, because of consistency with NUREG-0133 methodology.
None None 26 27 page 45-47, section 4.1 page 52, section 4.4 Capitalized the letter notation "U" which represents the consumption rate of fish, for clarification purposes.
Deleted the reference to the use of real time meteorology for calculating plume dispersion parameters.
This option is not available at this time.
None None Previous calculations always used five year average annual dispersion parameters.
28 page 55, section Deleted the reference to determining iodine in milk since this is not required by Tech'pecs.
22 None
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TABLE 4 SEMI-ANNUAL RADIOACTIVE.EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
29 30 ODCM Rev.
8 Section Chan ed page 59, Table l-l page 60-66, Tables 2-1 to 2-7 Description of Change (Justification)
Changed the table number to be consistent with the section it pertains to.
Added the liquid dose parameters for radwaste discharges.and liquid releases from the startup or testing of the emergency condenser vent.
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations None Improves the accuracy of the liquid dose calculations, since minor-doses due to liquid discharges from the Emergency Condenser vent are now calculated.
31 32 page 68, Table 3-1 page 69, Table 3-2 page 70, Table 3-3 Changed the location for the goat milk pathway, to be consistent with the cow milk location.
This was done to be conservative and for ease of keeping locations current.
Added the gamma air and whole body plume shine dose factors to keep consistent with sections 3.2.1 and 3.2.2.
Added the immersion dose factors for gamma whole body and beta skin dose calculations to keep consistent with sections 3.2.1 and 3.2.2.
None Improves the accuracy of the dose calculations, because they are in compliance with NUREG-0133.
Same as Change No. 32.
pages 71-89, Tables 3-4 to 3-22 Changed the dose factors to reflect changes in sections 3.2.1 and 3.2.2.
None 35 pages 92-93 Tables 5-1 Updated the sampling -locations to reflect changes in the land use census.
None
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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION,¹1 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1990 Change No.
ODCM Rev; 8
Section Chan ed Description of Change (Justi fication)
Affect on Accuracy/Reliability of Dose Calculations/Alarm Set oint Determinations 36 37 38 pages 97-99 pages 100-103 pages 104-114 Added Appendix A to describe the derivation of the equation used to calculate the liquid dose factors presented in tables 2-1 to 2-7.
Added Appendix B to describe the derivation of the plume shine dose factors presented in Table 3-2.
Changed the location for Appendix A to Appendix C and revised the text to reflect changes to the equation used to calculate the particulate, iodine and tritium dose factors presented in Tables 3-4 thru 3-22.
None None None 39 pages 115-129 Changed the location of Appendix None B to Appendix D, and revised the diagrams for the stack sample and return, RAGEMS dilution, RAGEMS Schematic, and OGESMS schematic.
These reflect changes to sections 3.1.5 in Revision 7
of the U-1 ODCM ~
24
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t TABLE 5 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 EXPLANATION OF 'INSTRUMENTATION INOPERABILITY JANUARY JUNE 1990 Instrument Offgas 'Radiation Monitor Offgas System Flow Rate Devices Sampler Flow Rate Device Service Hater System Monitor Stack Flow Rate Measuring Device Sample Flow Rate Measuring Device
'OGESMS Cause of Ino erabilit /Corrective Actions These monitors were not required to be operable during outage periods as specified by Unit 1 Technical Specifications.
New monitors were installed in the main control room during the period.
No flow for the period due to an extended outage.
A modification has been completed to provide annunciation along with a computer point to the control room when total power is lost to the service water monitor micro-computer skid.
On 4/9/90 the LCO was cleared.
In conjunction with modifications to the Radioactive Gaseous Effluent Monitoring System (RAGEMS), the stack flow device was inoperable during the entire reporting period.
Total stack flow was estimated by fan configuration in accordance with Technical Specification Table 3.6.14-2, Footnote (d).
The sample flow rate was manually set on an auxiliary skid to maintain conditions isokinetic with stack flow.
This ensures a
representative sample.
The monitors were recalibrated in June
- 1990, with operability in July 1990 after several system modifications were completed (see Attachment 1).
High Range Stack Monitor (RAGEMS)
Stack noble gas grab samples were taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to comply with Technical Specifications.
Stack flow taken 'from fan configuration.
Modification being performed to upgrade system to be more reliable (See Attachment 1) 25
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t TABLE 6 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1
SUMMARY
OF CHANGES.TO THE PROCESS CONTROL PROGRAM JANUARY JUNE 1990 The Nine Mile Point ¹1 Process Control Program (PCP) for waste solidification, as described in Administrative Procedure 3.7, Revision 3, was not revised during the January June 1990 reporting period.
26
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TABLE 7 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY -
DECEMBER 1989 A.
Fission 5 Activation ases 1.
Total release 2.
Average release rate for period
' '3."~Percent"of.Technical Specification Limit UNIT Ci uCi /sec 3rd 4th EST.TOTAL QUARTER QUARTER ERROR B.
Iodines 1.
Total iodine-131 2.
Average release rate for period 3.
Percent of'echnical Specification Limit Ci uCi/sec Prolonged Unit Outage C.
Particulates 1.
Particulates with half-lives
>8 days 2.
Average release rate
"'for"period 3.
Percent of Technical Specification Limit 4.
Gross alpha radio-activity D. Tritium 1.
Total release 2.
Average release rate for period 3.
Percent of Technical Specification Limit Ci 7.17E.05 3.68E-05 Ci 2.86E+00
,1.62E+00 2.5E+01
'uCi/sec 3.60E-01 2.03E-01 Ci 8.61E-04 5.41E-04 3.0E+01 uCi/sec 1.08E-04 6.80E-05
- Refer to E on"next page.
27
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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1
,TE GASEOUS'EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING
~
ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY DECEMBER 1989 UNIT 3rd gUARTER 4th gUARTER E.
Percent of Technical S ecification Limits (NMP-1 Elevated Release)
Fission and Activation Gases 1.
Percent of Quarterly Gamma Air Dose Limit 2.
Percent of Quarterly Beta Air Dose Limit 3.
Percent of Annual Gamma
- ,""'~Air'~Dose";Limit;to Date 4.
Percent of Annual Beta Air Dose Limit to Date 5.
Percent of Whole Body Dose Rate Limit 6.
Percent of Skin Dose Rate Limit O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.39E-09 7.39E-09 1.06E-07 1.06E-07 O.OOE+00 O.OOE+00 0:OOE+00 O.OOE+00 Tritium Iodines and Particulates (with half-lives reater than 8 da s):
1.
Percent of Quarterly Dose Limit 2.
Percent of Annual Dose Limit to Date 3.
Percent of Organ Dose Rate Limit
- 2. 47E-01
- 1. 57E-01 3.77E-01 4.56E-01 4.89E-03 1.80E-02 28
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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION ¹1 GASEOUS EFFLUENTS-ELEVATED RELEASE ELEVATED AND GROUND LEVEL UPDATE OF JULY-DECEMBER 1989 DATA USING ACTUAL RESULTS FROM THE OFFSITE VENDORS FOR STRONTIUM, TRITIUM AND IRON-55 JULY DECEMBER 1989 Nuc 1 i des Re 1 eased Fission Gases Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133
-" ""Xe'non-'.1 35 Xenon-135m Xenon-137 Xenon-138 Iodines Iodine-131 Iodine-133 Iodine-135 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CONTINUOUS MODE¹
~3dtd '
thlh t
3.
Particulates Strontium-89 Strontium-90
'e's i um-'.1 34 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 Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8.29E-06 1.80E-06 3.12E-04 4.60E-04 7.87E-05 2.86E+00 6.83E-06 2.32E-06 1.34E-04 3.24E-04 7.39E-05 1.62E+00 No batch mode release occurred during the reporting period.
concentrations are less than lower limits of detection required by Technical Specification i.e.,
1.00E-04 uCi/ml for Noble Gases, 1.00E-11 uCi/ml for particulates and 1.00E-12 uCi/ml for Iodines, respectively).
29
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ATTACHMENT 1
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
" PROBLEMS WITH THE NMP1 STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990 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 Radioactigve Gaseous Effluent Monitoring System (RAGEMS) and normal operation (lower range)
Old General Electric (GE) Stack Monitoring System (OGESMS).
Progress continues to be made toward the resolution of the system's
.design deficiencies so that a more reliable stack monitoring system can be obtained.
During the period of RAGEMS inoperability, all stack radiological monitoring requirements, as defined in section 3.6.14b of the Technical Specifications, were met using the Old General Electric Stack Monitoring System (OGESMS) or an auxiliary sampling system as allowed by Technical Specifications Limiting Conditions of Operation.
Installation of all modifications to RAGEMS and OGESMS* is complete.
Current plans are to complete functional and pre-operational testing of the
- ,.RAGEMS in 1990.
~ Additionally, it is the intent to maintain RAGEMS available
'sing 'b'acku'p "gr'ab ~sample methods du'ring most periods of commercial operation to meet NUREG 0737 monitoring requirements.
OGESMS modifications necessary
'or system-operability will be completed prior to restarts STACK MONITORING SYSTEM Modification U date 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 (PAID) to convey more detailed information on a complex system to enhance system operation.
P8 ID was updated to reflect the final modification, and issued 7/17/90 for Operations Acceptance of OGESMS per DCR's and field walkdown.
" 2.'Revise'he "'sye
.radiation alarming logic to include both the RAGEMS and the OGESMS to facilitate operator response.
This design package was reworked to incorporate a valve and logic alignment switch to remotely place either unit into service.
Installation is complete and was pre-operationally tested via Nl-POT-288 dated 6/90.
- NOTE:
Operations Acceptance of OGESMS on"'7'/13/90.
30
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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
PROBLEMS NITH THE NMPl STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990 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 logic switch identified earlier.
Installation is complete.
Functional testing was completed via Nl-ISP-112-A006.
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.
It has subsequently been reinstalled.
The spiking problem has been further addressed by evaluating and redesigning the power supplies to RAGEMS.
Installation is complete and was tested via Nl-ISP-201-A036.
.5.
Improve operator, interface with the system's parameters by increasing the abi'1'i'ty"'to'char't'/record the system's operation.
Installation is complete.
A.
Placing 'the existing"OGESMS radiation signals (counts per second or counts per minute) 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
'low).
During the reporting period, total stack flow value was 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 44 of RAGEMS.
Installation is complete.
,.7.
,Install cables for future expansion of the system.
Installation is compTete".
"Design 'packages which use these cables have been completed and issued.
Installation is complete.
8.
Install remote manual switches to the RAGEMS dilution system to manually override the RAGEMS process computer.
The design of this work is complete.
Installation of manually activated program to remotely control dilution is complete and functional testing is in progress.
9.
Provide RAGEMS with the capability 'to.isolate 'the 'plant' contai nment vent and purge valves.
OGESMS currently has this isolation capability.
The design of this modification is complete.
Installation is completed and pre-op tested in Nl-POT-288 in 6/90.
10.
Replace the flow control valves in RAGEMS.
The design of this work is complete.
Installation is complete and functional testing is in progress'1
4 W
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t ATTACHMENT 1 (Cont'd)
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PROBLEMS HITH THE NMP1 STACK EFFLUENT MONITORING SYSTEM:
CAUSES AND CORRECTIVE ACTIONS JANUARY JUNE 1990 ll. Replace the flow control valve and associated controller on OGESMS.
Installation is complete and pre-op tested via Nl-POT-288 in 6/90.
- 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 complete Additional valves are being installed to facilitate remotely aligning each unit (RAGEMS/OGESMS) from the control room.
Installation is complete and leak checked via Nl-ISP-201-R531.
13.
Redesign particulate and iodine filtration portion of OGESMS to provide filtration redundancy.
Installation is complete and pre-op tested via Nl-POT-288 in 6/90.
1,4.,Install additional shielding designed to eliminate periodic spikes in the background r'adiation levels on the OGESMS monitors.
Installation is complete.
15.
Resolve computer software and hardware problems.
This work includes the upgrade of the computer's modem capability.
Hardware installation is complete.
Software functional testing is in progress.
- 16. Modify RAGEMS/OGESMS computer input and output signals to provide additional essential input to the Safety Parameter Display System (SPDS).
Modification is complete and software tested.
17.
Revise the plant's process computer's descriptions and setpoints as they apply to the Stack Gas Monitoring System (OGESMS and RAGEMS).
Revision is complete and pre-op tested via Nl-POT-288 in 6/90.
- 18. Correct leakage pr'oblems with RAGEMS 3-way solenoid valves.
Installation is complete and leak checked via Nl-ISP-201-R531.
32
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l' TECHllICRL.REVIEV8119 CGllTROL REVIEW GHEGK LIST TO SE PREPARED BT AUTHOR CHECK LIST FOR DOCUMENT NO.............................,......
REV...................
DATE....../f........z....
JOCK Gt r 7
OILYBOXES THAThPPLY YES NA Allreferences needed to implement the procedure are clearly identified and available........... 5 0
The procedure contains adequate equipment lists, precautions and limitations,-
yrerequisites, graphs, diagrams or data sheets as required.....
~.....
Survei llaace and Maiatenance Procedure utiliscs PLANT IMPACTstatement associated with ayprovai/yermiss ion for use.....,.....
~ 00010\\ ~ 1 ~
00 ~ OHO ~ ~ 010 ~ 100 ~ 101 ~ 0 ~ OOOHOOOO ~ 1 ~ 11 ~ 00 ~
~
~
~ 0 ~ 0 As appropriate. procedure addresses use of MARK-UPs...............................,........;.................
0
-. Ifappropriate, procedure requires use of fire yrotection measures.
hfe ~ n$ nts'nose rnfec.
as ~ 00 isa hfe ~ n$ nts'nose rnfec.
as ~ 00 0
vo ~ 1 ~ 00th hto 0 1000H0 000000000000000000000000000000000tootoootoo
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~0 ~ 11010 ~\\ ~tootttH1 ~010Htttt OOHOHO ~ 0 ~ 0 1 ~ 01100 ~
0 lfleads are lifted, jumpers placed or blocks used in the procedure, the PLANT IMPACT statement ackaowledges such use........................................................,......................................
Aa appropriate. procedure notifies other affested departments such as O.C.. Operations, IAC. Maintenance, Rad Protection etc......H.
H.....H......H....H.H..H.
~
~ 00 F 0'0000 ~
~ 00
~
0 ~ 0 ~011H1 ~
ifTeohnloal Speoiffoatlon Is exceeded. approprlme sation is Identified, EY CI The yrocedure references valve numbers, motor control numbers. power supplies.
Instrumentation identification is clear and correct.....,
t Ef 0
When encountered. EQ. related equipment is identified as such...........=...................................
0 prooedurs maps aro olear and m surete.
They are not unnecessarily dlfffoultto Implement.... cl IS'he proosdm s reflects the lateit aysttoa or smapenent oonfisuratfon.-................:............. W 0 The prooedure reflasts uorh'es It is to he done st the station.............-........,,....................:.-. ~ fl Procedure removes aay jumpers or blocks aad restores lifted leads used to effect the ofkH00000000000HH\\HHHOOOHHHOHHOOOHHOOOOOHH0000000000HOOHOO 1111t010to ~OHHOttttHHOOOHtttttttttttt~ tHOOOHttttttttttttttt0 RETURN TO SERVICE uses double verification and identifies specifics being verified.......... 0 For mainteaance procedures, RETURN TO SERVICE either pciforms a POST MAINTENANCE TEST 0
0, 9
Of'efefenoeS a fequlfed teSt000ttttt000t000000000t0000t0000000000ttt000t0000t0000000tt00000ttttt0tt000000totottoootttooto MAQR'PH a~ cleared or surrendered...................................................................................
0 "ACCEPTANCE CRITERIA" Ideatifiea accomplishment of specific goals...............:....................
0 "CV FORM PREPARED BY....
... DATTr.Q2-..'g/65 FIG 2.0-2 SH 4 OF 4 AP-2.0 H32 Decefmber 1989
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