ML18038A663

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept,Jan-June 1989. W/890830 Ltr
ML18038A663
Person / Time
Site: Nine Mile Point Constellation icon.png
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)
v • d • e


Text

~~

'I PPLE D%1BUTION DEMONSTION SYFI'EM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)'CCESSION NBR:8909130020 DOC.DATE: 89/06/30 NOTARIZED: NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION WILLIS,J.L. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

"Nine Mile Point Nuclear Station Unit 1 Semiannual Radioactive Effluent Release Rept Jan-June 1989."

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2),Semiannual COPIES RECEIVED:LTR g Effluent Release Reports+

ENCL SIZE: CRQ NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME L R ENCL PD1-1 LA 3 PD1-1 PD 1 h SLOSSON,M 1 INTERNAL: ACRS 1 AEOD/DS P/TPAB 1 IRM TECH ADV 1 N RPB 10 2 NUDOCS-ABSTRACT 1 REG FI 01 1' RGN1 DRSS/RPB 2 RGN1 FILE 02 EXTERNAL BNL TICHLER I J0 3 1. EGGG,SIMPSON,F 2 LPDR 1' NRC PDR 1 R

I 9

h NOTE 'ZO ALL 'KIDS" MXZPIBGS PIZASE HELP US TO REDUCE HASTE! CORI'ACE 'IHE DOCUMEÃZ CXKZROL DESK, RQCM Pl-37 (EZZ. 20079) K) EIaTHHCQR KKR NAME PRCH DISTRIBUTION TOTAL NUMBER 8PPORP~EP: 59R ~ENCL 20 (-/

f.

h

'l 7 I

FIGURE 1 NINE MILE POINT NUCLEAR STATION UNIT Q DOCUMENT TRANSMITTAL AND VERIFICATION ASSIGNED BY W. /~if Z- ZA~ ./ TO . S'~~r DATE 9 jo DUE DATE LOGGED DATE SUBJECT

~e 0 DOCUMENT lA J vc/r. r (L a ~ Co r>

ADDRESSED TO PREPARED BY ~r DATE es v5 REVIEWED BY DATE el/'~v DATE DATE 2

a-,d DATE o DATE DATE ~~ cf DATE DATE g - A9-VERIFIED BY p ~

DATE DATE

-Po-DATE t'~

uw 4/ ~ DATE DATE COMMENTS RECEIVED FOR DATE TRANSMITTAL SENT TO ADDRESSEE BY DATE COPY RETURNED TO SITE BY LOGGED AT SITE DATE FILED AT SITE DOC. CONTROL RECORD DATE OFFICE STAMPS AP-10.2.1 -7 August 1987 S909130020 890630 PDR ADOCK 05000220 /

R PDC

~ ~

FIGURE 1 NINE MILE POINT NUCLEAR STATION UNIT Q DOCUMENT TRANSMITTAL AND VERIFICATION ASSIGNED BY, IJ~it ~. n'A> </ TO . ~~~4i DATE 5'o DUE DATE LOGGED DATE SUBJECT

- MA/, .

/r c DOCUMENT ADDRESSED TO PREPARED BY DATE ~s v~

REVIEWED BY DATE DATE 2 DATE DATE DATE DATE DATE DATE DATE VERIFZED BY DATE DATE DATE DATE COMMENTS RECEIVED FOR DATE TRANSMITTAL SENT TO ADDRESSEE BY DATE COPY RETURNED TO SITE BY LOGGED AT SITE DATE FILED AT SITE DOC. 'CONTROL RECORD DATE OFFZCE STAMPS AP-10.2.1 -7 August 1987

,C

)

1

'C Il l

FIGURE 1 NINE MILE POINT NUCLEAR STATION UNIT J DOCUMENT TRANSMITTAL AND VERIFICATION ASSIGNED BY >.d ~f ~.o'J~,/ TO DATE 5" zo DUE DATE LOGGED DATE SUBJECT

>4/i.

~C O DOCUMENT u cA C ADDRESSED TO PREPARED BY DATE as s-9 REVIEWED BY DATE DATE 2 DATE due/ DATE ATE DATE DATE

~ DATE DATE

. VERIFIED BY DATE DATE DATE DATE COMMENTS RECEIVED FOR DATE TRANSMITTAL SENT TO ADDRESSEE BY DATE COPY RETURNED TO SITE BY LOGGED AT SITE DATE FILED AT SITE DOC. CONTROL RECORD DATE OFFICE STAMPS AP-10.2. 1 -7 August 1987

'a s

~

~

LI 7 Nl'AGARA NMP53853 H O MOHAWK 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 tv 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.: 50-220 LICENSE NO.: 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 I or equal to 15 mrems to any organ.

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) Iodines: 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. (Cont'd)

I 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. 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: 0 hours 0 min.
3. Maximum time period for a batch 0 hours 0 min ~

time period for a batch release:

release.'verage 0 hours 0 min.

5. Minimum time period for a batch release.'. 0 hours 0 min.

Average stream flow during period of release of effluent into a flowing stream: Not Applicable

7. Total volume of water used to dilute the liquid effluent during release periods No Discharges
8. Total volume of water available to dilute the liquid effluent during reporting period 4.54E+01 GL

5'. (Cont. ),

B) Gaseous (Emergency Condenser Vents)

1. Number of batch releases: 0
2. Total 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. Minimum time period for a batch release: 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 QiKQER SUER ~

EST.TOTAL A. t'

l. Total release Ci i'<i'< 1.52E-04 O.OOE+00 2.5E+01 2~ Average release rate for period pCi/sec >'<>'<

1.95E-05 O.OOE+00

3. Percent of Technical Specification Limit LaU,um
1. Total iodine-131 Ci Prolonged Unit
2. Average release rate Outage for period pCi/sec
3. Percent of Technical Specification Limit C.
1. Particulates with half-lives >8 days Ci 7.52E-04 8.71E-04 3.0E+01
2. Average release rate for period pCi/sec 9.67E-05 1.12E-04
3. Percent of Technical Specification Limit
4. Gross alpha radio-activity Ci 2.47E-05 k

3.87E-05 2.5E+01 D.

1. Total release Ci 1.63E+00 1.65E+00 2.5E+01
2. Average release rate for period pCi/sec 2.10E-01 2.10E-01
3. Percent of Technical Specification Limit 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 1st 2nd Q1KEKE QEQKKR E ~ v'c t' t v t

)C)C t'v t' Percent of Quarterly Gamma Air Dose Limit 1.48E-08 O.OOE+00 2~ Percent of Quarterly Beta Air Dose Limit 2.11E-07 O.OOE+00 3~ Percent of Annual Gamma Air Dose Limit to Date 7.39E-09 7.39E-09

4. Percent of Annual Beta Air Dose. Limit to Date 1.05E-07 1.05E-07
5. Percent of Whole Body Dose Rate Limit 5.91E-10 O.OOE+00
6. Percent of Skin Dose Rate Limit 2.91E-09 O.OOE+00 t w't v t t Percent of Quarterly Dose Limit 2.43E-01 2.60E-01
2. Percent of Annual Dose Limit to Date 1.23E-01 2.53E-01
3. Percent of Organ Dose Rate Limit 4.95E-03 5.20E-03 Due to source gases used during annual calibration that were released out the stack after calibration was completed.

I

~ TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (1989)

NINE MILE POINT NUCLEAR STATION Nl GASEOUS EFFLUENTS-ELEVATED RELEASE JANUARX JUNE 1989 NCONTINUOUS MODE Nuclides Released

~ ~

Argon-41 Ci lClt Krypton-85 Ci l'c1.31E-04 Krypton-85m Ci lClC l'ClC Krypton-87 Ci Krypton-88 Ci l'Cl'C Xenon-127 Ci Xenon-133 Ci l'c 2, 1 1 E 05 ltlC Xenon-135 Ci lClC Xenon-135m Ci ltlC Xenon-137 Ci ltlC Xenon-138 Ci lClC 2~

Iodine-131 Ci ltl'C Iodine-133 Ci Iodine-135 Ci l'Cl't ltl'C t'

Strontium-89 Ci 5.37E-06 5.66E-06 Strontium-90 Ci 1.34E-06 1.62E-06 Cesium-134 Ci ltlC Cesium-137 Ci 1.63E-04 2 . 55E-04 Cobalt-60 Ci 5.25E-04 5 . 23E-04 Cobalt-58 Ci lCl'C l'C l'C Manganese-54 Ci 7.92E-06 Barium-Lanthanum-140 Ci lC l'C Antimony-125 Ci lClC Niobium-95 Ci lClC Cerium-141 Ci l'Cl't l'C l'C Cerium-144 Ci l'C l'C Iron-59 Ci l'Cl't Cesium-136 Ci l'CA lClC Chromium-51 Ci l'C l'C Zinc-65 Ci l'CA l'Cl't Iron-55 Ci 5.68E-05 7.76E-05 Molybdenum Ci ltlt l'C l'C

4. ~tag Ci 1.63E+00 1.65E+00 lt Due to source gases used during annual calibration that were released out the stack after calibration was completed.

8 No Batch Mode releases occurred during the reporting period.

l'Cl'C 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 CONTINUOUS MODE BATCH MODE Nuclides Released Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci No discharges No discharges Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci 2.

Iodine-131 Ci Iodine-133 Ci No discharges No discharges Iodine-135 Ci

3. t' Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-Lanthanum-140 Ci Antimony-125 Ci No discharges No discharges Niob ium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci
4. Ci 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 1st 2nd Est. Total ggj t Qu~~ Qumlax. Exxon~

A.

t.

To tal release (no t including tritium, gases, alpha) Ci None None Average diluted con-centration during reporting period pCi/ml

3. Percent of applicable limit B. gati m
l. Total release Ci None None
2. Average diluted con-centration during reporting period pCi/ml
3. Percent of applicable limit C. D'v
1. Total release Ci None None
2. Average diluted con-centration during reporting period pCi/ml
3. Percent of applicable limit D. Gr h t'v't
1. Total release Ci None None E.
1. Prior to dilution liters None None
2. Volume of dilution water used during release period liters
3. Volume of dilution water used during reporting period 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 1st 2nd ggj t Qum~IW QQkrr~X F. fc 'm't Percent of Quarterly whole Body Dose Limit fo

2. Percent of Quarterly Organ Dose Limit Io 3 0 Percent of Annual Whole Body Dose Limit to Date 4, Percent of Annual Organ Dose Limit to Date
5. Percent of 10CFR20 Concentration Limit 'lo
6. 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 Ci'i Strontium-90 Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Manganese-54 Ci Chromium-51 Ci No No Discharges Discharges Zirconium-niobium-95 Ci Molybdenum-99 Ci Technetium-99m Ci Barium-lanthanum-140 Ci Cerium-141 Ci Tungsten-187 Ci Arsenic-76 Ci Iodine-133 Ci Iron-55 Ci Neptunium-239 Ci Praseodymium-144 Ci Iodine-135 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 2.33E+Ol Curies 2.62E+01 Solidification Agent None Processing Method Dewatered Container HIC Package Type A Principle Isotopes Co60, Csl37, Fe55, Mn54, C14, Ni63 Non-compressible Dry Activated Waste m 2.32E+01 Curies 7.70E-02 Solidification Agent None Processing Method None Container Steel LSA Boxes Package Strong Tight Package Principle Isotopes Csl37, Co60, H3, Mn54, Cs134 Compressible Dry Activated Waste ms 8.73E+01 Curies 1.02E+00 Solidification Agent None Processing Method Compacted Container Steel Drums Package Strong Tight Package Principle Isotopes Co60, Cs137, Ni63 AgllOm, Mn54, Oil ms 5.10E+00 Curies 1.25E-03 Solidification Agent Cement Processing Method Cement Solidification Container Steel Liner Package Type A Principle Isotopes 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 5.83E+00 Curies 1.05E+01 2. 5E+01 Solidification Agent None Processing Method Dewatered Container HIC Package Type A Principle Isotopes Co60, C14, Mn54, Cs137, Sr90 Filter Sludge m 5.10E+00 Curies 2.83E+Ol 2.5K+01 Solidification Agent Cement Processing Method Cement Solidification Container Steel liner Package Type A Principle Isotopes Co60, Csl37, Fe55, Mn54, Ni63
c. gLa~

None t'

a~ Spent Resins Filter Sludges Cobalt-60 10 6.92K+01 Cesium-137 10 1.91E+Ol Iron-55 10 3.84E+00 Manganese-54 10 2.60E+00 Carbon-14 10 2.45E+00 Nickel-63 10 1.78E+00 Other 10 1.03E+00

b. Non-compressible Dry Activated Waste Cesium-137 5.94E+01 Cobalt-60 3.32E+01 Tritium 5.33E+00 Manganese-54 1.07E+00 Cesium-134 8.30E-01 Other 1.70E-Ol 13

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 (Cont'd)
c. Compressible Dry Activated Waste Cobalt-60 70 5.19E+01 Cesium-137 3.10E+01 Nickel-63 8.33E+00 Silver-110m 2.92E+00 Manganese-54 2.70E+00 Other 3.15E+00
d. Oil Tritium 70 7.32E+01 Cesium-137 1.22E+Ol Cobalt-60 70 5.97E+00 Iron-55 10 4.70E+00 Plutonium-241 2.73E+00 Other 1.20E+00 t

't'ruck them-Nuclear Systems Barnwell, South Carolina Truck Hanford, WA (Disposition)

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 m~ 1.18E+02 Ci 2.10E+00 Principle Isotopes Co60, Fe55, Mn54, Csl34, Co58

2. t' Cobalt-60 10 6.49E+01 Iron-55 lo 2.41E+01 Cesium-134 10 5.20E+00 Manganese-54 70 3.40E+00 Cobalt-58 Fo 2.30E+00 Other 70 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 Est.Total f t Ex'~~

a.

Spent Resins m~ 2.82E+Ol Curies 5.56E+01 2. 5E+01 Solidification Agent None Container HIC Package Type A Principle Isotopes Co60, Cs137, Mn54, Co58 Fe55, Zn65 Dry Activated Waste m~ 4.26E+01 Curies 1.47E-01 4.0E+Ol Solidification Agent None Containers Steel LSA Box and Steel Drums Package Strong Tight Package Principle Isotopes Co60, Ni63, AgllOm, Csl37, Mn54, Sbl25 Concentrated Waste m~ 2.97E+00 Curies 2.00E+00 3.0E+01 Solidification Agent Dow Media Container Steel Drums Package Type A Principle Isotopes Csl37, Co60, Fe55 Csl34

b. Qla,~>

Spent Resins m 1.43E+01 Curies 2.38E+02 2.5E+Ol Solidification Agent None Container HIC Package Type A Principle Isotopes Co60, Csl37, Mn54, Co58, Fe55, Zn65 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' Est.Total D R~~~

b. ~<~ (Cont ')

Filter Sludge m~ 5.03E+00 Curies 5.00E+01 2.5E+01 Solidification Agent Cement Container Steel liner Package Type A Principle Isotopes Co60, Cs137 Mn54, Ni63

c. Q3~~

None t'

a. Concentrated Wastes Resins Filter Sludges Cobalt-60 7.92E+01 Cesium-137 6.55E+00 Manganese-54 5.50E+00 Cobalt-58 2.34E+00 Iron-55 1.80E+00 Zinc-65 1.33E+00 Nickel-63 1.24E+00 Other 2.04E+00
b. Dry Activated Waste Cobalt-60 6.39E+01 Nickel-63 lo 1.48E+Ol Silver-110m 10 6.17E+00 Cesium-137 70 4.46E+00 Manganese-54 10 4.43E+00 Antimony-125 10 1.61E+00 Cobalt-58 1.37E+00 Chromium-51 10 1.16E+00 Zinc-65 lo 1.11E+00 Other lo 9.90E-01 t ~ ~

t4 Truck Chem-Nuclear Systems Barnwell, South Carolina 17

'C 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.

18

~

g I

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.

19

i A ~ 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 Modification being performed to upgrade Monitor (RAGEMS) system to be more reliable (See Attachment 1)

Liquid Radwaste This monitor was not required to be Effluent Monitor 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 The measuring device is obsolete and Flow Device 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 These monitors are not required to be Monitor and Emergency operable during outage periods as Condenser Radiation specified by Unit Nl Technical Specifications Monitor Instrumentation Operability will be re-established during unit restart.

Stack Flow Measuring In conjunction with modifications to the Device 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).

20

C

~ \

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

1 p

~ I

,r

I g) ~

P 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 to the RAGEMS dilution system to manually override the RAGEMS process computer. The design of this work is complete. The design package will be issued by the end of September 1989. Installation is expected 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.

22

~ 0 C

o r>>

I

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

( a ~-

h

Retrieved from "https://kanterella.com/w/index.php?title=ML18038A663&oldid=2417571"