ML18038A369

Forwards Nine Mile Point Nuclear Station-Unit 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1991 & Revs 4 & 5 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.

ML18038A369
Person / Time
Site:	Nine Mile Point
Issue date:	08/29/1991
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17058A955	List: ML17058A954 ML17058A956 ML18038A369
References
NMP2L-1313, NUDOCS 9109090102
Download: ML18038A369 (39)

Text

ACCEI;ERATED DI, UTION DEMONS . TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9109090102 DOC.DATE: 91/08/29 NOTARIZED: NO DOCKET g FACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 AUTH. NAME AUTHOR AFFXLIATION TERRY,C.D. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) R

SUBJECT:

Forwards "Nine Mile Point Nuclear Station-Unit 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1991" 6 Revs 4 5 to Administrative Procedure AP-3.7.1, "Unit 2 Radwaste Process Control Program." D DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR f ENCL J SIZE:

TXTLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES PM Q8W I&7S RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-1 LA 3 3 PD1-1 PD 1 1 BRINKMAN,D. ~

1 1 D INTERNAL: ACRS 1 1 AEOJ3J DS P/TPAB 1 1 NRR/DREP/PRPB11 2 2 EGMuTLE" 1 1 RGN1 DRSS/RPB 2 2 GN~FX"5E 0'2 1 1 EXTERNAL: BNL TICHLER, J03 1 1 EGGG SIMPSON,F 2 2 NRC PDR 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17

0 ~ M t fl N II(

V Mlle%,IRA 0 +~opsg NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD. SYRACUSE N Y 13212/TELEPHONE (315) 474 1511 August 29, 1991 NMP2L 1313 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: Nine Mile Point Unit 2 Docket No. 50-410 NPF-69 Gentlemen:

SUBJECT:

JANUARY JUNE 1991 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT In conformance with the Nine Mile Point Nuclear Station Unit 2 (NMP2)

Technical Specifications, we are enclosing the Semi-Annual Radioactive Effluent Release Re ort for the period January 1, 1991 through June 30, 1991.

Included in this report is a summary of liquid, gaseous and solid effluents released from the station during the reporting period (Tables 1-3) and an explanation as to the cause and corrective actions regarding the inoperability of any station liquid and gaseous effluent monitoring instrumentation (Attachment 1). During the reporting period there were no revisions to the Offsite Dose Calculation Manual (Attachment 2) or the Process Control Program Procedure (Attachment 3).

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 NMP2 Offsite Dose Calculation Manual. Distribution is in accordance with Regulatory Guide 10.1, 10 CFR 50.4 (b) (1) and the Technical Specifications.

If you have any questions concerning the attached report, please contact Beth Thomas, Chemistry and Radiation Protection Support, Syracuse Corporate Office, Salina Meadows (315) 428-7188.

Very truly yours, C. D. Terr Vice President Nuclear Engineering EDT/sek 001371LL Enclosure xc: Regional Administrator, Region I Mr. R. A. Capra, Project Director, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR Mr. W. L. Schmidt, Senior Resident Inspector Mr. D. S. Haverkamp, Chief, Reactor Projects Section No. 1B Records Management Cd~Q Q'g .

~9109090i02 910829'..0" PDR ADOCfC'5000@i R PDR"

NINE MILE POINT NUCLEAR STATION UNIT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1991 DOCKET NO.: 50-410 LICENSE NO.: NPF-69 9109090102 )

e 001371LL

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY JUNE 1991 Facility: Nine Mile Point Unit 2 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 or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.

2. The air dose from noble gases released in gaseous effluents from the Nine Mile Point 2 Station to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mr for gamma radiation and less than or equal to 10 mrad for beta radiation and, during any calendar year to less than or equal to 10 mr for gamma radiation and less than or equal to 20 mrad for beta radiation.

B&C) 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 in gaseous effluents from the site to areas at or beyond the site boundary, shall be less than or equal to 1500 mrem/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 eight days as part of gaseous effluents released from the Nine Mile Point 2 Station to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.

D) Liquid Effluents:

1. 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 gases, the concentration shall be limited to 28-04 microcuries/ml total activity.

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2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2. Maximum Permissible Concentrations:

A) Fission and activation gases:

None specified B&C) Iodines and particulates, half lives > 8 days:

None specified D) Liquid Effluents:

10CFR 20, Appendix B, Table II, Column 2.

Avg MPC (Jan. March) = 1.27E-03 uCi/ml Avg MPC (April June) = 1.87E-03 uCi/ml

3. Average Energy (Fission and Activation gases Mev):

Jan. March: Eg = 1.26; Ep 4.69E-01 Apr. June: Eg = 1.44; Ep 5.96E-01

4. Measurements and Approximations of Total Radioactivity:

Described below are the normal 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) of an isokinetic sample stream.

B) Iodines: Iodine effluent activity is determined by gamma spectroscopic analysis of charcoal cartridges sampled from an isokinetic sample stream.

C) Particulates: Activity released is determined by gamma spectroscopic analysis of particulate filters sampled from an isokinetic sample stream.

D) Tritium: Tritium effluent activity is measured 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.

001371LL

4. Measurements and Approximations of Total Radioactivity: (Continued)

P) Solid Effluents: Isotopic contents of waste shipments are determined by gamma spectroscopy analyses and water content estimates 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 plant smears.

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: 51

2. Total time period for batch releases: 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> 16.8 min.

3. Maximum time period for a batch release: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 28.3 min.

4, Average time period for a batch release: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 18 min.

5. Minimum time period for a batch release: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 17 min.

6. 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: 1.12 E+09 liters

8. Total volume of water available to dilute the liquid effluent during reporting period: 2.80 E+10 liters B) Gaseous (Primary Containment Purge):

1. Number of batch releases: 6

2. Total time period for batch releases~: 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> 35 min.

3. Maximum time period for a batch release: 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 5 min.

4. Average time period for a batch release: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 26 min.

5. Minimum time period for a batch release: 11 hours 59 min.

6. Abnormal Releases:

A. Liquids none B. Gaseous none Actual purge times are less than shown. The times presented are the sampling times, and represent a conservative approximation to actual purge times, (approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per purge). e 001371LL

TABLE 1A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1991 1st 2nd EST.TOTAL UNIT QUARTER QUARTER ERROR X A. Fission & Activation ases

1. Total release Ci 1.57E+01 2.90E+01 5.0E+01

2. Average release rate for period uCi/sec 2.00E+00 3.69E+00

3. Percent of Technicali Specification Limit B. Iodines

1. Total iodine Ci 2.70E-03 3.43E-03 5.0E+01

2. Average release rate for period uCi/sec 3.47E-04 4.36E-04

3. Percent of Technicali Specification Limit C. Particulates2 ~

1. Particulates with half-lives > 8 days Ci 1.29E-03 7.80E-03 5.0E+01

2. Average release rate for period uCi/sec 1.66E-04 9.92E-04

3. Percent of Technicali Specification Limit

4. Gross alpha radio-activity Ci 7.47E-06 1.84E-05 5.0E+01 D. Tritium3

1. Total release Ci 3.42E+00 3.14E+00 5.0E+01

2. Average release rate for period uCi/sec 4.40E-01 3.99E-01

3. Percent of Technicali Specification Limit Refer to Section E on next page.

Includes Mo-99 if applicable.

e Tritium, Iron-55, and Strontium results for the second quarter were not received from the offsite vendor as of August 15, 1991. Actual numbers will be provided in the next Semi-Annual Report.

001371LL

TABLE 1A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ELEVATED AND GROUND LEVEL JANUARY JUNE 1991 1st 2nd UNIT QUARTER QUARTER E. Percent of Technical S ecification Limits Fission and Activation Gases:

1. Percent of Quarterly Gamma Air Dose Limit (5 mrem) 1.50E-01 2.98E-01

2. Percent of Quarterly Beta Air Dose Limit (10 mrem) 8.52E-04 1.88E-03

3. Percent of Annual Gamma Air Dose Limit to Date (10 mrem) 7.51E-02 2.24E-01

4. Percent of Annual Beta Air Dose Limit to Date (20 mrem) 4.26E-04 1.37E-03

5. Percent of Whole Body Dose Rate Limit (500 mrem/yr) 5.87E-03 1.13E-02

6. Percent of Skin Dose Rate Limit (3000 mrem/yr) 1.13E-03 2.20E-03 Tritium Iodines and Particulates with half-lives reater than 8 da s

1. Percent of Quarterly Dose Limit (7.5 mrem) 2.00E-02 1.85E-02

2. Percent of Annual Dose Limit to Date (15 mrem) 1.00E-02 1.92E-02

3. Percent of Organ Dose Rate Limit (1500 mrem/yr) 7.86E-04 7.50E-04 001371LL

TABLE 1B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 GASEOUS EFFLUENTS-ELEVATED (STACK)

JANUARY JUNE 1991 CONTINUOUS MODE BATCH MODE Nuclides Released 1 ~ Fission Gases~

Argon-41 Ci 3.19E+00 6.29E+00 Krypton-85m Ci 8.55E-02 Krypton-87 Ci 5.32E-01 4.06E-01 Krypton-88 Ci 3.30E+00 1.44E+01 Xenon-133 Ci 4.70E-02 Xenon-135 Ci 2.52E-01 Xenon-135m Ci 1.62E+00 4.75E-01 Xenon-137 Ci 3.75E+00 Xenon-138 Ci 6.78E+00 3.55E+00 2~ Iodines~

Iodine-131 Ci 2.23E-04 1.82E-04 Iodine-133 Ci 2.48E-03 3.08E-03 Iodine-135 Ci 3~ Particulates

'trontium-89 Ci 5.31E-05 0 Strontium-90 Ci **

Strontium-91 Ci Cesium-134 Ci **

Cesium-137 Ci Cobalt-60 Ci 9.85E-06 1.01E-04 Cobalt-58 Ci 9.06E-05 Manganese-54 Ci ** 4.95E-06 Barium-Lanthanum -140 Ci **

Antimony-125 Ci **

Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci **

Iron-59 Ci **

Cesium-136 Ci **

Chromium-51 Ci 9.13E-05 3.69E-03 Zinc-65 Ci 1.44E-05 4.00E-04 Iron-55 Ci Molybdenum-99 Ci 9.14E-05 3.93E-04 4, Tritium Ci 1.12E+00 1.88E+00 1.72E-02 3.62E-02

~

Concentrations less than the lower limit of detection of 1.00E-04 uCi/ml for noble gases, 1.00E-11 uCi/ml for particulates, 1.00E-12 uCi/ml for iodines and 1.00E-06 uCi/ml for tritium as required by Technical Specifications are indicated with a double asterisk.

Iron-55 and Strontium results (indicated with a pound sign) for the second quarter were not received from the offsite vendor as of August 15, 1991. Actual numbers will be provided in the next Semi-Annual Report.

001371LL

I TABLE 1C SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 GASEOUS EFFLUENTS-COMBINED GROUND LEVEL-ELEVATED (REACTOR BUILDING/RADWASTE VENT)

JANUARY JUNE 1991 CONTINUOUS MODE BATCH MODE Nuclides Released

1. Fission Gases Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci

2. Iodines~

Iodine-131 Ci 1.02E-05 Iodine-133 Ci 1.53E-06 1.53E-04 Iodine-135 Ci

3. Particulates~ No batch releases Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 1.05E-04 7.11E-05 Cobalt-58 Ci 9.90E-07 1.68E-05 Manganese-54 Ci 4.64E-05 4.42E-06 Barium-Lanthan um-140 Ci Antimony-125 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci 1.48E-04 1.85E-03 Zinc-65 Ci 5.04E-04 5.90E-04 Iron-55 Ci Molybdenum-99 Ci 2.28E-04 5.88E-04

4. Tritium Ci 2.28E+00 1.23E+00

~

Concentrations less than the lower limit of detection of 1.00E-04 uCi/ml for noble gases, 1.00E-11 uCi/ml for particulates, 1.00E-12 uCi/ml for iodines, and 1.00E-06 uCi/ml for tritium as required by Technical Specifications are indicated with a double asterisk.

001371LL

TABLE 2A SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1991 1st 2nd Est. Total Unit Quarter guarter Error X A. Fission and activation roducts2'3

1. Total release (not including tritium, gases, alpha) Ci 5.03E-02 2.798-02 2.50E+1

2. Average diluted con-centration during reporting period uCi/ml 3.378-09 1.92E-09

3. Percent of applicablei limit x B. Tritium2'3

1. Total release Ci 1.448+00 1,84E+00 2.50E+1

2. Average diluted con-centration during reporting period uCi/ml 9.93E-08 1.36E-07

3. Percent of applicable limit 3.31E-03 4.548-03 C. Dissolved and entrained asesl

1. Total release Ci 1.448-04 5.00E+1

2. Average diluted con-centration during reporting period uCi/ml 9.918-12

3. Percent of applicable limit 4.968-04 D. Gross al ha radioactivit ~

1. Total release Ci E. Volumes

1. Prior to dilution liters 2.528+06 2.07E+06 2.50E+1

2. Volume of dilution water used during release period liters 6.24E+08 4.998+08 2.508+1

3. Volume of dilution water available during reporting period liters 1.458+10 1.358+10 2.50E+1 Refer to F on next page Concentrations less than the lower limit of detection of 5.008-07 uCi/ml for gamma emitting nuclides, 1.00E-05 uCi/ml for dissolved and entrained noble gases and tritium, 5.008-08 uCi/ml for Sr89/90, 1.00E-06 uCi/ml for Fe55 and 1.008-07 uCi/ml for gross alpha radioactivity as required by Technical Specifications are indicated with a double asterisk.

For batch and continuous mode, the Iron-55 and Strontium results for the second quarter, and Tritium results for May and June were not received from the offsite vendor as of August 15, 1991. Actual numbers will be provided in the next Semi-Annual Report. The numbers provided represent conservative estimates.

001371LL

TABLE 2A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY JUNE 1991 1st 2nd Uni t Quarter Quarter F. Percent of Technical S ecification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem) 2.11E+00 2.90E-01

2. Percent of Quarterly Organ Dose Limit (5 mrem) 1.40E+00 1.87E-01

3. Percent of Annual Whole Body Dose Limit to Date (3 mrem) 1.05E+00 1.20E+00 4, Percent of Annual Organ Dose Limit to Date (10 mrem) 7.00E-01 7.95E-01

5. Percent of 10CFR20 Concentration Limit 8.07E-03 7.42E-03

6. Percent of Dissolved or Entrained Noble Gas Limit (1.00E-5 uCi/ml) 4.96E-06 i Concentrations less than the lower limit of detection of 2E-4 uCi/ml as required by Technical Specifications are indicated with a double asterisk.

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TABLE 2B SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 LIQUID EPPLUENTS RELEASED JANUARY JUNE 1991 CONTINUOUS MODEi'~ BATCH MODE~

Nuclides Released~

Strontium-89 Ci 4.53E-04 Strontium-90 Ci 3.62E-05 Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci 1.47E-04 Cobalt-60 Ci 8.38E-03 1.45E-03 Iron-59 Ci 5.83E-05 Zinc-65 CI 3.73E-02 4.95E-03 Manganese-54 Ci 3.50E-03 5.92E-04 Chromium-51 Ci 8.44E-04 1.60E-02 Zirconium-niobium-95Ci Molybdenum-99 Ci Technetium-99m Ci Barium-lanthanum-140Ci Cerium-141 Ci Hydrogen-3 Ci 1.44E+00 1.84E+00 Sodium-24 Ci Iron-55 Ci 4.42E-03 Manganese-56 Ci Nickel-65 Ci Arsenic-76 Ci Iodine;133 Ci Tungsten-187 Ci Xenon-133 Ci 1.31E-04 Xenon-135 Ci 1.24E-05 Concentrations less than the lower limit of detection of 5.00E-07 uCi/ml for gamma emitting nuclides, 1.00E-05 uCi/ml for dissolved and entrained noble gases and tritium, 5.00E-08 uCi/ml for Sr89/90 and 1.00E-06 uCi/ml for Pe55 as required by Technical Specifications are indicated with a double asterisk.

No activities greater than their LLD for Sr-89/90 and Pe-55 are anticipated for the continuous mode as indicated with a 5 sign.

e For batch and continuous mode Iron-55 and Strontium results for the second quarter, and Tritium results for May and June were not received from the offsite vendor as of August 15, 1991. Actual numbers will be provided in the next Semi-Annual Report. The numbers provided represent conservative estimates.

001371LL

TABLE 3A SEMI-ANNUAL RADIOACTIVE EPPLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1991 A. Solid Waste Shi ed Off-Site for Burial or Dis osal Not irradiated fuel EST. TOTAL

1. T e of Waste UNIT 6-MONTH PERIOD ERROR

a. Spent resins, filter sludge bottoms, etc. m 9.05E+01 Ci 1.00E+03 2.50E+01

b. Dry compressible waste, contaminated equip., etc. 6.12E+01 Ci 1.36E+00 5.00E+01

c. Irradiated components, control rods, etc. m None None

d. Other m None Ci None All were solidified in cement as Class A waste in strong, tight containers. All were shipped as radioactive LSA.

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TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1991

2. Estimate of Ma'or Nuclide Com osition b T e of Waste

a. Spent Resins, filter sludges, evaporator bottoms, etc.

Percent Zinc-65 6.59E+01 Cobalt-60 1.08E+01 Iron-55 . 9.63E+00 Chromium-51 8.38E+00 Manganese-54 3.43E+00 Others 1.82E+00

b. Dry Compressible Waste, Contaminated Equips, etc.

Percent Chromium-51 4.61E+01 Zinc-65 2.63E+01 Iron-55 1.14E+01 Cobalt-60 8.10E+00 Manganese-54 2.64E+00 Hydrogen-3 (Tritium) 1.97E+00 Nickel-63 1.60E+00 Iron-59 1.10E+00 Others 7.90E-01

c. Irradiated components, control rods, etc.

NONE 001371LL

TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1991

3. Solid Waste Dis osition Number of Shi ments Mode of Trans ortation Destination 19 Truck Burial in Barnwell SC B. IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shi ment Mode of Trans ortation Destination None C. SOLID WASTE SHIPPED OFFSITE TO VENDORS FOR PROCESSING AND SUBSE UENT BURIAL Below is a summary of Dry Activated Waste that was shipped offsite for processing and burial by vendor facilities (i.e., ALARON, QUADREX and/or SCIENTIFIC ECOLOGY GROUP) during January June,1991. 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-2 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 information provided in this section, therefore, is in addition to that required by the NMP-2 Technical Specifications. The following data represents the actual shipments made from Quadrex of our non-compacted commingled trash. This trash was shipped to Oakridge, TN for processing prior to burial.

T e of Waste noncompacted Unit Burial Est. Total commingled trash shipped to Volume Error Oakridge, TN for processing prior to burial at Barnwell, SC m3 4.74E+00 Ci 6.84E-02 5.00E+01

2. Estimate of Ma'or Nuclide Com osition Percent Cobalt-58 3.25E+01 Cobalt-60 2.96E+01 Zinc-65 2.28E+01 Manganese-54 8.28E+00 Cesium-137 4.62E+00 Iron-55 2.20E+00 001371LL

TABLE 3A (Continued)

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY JUNE 1991

3. Solid Waste Dis osition~

Number of Shi ments Mode of Trans ortation Destination Truck -Processing in Oakridge, TN

-Burial in Barnwell, SC.

The number of shipments reported here represents the total number that Quadrex ships from Tennessee to South Carolina. This does not represent the number of shipments Niagara Mohawk sent to Quadrex, which was 2 in total.

001371LL

ATTACHMENT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 EXPLANATION OF INSTRUMENTATION INOPERABILITY JANUARY JUNE 1991 In accordance with NMP Unit 2 Technical Specifications, 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 fall into this category during the January June 1991 reporting period along with a description of causes for the inoperability and, as appropriate, corrective actions taken to resolve the problems.

Date of Instrument Date Returned Cause of Inoperability/

Instrument Ino erabilit to Service Corrective Actions Service Water A March 5, 1991 April 23, 1991 Sample pump tripped due Radiation Monitor April 23, 1991 to flow switch problems from silt build-up. In addition, corrosion build-up created low flow condition. The flow switch problem is being investigated by design engineering.

Service Water B Oct. 1, 1990 Feb. 4, 1991 Inoperable period was Radiation Monitor Feb. 4, 1991 due to an unreliable sample pump. Pumps were recently upgraded by plant modification.

001371LL

ATTACHMENT 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 RECENT CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL JANUARY JUNE 1991 During the January-June 1991 reporting period, there were no changes to the Offsite Dose Calculation Manual (ODCM), (Rev. 5).

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~p ATTACHMENT 3 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NINE MILE POINT NUCLEAR STATION 2 CHANGES TO THE PROCESS CONTROL PROGRAM JANUARY JUNE 1991 During the reporting period of January thru June 1991 there were changes to the PCP or Process Control Program to reflect personnel re-organization of titles and responsibilities. The old revision along -with the new revision are included with the report.

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