ML20091L244

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Effluent & Waste Disposal Semiannual Rept Jan-June 1995
ML20091L244
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/30/1995
From: Harry Salmon
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Martin T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
JAFP-95-0387, JAFP-95-387, NUDOCS 9508290035
Download: ML20091L244 (21)
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Text

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U".,W.%".*A L AL 315 342.3840 M New York Power g,,,y g. 3,, mon, s,.

4# Authonty sne exec.e Ouer August 24,1995 l JAFP-95-0387 United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. Thomas T. Martin Regional Administrator

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333. LICENSE NO. DPR-59 Gentlemen:

Attached is the Semi-Annual Radioactive Effluent Release Report for the period ofJanuary 1,1995 through June 30, 1995. This report is submitted in accordance with the requirements of Amendment 93, Appendix B, Section 7.3.C of the James A. FitzPatrick Nuclear Power Plant Technical Specifications.

Included as Attachment 7 are corrections to Attachment 2, Summary of Changes to the Process Control Program, for the Semi-Annual Radioactive Release Reports for 1993 & 1994. The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1.

Distribution is in accordance with Regulatory Guide 10.1, Revision 4.

If you have any questions concerning the attached report, please contact Alfred Jarvis, Chemistry General Supervisor, at the James A. FitzPatrick Nuclear Power Plant.

Very truly yours, C

dQ liARRY P. SALMON, JR.

lips /A./WH/jbh Attachments cc: Document Control Desk (USNRC) T. Salvagno (NMPC)

D. Sherman (ANI Library) M. Colomb W. A. Josiger (NYPA/WPO) A. McKeen J. J. Kelly (NYPA/WPO) RMS/JAF J. Blake (NYPA/WPO) RMS-Il (WPO Records J. Gray (NYPA/WPO) Management)

NRC Resident Inspector /

9508290035 950630 ADOCK 05000333

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i NEW YORK POWER AUTHORITY JAMES A.FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTEDISPOSAL SEMI-ANNUAL REPORT JANUARY 1,1995 - JUNE 30,1995 DOCKET NO.: 50-333 LICENSE NO.: DPR-59

. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

, SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTHORITY

1. Technical Snecification Lim.1
a. Fission and Activation Gases:

(1) The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluent shall be limited as follows:

(a) 12ss than or equal to 500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin from noble gases.

(2) The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous efflueat shall be limited:

(a) During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from beta radiation; and, (b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

b. Tritium, Iodines and Particulates, Half Lives > 8 days:

(1) The dose to a member of the public at or beyond the site boundary from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days released from the plant in gaseous effluent shall be limited:

(a) During any calendar quarter to less than or equal to 7.5 mrem to any organ; and, (b) During any calendar year to less than or equal to 15 mrem to any organ.

(c) Less than 0.1% of the limits of Specification 3.4.a. land 3.4.a.2as a result of burning contaminated oil.

(2) The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

(a) less than or equal to 1500 mrem / year to any organ from Iodine-131, Iodine-133, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 SUPPLEMENTAL INFORMATION (Continued)

c. Liquid Effluents:

(1) The concentration of radioactive materials released to the unrestricted areas shall not exceed the values specified in 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases the concentration shall be limited to 2.00E-04 Ci/ml.

(2) The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limited as follows:

(a) During any calendar quarter, limited 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, (b) During any calendar year, limited 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. Iodines: (None specified)  !
c. Particulates, half-lives > 8 days: (None specified)
d. Liquid effluents: Ouarter 1 Ouarter 2 (1) Fission and activation NONE 4.51E-05 products (mixture MPC)

( Ci/ml) l (2) Tritium (pCi/ml) 3.00E-03 3.00E-03 (3) Dissolved and entrained gases (pCi/ml) 2.00E-04 2.00E-04 2

. , l' NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 SUPPLEMENTAL INFORMATION (Continued)

3. Averane Enerav (None specified)
4. Measurements and Approximations of Total Radioactivity
a. Fission and Activation Gases: Continuous monitor on each release path calibrated to a marinelli grab sample analyzed by gamma spectroscopy; bubbler grab sample analyzed for Tritium.
b. Iodines: Gamma spectral analysis of charcoal cartridge and particulate filter on each release path,
c. Particulates: Gamma spectral analysis of each particulate filter and charcoal cartridge for each release path. A four week per quarter composite of particulate filters for each release path for Strontium-89 and Strontium-90. One week per month particulate filter for each release path for gross alpha.
d. Liquid Effluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha, d
e. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. Scaling factors established from off-site composite sample analyses to estimate concentration of non-gamma emitters. Low activity trash shipments, curie content estimated by dose rate measurement and application of appropriate scaling factors.
f. Error Estimation Method: Overall error for sampling and analysis estimated by combining individual errors using error propagation methods. This processs composed of determinate and undeterminate errors.

Determinate - Pump flowrates, volume measurements and analysis collection yields Undeterminate - Random counting error estimated using accepted statistical calculations 4

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 SUPPLEMENTAL INFORMATION (Continued)

5. Hatch Releases
a. Liquid: Ouarter 1 Ouarter 2 (1) Number of batch releases: NONE 5.00E+00 (2) Total time period for batch NONE 3.51E +02 release: (min)

(3) Maximum time period for NONE 7.40E+01 batch release: (min)

(4) Average time period for NONE 7.02E+01 batch release: (min)

(5) Minimum time period for NONE 6.60E+01 batch release: (min)

b. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases
a. Liquid: Ouarter 1 Ouarter 2 (1) Number of releases: None None (2) Total activity released: None None
b. Gaseous (1) Number of releases: None None (2) Total activity released: None None 4

NEW YORK POWER AUTHORITY 1 JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLE 1A GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL '

UNIT OUARTERI OUARTER 2 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 1.85E+01 2.30E+01 s2.50E+01
2. Average release rate for period pCi/sec 2.38E+00 2.93E+00
3. Tech. Spec. Limit  % *
1. Total lodine-131 Ci 2.35E-04 5.85E-04 s2.50E+01
2. Average release rate for period pCi/sec 3.02E-05 7.44E-05  !
3. Tech. Spec. Limit  % *
  • C. IODINE-133 AND PARTICULATES
1. lodine-133 and Particulates with half-lives >8 days Ci 2.68E-03 7.42E-03 s2.50E+01
2. Average release rate for period pCi/sec 3.45E-04 9.44E-04
3. Tech. Spec. Limit  % * * -
4. Gross alpha radioactivity Ci 8.78E-07 5.20E-07 s2.50E+01 D. TRITIUM
1. Total Release Ci 4.15E-01 3.18E+00 s2.50E+01
2. Average release rate for period pCi/sec 5.34E-02 4.04E-01
3. Tech. Spec. Limit  % * *
  • E. PERCENTOF TECHNICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES
1. Quarterly gamma air dose limit  % 9.47E-03 1.62E-02 '
2. Quarterly beta air dose limit  % 8.10E-04 1.79E-03
3. Yearly gamma air dose limit  % 4.73E-03 8.08E-03
4. Yearly beta air dose limit  % 4.05E-04 8.95E-04
5. Whole body dose rate limit  % 7.53E-03 6.78E-03
6. Skin dose rate limit  % 1.64E-03 1.4SE-03 HALOGENS. TRITIUM AND PARTICULATES l WITH HALF-LIVES >8 DAYS l
7. Quarterly dose limit (organ)  % 3.62E-02 1.04E-01
8. Yearly dose limit (organ)  % 1.81E-02 5.21E-02
9. Organ dose rate limit  % 5.41E-01 5.41E-01 5

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. 3 NEW YORK POWER AUTHORITY  !

JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLE IB GASEOUS EFFLUENTS-ELEVATED RELFASE CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER1 OUARTER 2

1. Fission Gases i

A rgon-41 Ci 9.47E-02 5.81E+00 Krypton-85m Ci 9.83E-01 4.37E+00 Krypton-87 Ci 3.85E+00 5.90E-01 Krypton-88 Ci 2.92E+00 3.26E+00 Xenon-133 Ci 1.97E-01 1.17E+00 Xenon-135 Ci 4.07E+00 1.16E+00 Xenon-135m Ci 1.47E+00 1.17E+00 Xenon-138 Ci 4.94E+00 2.42E+00 TOTAL Ci 1.85E+01 1.99E+01

2. Iodines lodine-131 Ci 2.31E-04 4.06E-04 lodine-133 Cl 1.11E-03 1.13E-03 lodine-135 Ci 1.45E-03 2.24E-04 TOTAL Ci 2.79E-03 1.66E-03
3. Particulates Manganese-54 Ci - - -

3.82E-07 Cobalt-60 Ci - - -

2.06E-07 Strontium-89 Ci - - -

7.23E-07 Barium / Lanthanum-140 Ci 1.18E-06 8.93E-07 TOTAL Ci 1.18E-06 2.20E-06 I

4. Tritium Hydrogen-3 Ci 5.51E-02 1.90E-01 Note: There were no batch releases for this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLEIC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTERI OUARTER 2 I. Fission Gases Krypton-87 Ci ---

6.37E-01 Krypton-88 Ci ---

1.40E+00 Xenon-135 Ci ---

3.35E-01 Xenon-135M Ci ---

7.52E-01 TOTAL Ci ---

3.12E+00

2. Iodines lodine-131 Ci 3.78E-06 1.79E-04 lodine-133 Ci 2.12E-05 2.15E-03 lodine-135 Ci ---

3.95E-03 TOTAL Ci 2.50E-05 6.28E-03

3. Particulates Manganese-54 Ci 1.28E-05 3.99E-06 Cobalt-60 Ci 2.52E-05 1.30E-05 Zinc-65 Ci 6.74E-06 - - -

Strontium-89 Ci ---

3.12E-05 Silver-Il0M Ci ---

5.47E-06 Barium / Lanthanum-140 Ci ---

4.95E-05 Cerium-144 Ci ---

1.35E-05 TOTAL Ci 4.47E-05 6.72E-05

4. Tritium ,

Hydrogen-3 Ci 3.60E-01 2.99E+00 Note: There were no batch releases for this report period, t

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT OUARTERI OUARTER 2 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium. gases and alpha) Ci - --

6.39E-05 s2.50E+01

2. Average diluted concentra-tion during period pCi/ml - --

3.39E-13

3. Applicable limit  % - --

7.52E-07 B. TRITIUM

1. Total Release Ci - --

3.65E-01 s2.50E+01

2. Average diluted concentra-tion during period pCi/ml - --

1.94E-09

3. Applicable limit  % - --

6.47E-05 C. DISSOLVED AND ENTRAINEDGASES

1. Total Release Ci - -- - - -

s2.50E+01

2. Average diluted concentra-tion during period pCi/ml - -- - - -
3. Applicable Limit  % - -- - - -

D. GROSS ALPIIA RADIOACTIVITY

1. Total Release Ci - -- - - -

s2.50E+01 E. VOLUMEOF WASTE RELEASED (PRIOR TO DILUTION) liters - --

2.28E+05 l l

F. VOLUMEOF DILUTION WATER l USED DURING PERIOD liters 3.23E+10 1.89E+11 G. PERCENTOF TECIINICAL SPECIFICATION LIMITS

1. Quarterly Whole Body Dose  % - --

2.90E-05 )

2. Quarterly Organ Dose  % - --

1.74E-05

3. Annual Whole Body Dose  % - --

1.4SE-05 ,

4. Annual Organ Dose  % - --

8.69E-06 l m

NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLE 2B LIQUID EFFLUENTS BATCH MODE NUCLIDES RELEASED UNIT OUARTERI OUARTER 2

1. Fission and Activation Products Manganese-54 Ci - --

2.73E-05 Cobalt-60 Ci - --

3.66E-05 TOTAL Ci - --

6.39E-05

2. Tritium Ilydrogen-3 Ci - --

3.65E-01

3. Dissolved and Entrained Gases NONE Ci - -- - --

Note: There were no continuous mode discharges during this report period.

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NEW YORK POWER AUTHORITY '

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SIIIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est Total Unit Class A Class B Class C Error %

1. Type of Waste 3
a. Spent resins, filter sludges, m 0.00E+00 0.00E+00 0.00E+00 --

evaporator bottoms. etc. Ci 0.00E+00 0.00E+00 0.00E+00 --

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b. Dry compressible waste, m 0.00E+00 0.00E+00 0.00E+00 --

contaminated equipment, etc. Ci 0.00E+00 0.00E+00 0.00E+00 --

3

c. Irradiated components, m 0.00E+00 0.00E+00 0.00E+00 --

control rods, etc. Ci 0.00E+00 0.00E+00 0.00E+00 --

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d. Other: Dry compressible waste, m 6.23E+02 0.00E+00 0.00E+00 --

contaminated equipment, etc. Ci 4.46E-01 0.00E+00 0.00E+00 2.50E+01 for Volume Reduction

2. Estimate of Maior Nuclide Composition (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

None

b. Dry compressible waste, contaminated equipment, etc.

Nonc

c. Irradiated components, control rods, etc. 1 None
d. Other: Dry compressible waste, contaminated equipment, etc. for Volume Reduction.

Isotone Percent Curies Isotone Percent Curies Cobalt-60 4.88E+01 2.18E-01 E Cesium-137 4.53E+00 2.02E-02 E Zinc-65 1.64E+01 7.33E-02 E Carbon-14 1.75E+00 7.80E-03 E l Iron-55 1.56E+01 6.94E-02 E Cesium-134 1.08E+00 4.80E-03 E l Manganese-54 1.07E+01 4.78E-02 E Nickel-63 9.27E-01 4.13E-03 E i

(E - ESTIMATED M - MEASURED) l Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 i TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition No. of Shinments Mode of Transportation Destination i1 Truc~k
  • Scientific Ecology Group Oak Ridge, TN
  • Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)

No. of Shioments Mode of Transportation _ Destination None N/A N/A u

. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL l SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 I TABLE 3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Dry Compressible 4 Waste, Contaminated j Equipment, Etc. Non-compacted 2080 ft' STC 5 Dry Compressible Waste, Contaminated l Equipment, Etc. Non-compacted 1040 ft' STC 12 l l

l Solidification Acent: None HIC - High Integrity Container STC - Strong Tight Container l

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 ATTACHMENT NO.1 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

In accordance with Section 7.3.C.30f Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Offsite Dose Calculation Manual (ODCM) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report.

No changes were made to the ODCM this report period.

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NEW - YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL '

SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 ATTACHMENT NO. 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In accordance with Section 7.3.C.30f Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, changes made to the Process Control Program (PCP) during the reporting period shall be included in the Semi-Annual Radioactive Effluent Release Report.

1. P_ROCESS CONTROL IMPl.EMENTING PROCEDURES Listed below is a brief summary of the revisions made to the plant process control implementing procedures. These changes do not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

o SP-03.06 Representative Sampling and Determination of Radioactive Material, Revision 1, effective 3/22/95 (PORC Meeting 95-037, 2/22/95). Revision 1

contains changes to clarify counting files used for Gamma Spectral Analysis and several editorial corrections, o RPP-15 Radioactive Waste Shipping, Revision 5, effective 6/26/95 (PORC Meeting 95-088 6/14/95). Changes to include onsite storage of radioactive waste.

Changes to clarify the definition of a High Integrity container; Added signature spaces on data forms for processing technicians and Supervisor Review; added clarification for reportable quantities and instructions for the disposition of records. Also included were several minor editorial corrections.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995  !

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ATTACHMENT NO. 3 l

SUMMARY

OF CHANGES TO THE ENVIRONMENTAL MONITORING AND DOSE CALCULATION LOCATIONS In accordance with Section 7.3.C.3 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, a listing of new locations for dose calculation and/or environmental monitoring identified by the land use census shall be included in the Semi-Annual Radioactive Effluent Release Report.

CIIANGES IN ENVIRONMENTAL MONITORING LOCATIONS During the report period, no changes in the Environmental Monitoring Locations required by Technical Specifications were made based on the land use census.

NEW LOCATIONS FOR DOSE CALCULATIONS During the report period, no changes in Dose Calculation Receptor Locations were required based on the results of the land use census.

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. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 ATTACHMENT NO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTAL SAMPLING SCHEDULE In accordance with Section 7.3.C.7 of Amendment 93 to the James A. FitzPatrick Nuclear Power Plant Technical Specifications, the cause for unavailability of any environmental samples required during the report period shall be included in the Semi-Annual Radioactive Effluent Release Report.

EXCEPTIONS TO THE ENVIRONMENTAL SAMPLING PROGRAM

1. The air sampling pumps at the R-3 and R-4 offsite Environmental Sampling Stations were inoperable for approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on 04/12/95 (21:00-23:30 hrs). These pump inoperabilities were caused by a general power failure as a result of a substation malfunction.

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4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT '

EFFLUENT AND WASTE DISPOSAL ,

SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 ATTACHMENT NO. 5 ,

SEMI-ANNUAL

SUMMARY

OF HOURLY METEOROLOGICAL DATA in accordance with Section 7.3.C.2 of Amendment 93 to the James A. Fitz. Patrick Nuclear Power Plant Technical Specifications, an annual summary of meteorological data may be included and submitted in the Semi-Annual Radioactive Effluent Release Report within 60 days after January 1 of each year. .

Meteorological data for the period of January 1,1995 through June 30,1995 will be included with the second half of the 1995 report. -

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

. EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 l ATTACHMENT NO. 6 REPORT NOTES Table 2A Section A and B and Table 2B Normal Liauid Effluents .

The values for Tritium, Strontium-89, Strontium-90, and Iron-55 were calculated from the most recent available sample data. If the actual sample data significantly alters the percent of allowable release limits, the report will be revised and redistributed.  ;

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1995 - JUNE 1995 ATTACHMENT NO. 7 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CORRECTIONS I)' Revisions to Chem Nuclear Procedure (CNSI DM-OP-046-45230) Operation of the FTDS at James A. FitzPatrick Nuclear Power Plant were incorrectly reported in the January-June 1993, July - December 1993, January - June 1994 and July-December 1994 Semi Annual Radioactive Effluent Release Reports. This procedure is not part of the Process Control Program.

2) A statement that the revisions to the Process Control Program "did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes" was inadvertently omitted from the January - June 1993, July - December 1993 and January - June 1994 Semi-Annual Radioactive Effluent Release Reports.

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