JAFP-94-0422, Effluent & Waste Disposal Semiannual Rept for Jan-June 1994

Effluent & Waste Disposal Semiannual Rept for Jan-June 1994

ML20072P637
Person / Time
Site:	FitzPatrick
Issue date:	06/30/1994
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-94-0422, JAFP-94-422, NUDOCS 9409080125
Download: ML20072P637 (21)

Text

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Jamss A. FitzPatrick Nucisar Powsr Plant P O. Box 41 (ycoming. New York 13093 315 342-3840

1. > NewYorkPbwer g gg Harry P. Salmon, Jr.

Resident Manager

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August 29, 1994 JAFP-94-0422 United States Nuclear i Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. Thomas T. Martin Regional .\dministrator

SUBJECT:

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

Attached is the Semi-Annual Radioactive Effluent Release Report for the period ofJanuary 1,1994 through June 30, 1994. This report is submitted in accordance with the requirements of Amendment 93. ippendix B, Section 7.3.C of the James A. FitzPatrick Nuclear Power Plant Technical Specifications.

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 Alan McKeen, Chemistry General Supervisor, at the James A. FitzPatrick Nuclear Power Plant.

Very tr ily yours, IIARRY P. sal. MON, JR.

IIPS/APM/Wil/jbh Attachments cc: / Document Control Desk (USNRC) J. Blaisiak (NMPC/NMP-2)

D. Sherman (ANI Library) R. Barrett W. A. Josiger (NYPA/WPO) - J. Sipp J. J. Kelly (NYPA/WPO) RMS/JAF l J. Blake (NYPA/WPO) RMS-11 (WPO Records J. Gray (NYPA/WPO) Management)

NRC Resident Inspector

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l NEW YORK POWER AUTIIORITY JAAIES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTEDISPOSAL SEMI-ANNUAL REPORT JANUARY 1,1994 - JUNE 30,1994 DOCKET NO.; 50-333 LICENSE NO.: DPR-59

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 SUPPLE 51 ENTAL INFORA1ATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTHORITY

1. Technical Specification Limits

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) Less than or equal to 500 mrem / year to the whole body and less than or equal to 3000 mrem / year to the skin frorn noble gases.

(2) The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluent 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, IIalf 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.1and 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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4-NEW YORK POWER AUTHORITY  !

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL '

SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 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 pCi/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. Maxinipm Permissible Concentrations P. . Fission and activation gases: (None specified) .i

b. Iodines: (None specified)

c. Particulates, half-lives > 8 days: (None specified)

d. Liquid effluents: Ouarter 1 Ouarter 2 (1) Fission and activation NONE 9.77E-05.

products (mixture MPC)

(pCi/ml)

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

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. NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 SUPPLEMENTAL INFORMATION (Continued)

3. Averane Energy (None specified) .

4. Measurements and ApDroximations 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. -

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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 Ef0uents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89, Strontium-90, Iron-55, Tritium, and Alpha. >

e. Solid Waste: Vamma 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 Dowrates, volume measurements and analysis collection yields Undeterminate - Random counting error estimated ; using accepted statistical.

calculations i

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NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 SUPPLE 31 ENTAL INFORMATION (Continued)

5. Batch Releases

a. Liquid: Ouarter 1 Ouarter 2 (1) Number of batch releases: NONE 8.00E+00 (2) Total time period for batch 0 5.70E+02 release: (min)

(3) Maximum time period for 0 8.00E +01 batch release: (min)

(4) Average time period for 0 7.13E +01 batch release: (min)

(5) Minimum time period for 0 6.50E+01 batch release: (min)

b. Gaseous:

There were no gaseous batch releases for this report period.

6. Abnormal Releases

a. Liquid: Ouarter i Ouarter 2 (1) Number of releases: None None (2) Total activity released: None None 1

b. Gaseous (1) Number of releases: None None (2) Total activity released: None None 4

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NEW YORK POWER AUTIIORITY _

JAMES 'A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL-SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 ,

TABLE l A

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GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL. ,

UNIT OUARTERI OUARTER 2 ERROR %

A. FISSION AND ACTIVATION GASES .

g

1. Total Release Ci 1.94E+01 2.44E+01 s2.50E+01

2. Average release rate for period pCi/sec 2.50Et00 3.10E+00 '

3. Tech. Spec. Limit  % *

• i B. IODINE-131

1. Total lodine-131 Ci 1.09E-04 7.81E-05 s2.50E+01

2. Average release rate for period pCi/sec 1.40E-05 9.93E-06

3. Tech. Spec. Limit  % *

• C.' IODINE-133 AND PARTICULATES

1. lodine-133 and Particulates with half-lives > 8 days Ci 1.18E-03 8.96E-04 s2.50E+01'

2. Average release rate for  ;

period pCi/sec 1.52E-04 1.14E-04

3. Tech. Spec. Limit  % * *

4. Gross alpha radioactivity Ci 7.36E-07 1.83E-06 s2.50E+01 D. TRITit,81

1. Total Release Ci 2.65E+00 1.51E+00 s2.50E+01

2. Average release rate for period pCi/sec 3.40E-01 1.92E 3. Tech. Spec. Limit  % * *

• E. PERCENT OF TECilNICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES -

1. Quarterly gamma air dose limit  % 2.91E-02 8.29E-03

2. Quarterly beta air dose limit  % E.74E-03 5.40E-03

3. Y:arly gamma air dose limit  % 1.46E-02. 1.14E-03

4. Yearly beta air dose limit  % 2.87E-03 2.70E-03

5. Whole body dose rate limit  % 4.22E-03 2.48E-03

6. Skin dose rate limit-  % 9.67E-04 5.33E-04 IIALOGENS, TRITIUM AND PARTICULATES WITH liALF-LIVES >3 DAYS /

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7. - Quarterly dose limit (organ)  % 3.52E-02 2.35E-02

8. Yearly dose limit (organ)  % 1.76E-0? 1.17E-02

9. Organ ' dose rate limit .% 4.39E-02 3.05E-02 5

NEW YORK POWER AUTHORITY i JAMES A FITZPATRICK NUCLEAR POWER PLANT l 4

EFFLUENT AND WASTE DISPOSAL  :

SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 .

TABLE IB GASEOUS EFFLUENTS-ELEVATED RELEASE

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CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER1 OUARTER 2

1. Fission Gases l Argon 41 Ci 6.76E+00 1.87E+00 Krypton-85m Ci 1.53E-01 1.12E-01 l Krypton-87 Ci 1.77E-02 4.59E-01  ;

Krypton-88 Ci 3.19E-02 4.51E-01 i Xenon-133 Ci 1.10E+00 2.64E-01 i Xeno '33M Ci - - -

4.07E-01 1 Xenon-135 Ci 2.65E-01 1.34E+00 .I Xenon-135m Ci 4.11E-02 2.60E-01:  ;

Xenon-137 Ci - - -

7.59E-02  !

Xenon-138 Ci 1.48E-01 5.66E-01 l 1

TOTAL Ci 8.52E+00 5.80E+00 .

' 2. julines

• i lodine-131 Ci 2.70E-06 6.53E-06 l 15 dine-133 Ci 2.01E-05 3.29E-05 ,

TOTAL Ci 2.28E-05 3.94E-05  ;

3. Particulates - l Cobalt-57 Ci - - -

2.98E-08 Strontium-89 Ci 5.04E-06 2.59E-06 Strontium-90 Ci 4.44E-08 1.39E-08 Cesium-137 Ci 2.83E-06 - - -

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TOTAL Ci 7.91E-06 2.63E-06 '

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4. Tritium liydrogen-3 Ci 5.73E-02 5.03E-02 i

Note: There were no batch ecleases for this report period. l l

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n NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTERI OUARTER 2

1. Fission Gases Argon-41 Ci 3.73E-02 1.55E-03 Krypton-85m Ci 1.45E-01 5.47E+00 Krypton-87 Ci 4.99E-01 2.69E-01 Krypton 88 Ci 2.83E+00 - - -

Xenon-133 Ci 4.58E-01 2.15E-01 Xenor-133m Ci ---

1.08E+01 Xenon-135 Ci 2.79E+00 1.85E+00 Xenon-138 Ci 4.15E+00 - --

TOTAL Ci 1.09E+01 1.86E+01

2. Iodines lodine-131 Ci 1.06E-04 7.16E-05 lodine-133 Ci 1.06E-03 5.66E-04 Iodine 135 Ci 4.03E-04 - - -

TOTAL Ci 1.57E-03 6.38E-04

3. Particulates Chromium-51 Ci 4.12E-05 - - -

Manganese-54 Ci 1.93E-06 4.79E-06 Cobalt 58 Ci 2.06E-06 7.26E-07 Cobalt-60 Ci 2.39E-05 2.69E-04 Zinc-65 Ci 1.42E-05 8.50E-06 Strontium-89 Ci 8.77E-06 1.12E-05 TOTAL Ci 9.21E-05 2.94E-04

4. Tritium flydrogen-3 Ci 2.59E+00 1.46E+00 Note: There were no batch releases for this report period.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATPKK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1944 TAllLE 2A LIQUID EFFLUENTS--SUMMATION OF AI.L RELEASES EST TOTAL UNIT QUARTERI OUARTER 2 ERROR %

A. FISSION AND ACTIVATION PRODUCTS

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

7.49E-04 s2.50E+01

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

1.40E-12

3. Applicable limit  % - --

1.43E-06 IL TRITIUAI

1. Total Release ci - --

6.4SE-01 s2.50E+01

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

1.21E-09

3. Applicable limit  % - --

s.03E-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 AI. Pila RADIOACTIVITY

1. Total Release Ci - --

7.71E-06 s2.50E+01 l E. VOLUhlEOF WASTE RELEASED (PRIOR TO DILUTION) liters - --

3.58E+05 F. VOLUhlEOF DillTflON WATER USED DURING PERIOD liters 6.14E+11 5.33E+11 G. PERCENTOF TECIINICAL SPECIFICATION LINIITS

1. Quarterly Whole Body Dose  % - --

7.20E-04

2. Quarterly Organ Dose  % - --

4.22E-04

3. Annual Whole Body Dose  % - --

3.60E-04

4. Annual Orean Dose  % - --

2.11E-04 8

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NEW YORK POWER AUTIf0RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 TABLE 2B LIQUID EFFLUENTS llATCll MODE NUCLIDES REI. EASED UNIT OUARTERI OUARTER 2

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

1.42E-04 Iron-55 Ci - --

2.65E-04 Cobalt-58 Ci - --

7.06E-06 Iron-59 Ci - --

8.80E-05 Cobalt-f4 Ci - --

9.61E-05 Zinc-65 Ci - --

8.09E-05 TOTAL Ci - --

6.79E-04

2. Tritium liydrogen-3 Ci - --

6.45E-01

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

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

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i. . l NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS  ;

A. SOIID WASTE SIIIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) i 6-month Period Est Total Unit Class A Class B Class C Error %

1. Tyne of Waste 3

a. Spent resins, filter sludges. m 6.62E+01 0.00E+00 0.00E+00 --

evaporator bottoms,'etc. Ci 2.94E+02 0.00E+00 0.00E+00 2.50E+01 3

b. Dry compressible waste, m 4.91E+02 0.00E+00 0.00E+00 --

contaminated equipment, etc. Ci 3.53E+00 0.00E+00 0.00E+00 2.50E+01 3 '

c. ' Irradiated components, m 0.00E+00 3.85E+00 3.25E+00 --

control rods, etc. Ci 0.00E+00 1.47E+02 3.66E+04 2.50E+01 3

d. Other: m 0.00E+00 0.00E+00 0.00E+00 N/A Ci 0.00E+00 0.00E+00 0.00E+00 N/A

2. Estimate of Maior Nuclide Composition (hv type of waste)

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

Isotone Percent Curies Isoto,p_e Percent Curies Zine-65 3.68E+01 1.08E+02 M Cobalt-58 3.03E+00 8.93E+00 M Cobalt 60 2.31E+01 6.81E+01 M Cesium-137 1.54E+00 4.53E+00 M Iron-55 1.98E+01 5.82E+01 E Chromium-51 1.28E+00 3.77E+00 M Manganese-54 1.24E+01 3.65E+01 M Iron-59 1.28E+00 3.77E+00 E

b. Dry compressible waste, contaminated equipment, etc. l Isotope Percent Curies Isotope Percent Curies Cobalt-60 4.99E+01 1.76E+00 E Zine-65 1.87E+00 6.6OE-02 E Iron-55 2.87E+01 1.01E+00 E Manganese-54 8.67E-01 3.06E-02 E Ilydrogen-3 1.49E+01 5.26E-01 E Cobalt-58 2.48E-01 8.74E-03 E Nickel-63 3.42E+00 1.21E-01 E Cesium-137 6.75E-02 2.38E-03 E I

c. Irradiated components, control rods, etc. 1 Isotone Percent Curies Isotone Percent Curies Iron-55 4.83E+01 1.77E+04 E Hydrogen-3 1.06E-01 3.88E+01 E Cobalt-60 4.67E+01 1.71E+04 E Nickel-59 2.43E-02 8.91E+00 E Nickel-63 4.30E+00 1.58E+03 E Carbon-14 7.00E-03 2.57E+00 E Manganese-54 5.91E-01 2.17E+02 E Cesium-137 2.73E-04 1.00E-01 E l

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a NEW YORK POWER AUTHORITY ,

JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

d. Other: .

N/A .

(E - ESTIMATED M - MEASURED) ,

Percentage of nuclides and total activities are based on a combination of direct measurements and scaling for non-gamma emitting nuclides.

3. Solid Waste Disposition i No. of Shioments Mode of Transnortation Destina!io2 16 Truck Barnwell, SC 9 Truck *Alaron Corp.

Wampum, PA 1 Truck *Quadrex Corporation Oak Ridge, TN

• Volume Reduction Facility -

H. IRRADIATED FUEL SIIIPMENTS (Disposition) g No. of Shbments Mode of Transportation Destination None N/A N/A 1

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NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 TABLE 3B SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS A. NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent R" sin Dewatered 205.8 ft3 HIC 9 Dry Compressible Non-Waste (DAW) Compacted 177.5 ft3 STP 1 Spent Resin Dewatered 170.8 ft 3 HIC 3 Dry Compressible Non-Waste (DAW) Compacted 2080 ft3 STP 9 Dry Compressible Non-Waste (DAW) Compacted 380 ft 3 STP 1 Solidification Agent: None B. NRC CLASS B SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Irradiated Components Dewatered 135.8 ft 3 HIC 1 Solidification Agent: None C. NRC CLASS C SOURCE OF PROCESSING CONTAINER TYPE OF NUMBER WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Irradiated Components Dewatered 57.4 ft 3 STP 2 Solidification Acent: None HIC - High Integrity Container STP - Strong Tight Package I

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NEW YORK. POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994

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ATTACIBfENT NO.1 CIIANGES TO TIIE 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 JAMES A. FITZPATRICK NUCLEAR POWER PLANT.

EFFLUENT - AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY.1994 - JUNE 1994 i

ATTACHMENT NO. 2 I

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM 1

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 Semiannual Radioactive Effluent Release Report.

1. CONTRACTOR PROCEDURES -

a. Changes to the Chem-Nuclear Systems, Inc. Procedures are as listed:

CNSI Procedure, QA-AD-001 - Quality Assurance Program, Revision 7, 5/25/94 (PORC Meeting No.94-064). Revision 7 of the CNSI QA Program'provides equivalent or enhanced QA Program commitment assuring continuing compliance with 10CFR-71, Subpart H; 10CFR72, Subpart G; and 10CFR50, Appendix B.

Reference to RA-0740-93, Nov. 3,- 1993 memo from Chem-Nuclear to NRC.

Revision 7 also changes category of procedure from " Technical" to ,

" Administrative". ,

CNSI Procedure FO-AD-002-41802 - Operating Guidelines For Use Of Polyethylene High Integrity Containers at James A. FitzPatrick*, Revision 2, t 5/25/94 (PORC Meeting No.94-064). Steps 1.3.1,1.3.2 and 1.3.3 were deleted due to Chem-Nuclear policy changes allowing use of the JAF QA Program. Also Step'5.1 was changed to add the responsibility for Chem-Nuclear to also ensure their customers have the right documentation on hand for High Integrity Containers.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 ATTACIISIENT NO. 2 (CONT)

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAAI l

CNSI Procedure FO-OP-022-41802 - Ecodex/Precoat/Powdex/Solka-Floc / Diatomaceous Earth Dewatering Procedure For CNSI 14-215 Or Smaller Liners At James A. FitzPatrick Nuclear *, Revision 1,2/18/94 (PORC Meeting No.94-018). Step 2.3 was changed and added to ensure that all paperwork is documented in accordance with Chem Nuclear Quality Assurance Program. Step 2.4 added to ensure that all work done by Chem-Nuclear personal, is done to Chem Nuclear Safety Procedures. Step 3.1.6added to ensure that the dewatering completion record is completely filled out. Step 3.3.1.3 added to ensure that the CNSI Technician follows all JAF plant and CNSI safety procedures. Step 3.3.1.4 added to ensure that the CNSI Technician enters any confined spaces in accordance with both Chem Nuclear and JAF Safety Procedures. Step 4.1.3 added to ensure that all connections for the dewatering manifold is in its proper configuration. Step 4.2.5added to ensure proper dewatering. Step 5.0 added to ensure that all paperwork done by the CNSI technician is in accordance with Chem Nuclear Quality Assurance procedures.

CNSI Procedure FO-OP-023-41802, Bead Resin / Activated Carbon Dewatering Procedure For CNSI 14-215 or Smaller Liners At James A. FitzPatrick Nuclear *,

Revision 1 (Porc Meeting No.94-018). Step 1.2 added to ensure that the dewatering process meets the acceptance criteria. Step 2.7 added to ensure that all work done by Chem-Nuclear personal, is done to both Chem Nuclear and JAF Safety Procedures. Step 3.3.ladded to ensure extra safety during disassembly of equipment. Step 3.3.1.4 added to ensure that the CNSI technician works to the Chem Nuclear Safety Program. Step 3.3.1.5 added to ensure that the CNSI )

Technician enters any confined space in accordance with both Chem Nuclear and '

JAF Safety Procedures. Step 6.0 added to ensure that all paperwork done by the CNSI Technician is in accordance with Chem Nuclear Quality Assurance Procedures.

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i NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 ATTACII51ENTNO. 3 l

SUMMARY

OF CIIANGES TO TIIE ENVIRON 5fENTAL AIONITORING AND l DOSE CALCULATIONLOCATIONS 1 i

i In accordance with Section 7.3.C.30f 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 ENVIRONMENTAI. MONITORING LOCATIONS

1. No changes in the Environmental Monitoring Locations required by Technical Specifications were made based on the land use census, i

NEW LOCATIONS FOR DOSE CALCULATIONS -

1. . No changes in Dose Calculation Receptor Locations were required based on land use census.

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1 NEW YORK POWER. AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j EFFLUENT - AND WASTE DISPOSAL i

SEMI-ANNUAL REPORT ' JANUARY 1994 - JUNE 1994 ATTACIIMENTNO. 4 DEVIATIONS FROM THE REQUIRED ENVIRONMENTALSAMPLING SCHEDULE In accordance with Section 7.3.C.7of Amendment 93 to the James A. FitzPatrick

• Nuclear Power Plant Technical Specifications, the cause for unavailability of any l environmental samples required during the report period shall be included in the Semi-Annual Radioactive Effluent Release Report. >

EXCEPTION TO THE ENVIRONMENTAL SAMPLING PROGRAM'

l. There were no exceptions to the Environmental Sampling Program, as required by the Technical Specifications, for the report period of January 1,1994 through June 30,1994.

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, NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK- NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL -

SEMI-ANNUAL REPORT JANUARY 1994 - JUNE 1994 ATTACIIMENT NO. 5 SEMI-ANNUAL

SUMMARY

OF IIOURLY METEOROLOGICAL DATA c

In accordance with Section 7.3.C.2 of Amendment 93 to the James A. FitzPatrick 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 I of each year.

Meteorological data for the period of January 1,1994 through June 30,1994 will be-included in the second half of the 1994 report.

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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL. REPORT JANUARY 1994 - JUNE 1994 I l

ATTACIIMENT NO. 6 REPORT NOTES l

1 Table 2A Section A and B and Table 2B Normal Liauid Effluents l 1

i The values for Tritium, Strontium-89, Strontium-90, and Iron-55 were calculated from 1993 Quarter 4, 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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