ML20210R250

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Ja FitzPatrick Nuclear Power Plant Effluent & Waste Disposal Semi-Annual Rept,Jan-June 1997
ML20210R250
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/30/1997
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20210R238 List:
References
NUDOCS 9709020359
Download: ML20210R250 (18)
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1 NEW YORK POWER AUTIIORITY JAMES A.FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTEDISPOSAL l

SEMI-ANNUAL REPORT l

l JANUARY 1,1997 - JIINE 30,1997 l

l DOCKET NO.: 50-333 I LICENSE NO.: DPR-59 s

9709020359 970821 PDR ADOCK 05000333 R p:. g

NEW YORK POWER AUTHORITY

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

i

- - -- SEMI ANNUAL REPORT JANUARY 1997 - JUNE 1997 SUPPLEMENTAL INFORMATION FACILITY: JAFNPP LICENSEE: NEW YORK POWER AUTilORITY

- 1. Technical Snecification Limits

a. Fission and Activation Gases:

l l

(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) Ixss than or equi 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 s".e boundary from noble gases released from the plant in gaseous efiluent shall be limited:

i (a) During any calendst quarter, to less than or equal to 5 mrad from ,

f gamnia radiation, and less than or equal to 10 mrad from beta radiation; '

and, f

(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 leGne-131, Iodine-133, Tritium, and radionuclides in particulate form with .

half-lives greater than 8 days released from the plant in gaseous eftluent

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.1 and 3.4.a.2 as a result of burning contaminated ol (2) The dose rate at or beyond the situ coundary due to radioactive materials released from the plant in gaseous efiluents 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).

Page 1 of 17 1

NEW YORK POWER AUTHORITY

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

.. SEMI ANNUAL REPORT JANUARY 1997 - JUNE 1997 SUPPLEMENTAL INFORM ATION (Continued)

c. Liquid Effluents:

l (1) The concentration of radioactive materials released to the unrestricte6 areas

! shall not exceed the values specified in 10 CFR 20, Appendix B, Tabl II,

f. 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 1- - from the plant in liquid efnuents to unrestricted areas shall be limited as follows:

l (a) During any caler.dar 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. lodines: (None specified)
c. Particulates, half-lives >8 days: -(None specified) d.. Liquid effluents: Ouarter 1 Ouarter 2' (1) Fission and activation NONE NONE products (mixture MPC)

(pCi/ml)

(2) Tritium (pCi/ml) 3.00E 3.00E-03 (3) Dissolved and entrained gases (pCi/ml) 2.00E-04 2.00E-04 Page 2 of 17

NEW YORK POWER AUTIIORITY

- JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFI.UENT AND WASTE DISPOSAL

-SEMI-ANNUAL REPORT J ANUARY 1997 - JUNE 1997 SUPPLEMENTAL INFORMATION (Continued)

3. Averane Enercy (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 chamoal cartridge and particulate filter on each release path,
c. Particulates: Gamma spectral analysis of each particulate filter and charcoal l

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 particelate filter for each release path for gloss alpha,

d. Liquid Effluents: Gamma spectral analysis of each batch discharged, except composite analysis for Strontium-89,- Strontium-90, Iron-55, Tritium, and Alpha, 1
c. Solid Waste: Gamma spectral analysis of a representative sample of each waste shipment. ' Scaling factors established from off-site ccmposite 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 process is composed of determinate and undeterminate errors.

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

calculations Page 3 of 17 i

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4 NEW YORK POWER AUTHORITY

-,- JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT- AND WASTE DISPOSAL

- - - - SEMI ANNUAL -REPORT JANUARY 1997 - JUNE 1997 SUPPLEMENTAL INFORMATION (Continued)

5. Batch Releases
a. Liquid: Ouarter 1 Ouarter 2 NONE NONE

~(1) Number of batch releases:

(2) Total, time period for batch NONE NONE release: (min)

! NONE h (3) Maximum time period for NONE

-batch release: (min) .

(4) Average time period for NONE NONE-batch release: (min)

(5) Minimum time period for NONE NONE f batch release: (min) b Gaseous: NONE NONE 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 Page 4 of 17

NEW YORK POWER AUTHORITY

.- JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

. .. SEMI ANNUAL REPORT JANUARY 1997 -JUNE 1997 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES EST TOTAL UNIT OllARTER 1 - OUARTER 2 ERROR %

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 2.54E+01 3.77E+01 so.50E+01
2. Average release rate for period pCi/sec 3.27E+00 4.79E+00
3. Tech. Spec. Limit  %

H. IODINE 131 Total Iodine-131 Ci 8.87E-05 5,47E-05 s2.50E+01 >

i 1.

2. Average release rate for period pCi/sec 1.14E-05 6.96E-06
3. Tech. Spec. Limit  %

i C. PARTICULATES

1. Particulates with half-lives

> 8 days Ci 4.09E-05 1.93E-04 s3.60E+01

2. Average release rate for period - pCi/sec 5.26E-06 2.45E-05
3. Tech. Spec. Limit _  %
4. Gross alpha radioactivity Cl 1.23E-06 2.29E-07 s2.50E+01 D. TRITIUM
1. Total Release Ci 2.55E+01 3.'8E+01 s2.50E+01
2. Average release rate for period pCi/sec 3.28E+00 4.13E+00
3. Tech. Spec. Limit  %
  • E. PEkCENTOF TECHNICAL SPECIFICATION LIMITS FISSION AND ACTIVATION GASES L Quarterly gamma air dose limit  % 3.47E-02 3.12E-02
2. Quarterly beta air dose limit  % 8.67E-03 6.12E-03
3. Yearly gamma air dose limit  % 1.74E-02 1.56E-02
4. Yearly beta air dose limit  % 4.33E-03 3.06E-03
5. Whole body dose rate limit  % 3.02E-03 3.02E-03
6. - Skin dose - rate limit  % 8.14E-03 6.36E-04 HALOGENS, TRITIUM AND PARTICULATES WITII IIALF-LIVES >8 DAYS l 7, Quarterly dose limit (organ)  % 2.19E-02 2.19E-02
8. Yearly dose limit (organ)  % 1.09E-02 1.09E-02
9. Organ dose rate limit  % 6.34E-05 6.96E-05 Page 5 of 17

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NEW YORK POWER- AUTilORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

. . .. SEMI-ANNUAL REPORT JANUARY 1997 - JUNE 1997 TABLE IB GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE UNIT OUARTER1 OUARTER 2 NUCLIDES RELEASED

1. fjssion Gases Argon-41 Cl 1.06E+00 1.39E+00 Krypton 85m Ci 7.51E-02 2.28E+00 l

Krypton 87 - Ci --------- 2.05E+00

' Krypton 88 Ci -------- 5.38E+00 Xenon 133 Ci 1.12E-01 3.05E-01 Cl 1.07E+00 1.21E+01 Xenon-135 Xenon-135m Ci 5.53E-01 1.96E-02 Xenon-137 Ci 8.56E-02 --------

Ci 1.23E-01 7.27E-02 Xenon-138 TOTAL Ci 3.08E+00 2.36E+01

-2. fodines lodine-131 Ci 7.01E-05 4.77E-05

- lodine-133 Ci 1.23E-04 2.56E-04 Ci -------- 1.32E-04 lodine-135 Ci 1.93E-04 4.36E-04 TOTAL

3. Particulates Manganese-54 Ci 1.40E-06 6.50E-07 ,'

Iron-55 Ci -------- 6.32E --------

Cobalt 60 Ci 2.12E-07 Strontium-89 Ci 5.80E-07 2.10E-06

- Barium / Lanthanum-140 Ci 1.69E-06 2.20E-07

' TOTAL Ci 3.88E-06. 2.98E-06

4. Tritium -

Ilydrogen-3 Cl 1.61E+00 1.99E+00 Note: Here 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 1997 - JUNE 1997 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT OUARTER1 OUARTER 2

1. Fission Gases Xenon-135 Ci 2.13E+00 1.20E+00

, Xenon-135m Ci 3.84E+00 2.67E+00-I Xenon-138 Cl 1.63E+01 1.02E+01 TOTAL Ci 2.23E+01 1.41E+01

2. lodines lodine-131 Cl 1.86E-05 6.97E-06 lodine-133 Ci 1.02E-04 9.13E-05 TOTAL Ci 1.21E-04 9.83E-05
3. Particulates Chromium-51 Ci -------- 7.65E-05 Manganese-54 Ci 2.97E-06 3.50E-05 Imn-59 Ci -------- 1.44E-05 Cobalt-58 Ci -------- 7.81E-06 Cobalt-60 Ci 3.21E-06 1.90E-05 Zinc-65 Ci -------- 1.73E-05 Strodtium-89 Ci 2.47E-05 1.83E-05 Antimony-124 Ci -------- 1.42E-06 Cesium-137 Ci 2.22E-06 5.77E-07 Barium / Lanthanum-140 Ci 3.S6E-06 --------

TOTAL Ci 3.70E-05 1.90E-04

4. Tritium Hydrogend Ci 2.39E+01 3.08E+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 1997 - JUNE 1997 TABLE 2A LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES EST TOTAL UNIT QUARTER 1 OUARTER 2 ERROR % -

A. FISSION AND ACTIVATION PRODUCTS 1, Total Release (not including tritium. gases and alpha) Ci NONE NONE s2.50E+01 ,

2. Average diluted concentra-tion during period pCi/mi NONE NONE 3 Applicable limit -  % --------

B. TRITIUM

'l. Total Release Ci .NONE NONE s2.50E+01 l

j' 2. Average diluted concentra-tion during period pCi/ml NONE NONE

3. Applicable limit  % --------

~ C. DISSOLVED ANDENTRAINEDGASES

1. Total Release Ci NONE NONE s2.50E+01 2: Average diluted concentra-tion during period pCi/mi NONE NONE

-3. Applicable Limit  % --------

D. GROSS ALPHA RADIOACTIVTlY

1. Total Release Ci NONE NONE s4.20E+01 E. VOLUMEOF WASTE RELEASED liters NONE NONE

'(PRIOR TO DILUTION)

F. VOLUMEOF DILUTION WATER USED DURING PERIOD liters NONE NONE G. PERCENTOF TECHNICAL SPECIFICATION LIMITS

1. Quarterly Whol Body Dose  %
2. Quarterly Organ Dose-  % --------
3. Annual Whole Body Dose  % --------
4. Annual Organ Dose  % --------

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NEW YORK POWER AUTI1ORITY L JAMEm A. - FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

.. .. SEMI-ANNUAL REPORT JANUARY 1997 - JUNE 1997 TAHLE2B LIQUID EFFLUENTS HATCII MODE NUCLIDES REl,EASfil UNIT OUARTERI OllARTER 2

1. Fission and Activation Produch None 1

i

2. Tritium None
3. Dissolved and Entrained Gases -

None Note: There were no continuous mode discharges during this repon period.

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

.. SEMI-ANNUAL REPORT JANUARY 1997 - JUNE 1997 TABLE 3A SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-month Period Est Total Unit Class A Class B Class C Error %

1. Tyne of Waste o a.- Spent resins, filter sludges, m 3

5.05E+01 4.84E+00 0.00E+00 1.00E+01 evaporator bottoms, etc. Ci- 9.48E+01 4.02E+01 0.00E+00 2.50E+01

b. Dry compressible waste, m 3

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.ClE+00 0.00E+00 --

d. Other: Dry Compressible Waste, m 3

1.13E+02 0. 0( E+ 0 0 0.00E+00 1.00E+01 contaminated equip., cct for Ci 2.98E-01 0.00E+00 0.00E+00 2.50E+01 volume reduction i '

2. Estimate of Maior Nuclide Comnosition (by troe of waste) a.- Spent resins, filter sludges, evaporator bottoms, etc.

Isotone Percent Curies . Isotone Percent Curies Iron-55 4.51E+01 5.37E+01 E Cesium-137 4.13E+00 4.92E+00 M Cobalt-60. 3.00E+01 3.58E+01 M Niekel-63 1.63E+00 1.94E+00 E

-Zinc-65 9.89E+00 1.18E+01 M Cobalt-58 8.85E-01 1.05E+00 M Manganese-54 7.17E+00 8.54E+00 M Ca. ban-14 5.57E-01 6.62E-01 M

b. Dry compressible waste, contaminated equipment, etc.

NONE

c. Irradiated components, control rods, etc.

NONE Page 10 of 17 V

- NEW YORK POWER AUTIIORITY ~

JAMES - A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT - AND WASTE DISPOSAL SEMI-ANNUAL REPORT J ANUARY 1997 - JUNE - 1997

_ TABLE 3A (continued)

SOLID WASTE AND IRRADIATED FUCL SillPMENTS

d. Other: ' Dry Compressible Waste, contaminated equip., ect. for volume reduction.

Curles Lsotone P_ercent Curies Isotone Percent Nickel 63 1.33E+00 3.07E-03 E Iron 55 5.98E+01 1.78E-01 E Cobalt-60 2.18E+01 6.51E-02 E Cesium-137 8.51E-01 2.54E-03 E l

Manganem-54 8.68E+00 2.59E-02' E Carbon-14 6.00E-01 1.79E-03 E l Zine-65 7.02E+00 2.09E-02 E Cerium-144 8.34E-02 2.49E-04 E l

l M - MEASURED)

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

j

3. Solid Waste Disposition No. of Shinments Mode of Transportation Destination 10 Truck Chem-Nuclear Systems, Inc.

Barnwell, SC 2 Truck

  • Scientific Ecology Group Oak Ridge, TN t-
  • Volume Reduction Facility B. IRRADIATED FUEL SHIPMENTS (Disposition)-

Mode of Transnortation Destination Eo. of Shioments None N/A N/A i

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NEW YORK POWER - AUTIlORITY

-, JAMES A. FITZPATRICK NUCLEAR -POWER - PLANT EFFLUENT' AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1997 - JUNE 1997 TABLE 3B -

SOLID WASTE AND IRRADIATED FUEL SillPMENTS Ac NRC CLASS A SOURCE OF PROCESSING CONTAINER TYPE OF- NUMBER OF WASTE EMPLOYED VOLUME CONTAINER CONTAINERS Spent Resins, Filter Dewatering 205.8 ft) HIC 7 Studges, Evaporator Bottoms, etc.

Spent Resins, Filter Dewatering. 170.8 ft' HIC 3 Studges, Evaporator Bottoms, etc.

Non-Compacted 1(M0 ft' STC 4 Dry Compressible Waste (DAW),

Contaminated Equipment, etc.

Solidification Acent: - None IllC - High Integrity Container STC - Strong Tight Container 1

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NEW- YORK POWER AUTHORITY

,- JAMES A. FITZPATRICK NUCLEAR POWER PLANT

< EFFLUENT AND WASTE DISPOSAL

. .. SEMI-ANNUAL REPORT JANUARY 1997 JUNE 1997 ATTACHMENT NO.1 CIIANGES TO TIIE OFFSITE DOSE CALCULATION MANUAL (ODCM)

'In accordance with Section 7.3.C.3 of 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.

l-There were no changes to the Offsite Dose Calculation Manual (ODCM) this report period.

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NEW YORK- POWER AUTilORITY

- JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL

- . .. SEMI ANNUAL REPORT JANUARY 1997 - JUNE 1997 ATTACIIMENT NO. 2

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM In accordance with Section 7.3.C.3 of 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 meluded in the Semi-Annual Radioactive Effluent Release Report.

I Revision 4 to the PCP was approved by the Plant Operating Review Committee on March 4,1997 at Meeting No.97-014 and became effective on March 6,1997. This revision does not reduce the overall conformance of the solidified waste product to existing criteria for  !

solid wastes. Listed below is a brie.f summary of the changes incorporated in this revision.

1) Process Control Program Procedure
  • Procedure was upgraded to coraply with the requirements of the JAF Procedure Writing Manual AP-02.01 Rev. 6.
  • Deleted various developmental references, CNSI and JAF procedures that were not applicable to this process.
  • Memo JLIC-96-187 Lice _nsing to Quality Assurance / Quality Control clarified that editorial revisions to the PCP need not be reported in the Semi-Annual Radioactive Release Report.
  • Program responsibility assigned to Operations Manager per instructions from General Manager - Operations.
  • Designate precoat and bead resin dewatering procedures and RDS-1000 operation procedure as implementing procedures.

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NEW YORK POWER AUTIIORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT- AND WASTE DISPOSAL SEMI ANNUAL REPORT JANUARY 1997 - JUNE 1997 ATI'ACilMENT NO 3

SUMMARY

OF CilANGES TO Tile ENVIRONMENTALMONITORING 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 environmenhl monitoring identified by the land use census shall be included in the Semi-Annual Raduactive Effluent Release Report.

CJJANGES IN ENVIRONMENTAL MONITORING LOCATIONS l

During the report period, no changes in the Environmental Monitoring Locations sampled to implement the requirements of Technical Specifications were made.

Sample location selections are based on the annual land use census.

NEW LOCATIONS FOR DOSE CALCUI.ATIONS

- 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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O NEW YORK POWER AUTilORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT JANUARY 1997 JUNE 1997 NITACllMENT NO 4 DEVIATIONS FROM Tile REQUIRED ENVIRONMENTAL SAMPLING SCllEDULE In accordance with Section 7.3.C.7 of Amendment 93 to the James A. FitzPatrick Nuclear Power P; ant Technical Specifications, the cause for unavailability of any environmental samples required during the report period shall be included in the Semi Annual Radioactive Efiluent Release Report.

EXCEPTIONS TO TiiE ENVIRONMENTAL S AMPLING PROGRAM

1. The air samptng pumps at the R-1 and R 2 off-site Environmental Sampling Stations were inoperable for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The loss of power at the Emironmental Air Sampling Station was the result of a local power outage. The air sample pumps were out of service for a five hour period between 03/11/97 and 03/18/97. No corrective action was implemented.

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NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT JANUARY 1997 - JUNE 1997

- ATTACilMENT NO. 5 SEMI-ANNUAL

SUMMARY

OF llOURLY METEOROLOGICAL DATA $

Th: James A. FitzPatrick Nuclear Power Plant Radiological Environmental Technical Specificatior 7.3.c.2 states in part. "The Radioactive Efnuent Release Report to be submitted within 60 days after January I of each year may include an annual summary.of meteorological data collected over the previous year, if the meteorological data is not included, the licensee shall retain it on file and provide it to the U.S. Nuclear Regulatory Commission upon request." In accordance with the aforementioned technical specification, meteorological data is not included in this report. it is retained on Ole and is available upon request.

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