AEP-NRC-4691-03, Units I and 2, Errata to Annual Radioactive Effluent Release Report

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Units I and 2, Errata to Annual Radioactive Effluent Release Report
ML041460273
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/17/2004
From: Zwolinski J
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-4691-03
Download: ML041460273 (5)
v • d • e


Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1373 INDIANA MICHIGAN POWER May 17, 2004 AEP:NRC:4691-03 Docket Nos: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units I and 2 ERRATA TO ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT In accordance with Technical Specification (TS) 6.9.1.7, Indiana Michigan Power Company submitted the Annual Radioactive Effluent Release Report for Donald C. Cook Nuclear Plant (CNP) on March 24, 2004. Subsequently, it was discovered that the last three lines of text were inadvertently omitted from Page 1 of the subject report.

Please replace the page currently in the report with the corrected Page 1 attached to this letter. Page 2 is also being provided on the back of Page 1 for filing convenience.

There are no new commitments in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Supervisor of Nuclear Licensing, at (269) 697-5020.

Sincerely, A. Zwolinski Director of Design Engineering and Regulatory Affairs DB/rdw

Attachment:

Annual Radioactive Effluent Release Report - Page 1 and Page 2

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U.S. Nuclear Regulatory Commission AEP:NRC:4691-03 Page 2 c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachment J. T. King, MPSC, w/o attachment J. G. Lamb MDEQ - WHMD/HWRPS, w/o attachment D. Minnaar, MDEQ NRC Resident Inspector

ATTACHMENT TO AEP:NRC:4691-03 ERRATA TO ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

I. INTRODUCTION This report discusses the radioactive discharges from Unit 1 and Unit 2 of the Donald C. Cook Nuclear Plant during 2003. This is in accordance with the requirements of Donald C. Cook Nuclear Plant Technical 'Specification 6.9.1.7.

The table below summarizes the pertinent statistics concerning the Plant's operation during the period from January 1 to December 31, 2003. The data in this table and the descriptive information on

.plant operation are based upon the respective Unit's Monthly Operating Reports, Performance Indicators and Control Room Logs for 2003.

Parameter Unit 1 Unit 2 Gross Electrical Energy Generation (MWH) 6,799,373 . 7,340,330 Unit Service Factor (e) 74.1 75.5 Unit Capacity Factor - MDC Net (%) 75.0 76.6 Unit 1 entered the reporting period in Mode 1 at 100 percent (%)

Rated Thermal Power (RTP). Small power adjustments were made to facilitate main turbine valve testing throughout the year. On 1/15/03 the unit experienced a Turbine Trip/Rx trip from 100% RTP due to Main Transformer fire. The transformer was replaced, the unit attained criticality on 2/4/03 and returned to 100% RTP on 2/6/03. On 4/24/03 the unit was manually tripped due to lowering vacuum, degraded circulating water conditions caused by an alewife intrusion event. An Alert was declared at this time due to influx of material in the screen wash system resulting in decreased Essential Service Water flow to all Emergency Diesel Generators.

Alert was exited on 4/25/03. The unit attained criticality on 5/27/03 and returned to 100% RTP on 5/30/03. On 10/18/03 the unit was shutdown and the scheduled UlC19 refueling outage commenced.

The unit attained criticality on 11/25/03 and reached 100% RTP on 12/1/03. The unit exited the reporting period at 100% RTP.

.Unit 2 entered the reporting period in Mode 1 at 100% RTP. Small power adjustments were made to facilitate main turbine valve testing throughout the year. On 1/26/03 the unit was manually shutdown due to entering the Limiting Condition for Operation (LCO) associated with 2 CD Emergency Diesel Generator being inoperable. The LCO for 2 CD Emergency Diesel Generator was exited on 1/27/03. The unit attained criticality on 1/29/03 and achieved 100% RTP on 1/31/03. On 2/5/03 the unit experienced a reactor trip due to feedwater/steam flow mismatch associated with loss of 24 VDC power. The power supply was replaced and the unit attained 'criticality on 2/14/03 and reached 100% RTP on 2/16/03.

On 4/24/03 the unit was manually tripped due to lowering vacuum, degraded circulating water conditions caused by alewife intrusion event. An Alert was declared at this time due to influx of material in the screen wash system resulting in decreased Essential Service Water flow to all Emergency Diesel Generators.

Alert was exited on 4/25/03. The unit entered scheduled U2C14 refueling outage from forced outage on 5/5/03. The unit attained criticality on 6/19/03 and 100% RTP was achieved on 6/26/03. On 8/13/03 the unit was manually shutdown due to a steam leak found on feedwater check valve 2-FW-118-2. The unit attained criticality on 8/28/03 and 100% RTP was achieved on 8/30/03. On 12/14/03 power was reduced to Mode 2 to allow repair of feedwater regulating valve 2-FRV-240 positioner. The unit returned to 100%

RTP on 12/16/03. On 12/30/03 the reactor automatically tripped 1

from 100% power due to a low steam generator level coincident with feed flow less than steam flow, which occurred during maintenance activities. The unit exited the reporting period in Mode 3.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT ON MAN Since a number of release points are common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report. Appendices A1.1 through A2.4 of this report present the information in accordance with Section 6.9.1.7 of Appendix A to the Facility Operating Licenses, as specified in the Technical Specification, Regulatory Guide 1.21 and 10 CFR Part 50, Appendix I.

The "MIDAS System" is a computer code that calculates doses due to radionuclides that were released from the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within Offsite Dose Calculation Manual limits and Federal Limits.'

There were no abnormal liquid or gaseous releases.

Liquid Releases During 2003 there were 62 liquid batch releases. During the first quarter there were 11 liquid batch releases. During the second quarter there were 25. During the third quarter there were 20.

During the fourth quarter there were 26.

Estimated doses (in millirem) to maximally exposed individuals via the liquid release: pathways are given in Appendix 1.2 of this report.

Gaseous Releases During the first quarter of 2003 there were six batch releases from Waste Gas Decay Tanks (GDT) and 133 Containment Pressure Reliefs (CPR).. During the second quarter there were six batch releases from GDT, two from containment purge and 57 CPR. During the third quarter there were three batch releases from GDT, one from containment purge and 144 CPR. During the fourth quarter there were four batch releases from GDT, one from containment purge and 69 CPR. CPR continue to be listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) and 50-316/8917 N(DRSS). There were a total of 19 GDT, four unit purges and 403 CPR during 2003.

In calculating the dose consequences for continuous and batch gaseous releases during 2003, the meteorological data measured at the time of the release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathways are given in Appendix 1.2 of this report.

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