ML040650370
| ML040650370 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 02/27/2004 |
| From: | Coutu T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-04-00-024 | |
| Download: ML040650370 (13) | |
Text
Committed tof carEx Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-04-024 10 CFR 50.46 February 27, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 LICENSE No. DPR-43 2003 ANNUAL OPERATING REPORT Enclosed is the 2003 Kewaunee Nuclear Power Plant (KNPP) Annual Operating Report.
This report is being submitted in accordance with Section 6.9.a.2 of the KNPP Technical Specifications.
This submittal of the 2003 KNPP Annual Operating Report also satisfies the reporting requirements of 10 CFR 50.46(a)(3)(ii) (Emergency Core Cooling System evaluation model changes), and KNPP Technical Specification 4.2.b.7.b (steam generator inspection). Also, in accordance with the commitment made by KNPP upon NRC issuance of the turbine valve test frequency Technical Specification amendment, any turbine stop and control valve failures are described.
Thomas Coutu Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Senior Resident Inspector, Kewaunee, USNRC INPO Records Center N490 Highway 42
- Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560 0C)D>
ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 February 27, 2004 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC) 2003 Annual Operating Report 11 Pages Follow
TABLE OF CONTENTS INTRODUCTION ..................................................... i 1.0 CHALLENGES TO AND FAILURES OF PRESSURIZER SAFETY AND RELIEF VALVES ..................................................... 1-1 2.0
SUMMARY
OF THE STEAM GENERATOR EDDY CURRENT EXAMINATION ..................................................... 2-1 TABLE 2.1 ..................................................... 2-2 3.0 PERSONNEL EXPOSURE AND MONITORING REPORT ....................... 3-1 TABLE 3.1 ..................................................... 3-2 TABLE 3.2 ..................................................... 3-3 4.0 CHANGES IN THE EMERGENCY CORE COOLING SYSTEM MODEL ..................................................... 4-1 5.0 FAILURES OF TURBINE STOP AND CONTROL VALVES ...................... 5-1 6.0 MAXIMUM COOLANT ACTIVITY ..................................................... 6-1
INTRODUCTION This annual operating report is being submitted to fulfill several reporting requirements contained either in the Kewaunee Nuclear Power Plant (KNPP)
Technical Specifications (TS) or in other commitments made by KNPP to the Nuclear Regulatory Commission (NRC).
In response to NUREG-0737, Item II.K.3.3, and in accordance with KNPP Technical Specification (TS) 6.9.a.2.C, Section 1.0 reports challenges to and failures of pressurizer safety and relief valves, if applicable.
Section 2.0 provides a summary of the steam generator eddy current examination in accordance with KNPP TS 4.2.b.7.b.
Personnel exposure and monitoring data is provided in Section 3.0 per Regulatory Guide 1.16, Section C.1.b.(3), and KNPP TS 6.9.a.2.B.
The provisions of 10 CFR 50.46 require the reporting of corrections or changes to the Emergency Core Cooling System (ECCS) evaluation models that are approved for use in performing the loss-of-coolant accident (LOCA) safety analysis. This information, if applicable, is provided in Section 4.0.
Section 5.0 reports failures of turbine stop and control valves, if applicable, in accordance with a commitment made to the NRC upon approval of KNPP TS Amendment 84.
Section 6.0, in accordance with KNPP TS 6.9.a.2.D, contains documentation of the results of specific analysis in which the reactor coolant exceeded the limits of KNPP TS 3.1.c.1.A, if applicable.
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1.0 CHALLENGES TO AND FAILURES OF PRESSURIZER SAFETY AND RELIEF VALVES In response to NUREG-0737, item ll.K.3.3, and in accordance with KNPP Technical Specification 6.9.a.2.C, NMC is committed to reporting challenges to and failures of pressurizer safety and pressurizer power-operated relief valves.
There were no challenges to, or failures of, pressurizer safety or pressurizer power-operated relief valves during 2003.
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2.0
SUMMARY
OF THE 2003 STEAM GENERATOR EDDY CURRENT EXAMINATIONS During the 2003 Kewaunee Nuclear Power Plant refueling outage, the following steam generator eddy current examinations were performed:
- 1) A bobbin coil examination of 100% of the tubes through their entire length.
- 2) A rotating plus point examination of 20% of the row 1 U-bends.
- 3) A rotating plus point examination of 20% of the hot leg tube expansion transitions, from 2 inches below to 2 inches above the secondary face of the tubesheet.
- 4) Augmented rotating plus point examinations at various locations to resolve indeterminate bobbin coil signals.
As required by Technical Specification (TS) 4.2.b.7.b.1, Table 2.1 provides the number of tubes inspected and extent of inspection.
Technical Specification 4.2.b.7.b.2 requires a tabulation of the location of each tube wall degradation and its percent of wall penetration. Degradation is defined in TS 4.2.b as service-induced cracking, wastage, wear or corrosion of a tube wall. No indications of degradation were reported during the 2003 SG eddy current examination.
Technical Specification 4.2.b.7.b.3 requires the identification of tubes plugged.
No tubes were plugged during the 2003 steam generator eddy current examination.
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TABLE 2.1 2003 STEAM GENERATOR EDDY CURRENT EXAMINATIONS NUMBER AND EXTENT OF TUBES TESTED SG A SG B EXTENT OF INSPECTION NUMBER TESTED NUMBER TESTED TEH to TEC 3592 3592 U-bend (07H to 07C) 20 20 TSH - 2" to TSH + 2" 721 769 06H - 1" to 07H + 1" 2 0 02C - 1" to 03C + 1" 0 1 06C - 1" to 07C + 1" 0 1 TEC to TSC +2" 0 1 TSC -2" to FBC + 1" 5 0 TEH to TSH + 2" 0 1 TSH -2"to FBH + 1" 6 12 Table 2.1 Nomenclature TEH: Tube end hot leg side TEC: Tube end cold leg side TSH: Top of tubesheet hot leg side TSC: Top of tubesheet cold leg side FBH: Hot leg flow distribution baffle plate FBC: Cold leg flow distribution baffle plate 06H: Sixth hot leg tube support plate 07H: Seventh hot leg tube support plate 07C: Seventh cold leg tube support plate 06C: Sixth cold leg tube support plate 03C: Third cold leg tube support plate 02C: Second cold leg tube support plate 2 -2
3.0 PERSONNEL EXPOSURE AND MONITORING REPORT Table 3.1 presents a tabulation of the total number of individuals for whom monitoring was provided, along with information on total station dose for the year.
Table 3.2 presents a tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr (1.0 mSv/yr) and their associated person-rem exposure according to work and job functions. This table is provided per Regulatory Guide 1.16, Section C.1.b.(3), and Kewaunee Technical Specification 6.9.a.2.B.
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TABLE 3.1 TOTAL STATISTICS 1/1103 To 12/31/03 Deep Dose Exposure Number of Individuals Range in Range None - Detected 604 Less then .100 rem 217 0.100 rem to 0.249 rem 116 0.250 rem to 0.499 rem 75 0.500 rem to 0.749 rem 26 0.750 rem to 0.999 rem 4 1.000 rem to 1.999 rem 1 Greater then 2.000 rem 0 Total Monitored Individuals 1043 Total Site Deep Dose (NDE + DDE) = 73.108 re.m 3 -2
TABLE 3.2 U.S.N.R.C. REGULATORY GUIDE 1.16 REPORT KEWAUNEE NUCLEAR POWER PLANT FROM 1/1/03 TO 12/31/03 Number of Persons > .100 Rem Total Man-Rem Work and Job Functicr. Station Utility Contract Station Utility Contract inservice Inspection Maintenance Person. 10 0 46 0.140 0.000 9.153 Operating Personnel 1 0 0 0.030 0.000 0.000
-.ealth Physics Per. 10 0 15 0.244 0.000 1.363 Supervisory Person. 1 0 1 0.081 0.000 0.002 Engineering Person. 2 0 8 0.211 0.000 2.150 Routine Maintenance Maintenance Person. 30 0 30 0.315 0.000 3.492 Operating Personnel 6 0 0 0.279 0.000 0.000 Health Physics Per. 20 0 34 3.786 0.000 7.132 Supervisory Person. 1 1 1 0.212 0.024 0.008 Engineering Person. 0 1 0.001 0.000 0.086 Reactor Operations & Surv MaIn.tenance Person. 3. 0 2 0.028 0.000 0.002 Operating Personnel 10 0 0 2.052 0.000 0.000 Health Physics Per. 1 0 1 0.001 0.000 0.019 Supe-isor' Person. 0 0 0 0.000 0.000 0.000 Engineering Person. 1 0 0 0.022 0.000 0.000 Refueling Mzaintenance Person. 15 1 33 3.219 0.101 3.962 Operating Personnel 1 0 0 0.004 0.000 0.000 Health Physics Per. 8 0 13 1.920 0.000 0.196 Supervisory Person. 0 1 0 0.000 0.005 0.000 Engineering Person. 3 0 1 0.530 0.000 0.004 Snecial Maintenance Maintenance Person. 33 0 70 7.162 0.000 8.816 Operating Personnel 3. 0 0 0.054 0.000 0.000 Health Phyhvsics Per. 19 0 28 1.047 0.000 1.342 Supervisory Person. 1 i 1 0.011 0.099 0.110 Engineering Person. 6 0 11 0.506 0.000 1.727 rWaste Processing Mairtenance Person. 15 0 0 0.073 0.000 0.000 Operating Personnel 3 0 0 0.085 0.000 0.000 Health Physics Per. 17 0 4 1.325 0.000 0.045 Supervisory Person. 1 0 . 0 0.079 0.000 0.000 Engineering Person. 0 0 0 0.000 0.000 0.000 Sub Totals Maintenance Person. 106 1 181 10.937 0.i01 25.425 Operating Personnel 24 0 0 2.504 0.000 0.000 Health Physics Per. 75 0 95 8.323 0.000 10.097 Supervisory Person. 4 3 3 0.383 0.128 0.120 Engineering Person. 13 0 21 1.270 0.000 3.967 3rand Totals 222 4 300 23.417 0.229 39.609 Total Site Deep Dose (NDE + DDE) for Ind. with >.100 rem = 64.462 rem INDIVIDUALS MAY BE LISTED UNDER MORE THIN ONE WORK AND JOB FUNCTION 3- 3
4.0 CHANGES IN THE EMERGENCY CORE COOLING SYSTEM MODEL In accordance with the provisions of 10 CFR 50.46, this section provides corrections or changes to the emergency core cooling system (ECCS) models.
Large Break LOCA Analysis Large Break (LB) LOCA analysis was performed to support the transition to the Westinghouse 422 Vantage + fuel design (Reference 1) and the stretch power uprate (Reference 2). Approved best estimate upper plenum injection LB LOCA methods were used for the LB LOCA analysis.
Peak cladding temperature (PCT) results were < 1760 0F for the 50t percentile PCT and < 2084 OF for the 95th percentile PCT.
Small Break LOCA Analysis Small Break (SB) LOCA analysis was performed to support the fuel transition (Reference 1) and the stretch power uprate (Reference 2). Approved SB LOCA methods were used for the analysis. The peak cladding temperature was calculated to be 1030'F.
Based on Reference 3, KNPP PCT for SB LOCA was increased by 35 OF to account for the SB LOCA evaluation model (NOTRUMP) bubble rise and drift flux model inconsistencies.
The calculated LB LOCA and SB LOCA values for PCT, oxidation, and core-wide hydrogen generation are less than the limits specified in 10 CFR 50.46. Therefore the LB and SB LOCA analyses are acceptable and demonstrate that KNPP complies with the requirements of 10 CFR 50.46 (b)(1)-(4) (section 2.4.1 of Reference 1).
References:
Ref. 1. Letter from Mr. John Lamb (NRC) to Mr. Tom Coutu (NMC) "Issuance of Amendment (TAC No. MB5718)" dated April 4,2003.
Ref. 2. Nuclear Management Company, NRC Submittal via NMC Letter, "License Amendment Request (LAR) 195, Stretch Power Uprate for Kewaunee Nuclear Power Plant", submitted 5-22-03 and the LAR Supplements submitted 11-06-03,12-15-03,1-30-04, and 2-09-04.
Ref. 3. Letter from Stephen Swigart (Westinghouse) to Tom Coutu (NMC) dated November 12,2003, " 10CFR 50.46 Mid Year Notification and Reporting for 2003" 4 -1
5.0 FAILURES OF TURBINE STOP AND CONTROL VALVES There were no failures of the turbine stop and control valves to close during 2003.
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6.0 MAXIMUM COOLANT ACTIVITY KNPP TS 6.9.a.2.D requires the documentation of the results of specific activity analysis in which the reactor coolant exceeded the limits of TS 3.1.c.1.A during the past year.
The reactor coolant did not exceed the limits of TS 3.1.c.1.A during 2003.
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