ML050680215
| ML050680215 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 02/28/2005 |
| From: | Lambert C Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-05-018 | |
| Download: ML050680215 (12) | |
Text
-w myu Committed toNOperated Kewaunee Nuclear Power Plant tOperated by Nuclear Management Company, LLC February 28, 2005 NRC-05-018 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Kewaunee NuclearPower Plant Docket 50-305 License No. DPR-43 2004 ANNUAL OPERATING REPORT Enclosed is the 2004 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 2004 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.
Craig e
Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosure (1) cc:
Administrator, Region ll, USNRC Resident Inspector, Kewaunee, USNRC INPO Records Center N490 Highway 42
- Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560
ENCLOSURE I 2004 KEWAUNEE NUCLEAR POWER PLANT ANNUAL OPERATING REPORT II 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 2004 STEAM GENERATOR EDDY CURRENT EXAMINATIONS......................................................
2-1 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 II.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 2004.
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2.0
SUMMARY
OF THE 2004 STEAM GENERATOR EDDY CURRENT EXAMINATIONS During the 2004 Kewaunee Nuclear Power Plant refueling outage, a steam generator eddy current examination was not performed per KNPP License Amendment 175, "Steam Generator Eddy Current Inspection Frequency Extension". The one-time Technical Specification change was approved by the NRC via letter to KNPP dated June 18, 2004.
Technical Specification (TS) 4.2.b.7.b.1 requires a tabulation of the number of tubes inspected and extent of inspection. No tubes were inspected during the 2004 KNPP refueling outage.
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, and wear or corrosion of a tube wall. No tubes were inspected; therefore no indications of degradation were reported during the 2004 KNPP refueling outage.
Technical Specification 4.2.b.7.b.3 requires the identification of tubes plugged.
No tubes were inspected; therefore no tubes were plugged during the 2004 KNPP refueling outage. There are currently zero tubes plugged in the KNPP steam generators.
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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 1/1/04 To 12/31/04 Personnel Deep Dose Exposure Report For Calendar Year 2004 Kewaunee Nuclear Power Plant Deep Dose Exposure Range None - Detected Less than.100 rem 0.100 rem to 0.249 rem 0.250 rem to 0.499 rem 0.500 rem to 0.749 rem 0.750 rem to 0.999 rem 1.000 rem to 1.999 rem Greater than 2.000 rem Total Monitored Individuals Number of Individuals in Range 670 306 132 93 26 5
4 0
1236 Total Site Deep Dose (NDE + DDE) =
91.202 rem 3 - 2
TABLE 3.2 U.S.N.R.C. REGULATORY GUIDE 1.16 REPORT KEWAUNEE NUCLEAR POWER PLANT FROM 1/1/04 TO 12131/04 Number of Personnel and Man-Rem by Work and Job Functions (2004)
Kewaunee Nuclear Power Plant Number of Persons >.100 Rem Total Man-Rem Work and Job Function Station Utility Contract Station Utility Contract Inservice Inspection Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Routine Maintenance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Reactor Operations & Surveillance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Refueling Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel 8
1 7
1 3
32 8
23 2
3 2
13 4
0 0
19 1
12 0
0 29 0.046 1
0.006 7
0.032 2
0.004 14 0.340 27 1.040 0
0.323 28 5.207 2
0.284 3
0.115 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.353 0.001 0.180 0.066 1.466 2.486 0.000 6.301 0.062 0.015 0.000 0.000 0.000 0.000 0.002 1.207 0.420 0.204 0.004 4.043 0
0 0
0 I
0.002 3.357 0.060 0.000 0.000 27 1.520 2
0.195 6
0.797 1
0.000 15 0.000 Special Maintenance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Waste Processing Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Sub Totals Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel 35 12 23 3
6 10 3
19 1
0 106 38 88 7
12 0
0 0
0 0
0 0
0 0
0 98 6.508 2
0.189 15 2.022 3
0.562 20 0.664 4
0.138 0
0.019 5
0.751 0
0.062 0
0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 24.437 0.116 0.836 0.280 3.467 0.015 0.000 0.066 0.000 0.000 35.498 0.537 7.587 0.412 8.993 0
185 0
5 0
61 0
8 0
53 9.254 4.089 8.869 0.912 1.119 Grand totals 251 0
312 24.243 0.000 53.027 Total Site Deep Dose (NDE + DDE) for Ind. with >.100 rem =
78.665 rem
- INDIVIDUALS MAY BE LISTED UNDER MORE THAN 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 (LB) Loss of Coolant Accident (LOCA) Analysis There are no changes in the LB LOCA analysis. Peak cladding temperature (PCT) results remain < 20840F for the 95th percentile PCT (Reference 1).
Small Break (SB) LOCA Analysis There are no changes in the SB LOCA analysis. PCT results remain at 10650F which is the calculated value of 1030'F increased by 350F to account for the SB LOCA evaluation model (NOTRUMP) bubble rise and drift flux model inconsistencies (Reference 1).
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).
References:
/
Ref. 1 Letter from Stephen Swigart (Westinghouse) to Kevin Davison (NMC) dated March 17, 2004, " 10 CFR 50.46 Annual Notification and Reporting for 2003" 4 -1
5.0 FAILURES OF TURBINE STOP AND CONTROL VALVES There were no failures of the turbine stop, reheat stop, control, or interceptor valves to close during 2004 testing.
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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 2004.
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