ML20034F380

Annual Repts to NRC, 1992

ML20034F380
Person / Time
Site:	Sequoyah
Issue date:	12/31/1992
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20034F377	List: ML20034F380
References
NUDOCS 9303030079
Download: ML20034F380 (8)

Text

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 l

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i ANNUAL REPORTS TO THE NUCLEAR REGULATORY COMMISSION JM" JAR'l 1 - DECEMBER 31, 1992 DOCKET NUMBER 50-327 AND 50-328 LICENSE NUMBER DP?.-77 AND DPR-79 e

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SEQUOYAH NUCLEAR PLANT ANNUAL REPORTS I

1992 l

1 TABLE OF COE[Q[TS

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Page i

Preface.

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Occupational Exposure Data

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i Diesel Generator Reliability Data.

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1 SEQUOYAH NUCLEAR PLANT (SQN)

ANNUAL REPORTS j

1992 The following are descriptions of the items contained in this report.

Occupational _ Exposure Data Enclosed is

r. 2 exposure data for personnel at SQN that received greater than 100 millirem between January 1 and December 31, 1992. Exposure data for special maintenance is based on the following activities:

Modifications of Hangers, Supports and Clamps Modification of Thermal Growth Slip Joints Modification of Fuel Handling Equipment Repair of the Unit 1 Steam Generator Feedwater Nozzles Installation of a New 8-Inch Check Valve in the Unit 2 Residual Heat Removal System Relocation of the Unit 2 Auxiliary Feedwater Transmitter Modification of the Unit 2 Transfer Tube Upgrade of the Unit 2 Reactor Vessel Level Indication System Repair of the Unit 2 Steam Generator Feedwater Nozzles Shot Peening of the Unit 2 Steam Generators Reacts.r Coolant System _ Specific Activity Analysis (Specific Iodine Isotopic Activity Concentration and/or DEI-131 Determination)

During 1992 there were no specific activity results of Unit 1 or Unit 2 reactor coolant systems exceeding the limits of Technical Specification (US) 3.4.8.a (1.0 pCi/gm) during either power operation or reactor shutdown and/or start-up.

Diesel Generator Reliability Data The reliability data for the SQN 6900-volt emergency diesel generators is enclosed in accordance with TS 6.9.2.2.

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I REXPR219 TENNESSEE VALLEY AUTHOR I TY PAGE:

5 RUN DATE; O2-10-93 SQN RADIATION EXPOSURE SYSTEM

.t RUN TIME: 09:32:35

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NUMBER OF PERSONNEL AND MAN-REM BY WOhK JOB FUNCTION TOTAL NUMPER OF INDIVIDUALS

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NUMDER OF PERSONNEL () 100 M-REM)

TOTAL MAN-REM I

MO= REACTOR OPS SURVEILLANCE

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GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRAC1 TOTAL

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EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTHERS M-REMS

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MAINTENANCE PERSONNEL 102 4

146 252 1.395 0.019 1.626 3.040 T

OPERATING PERSONNE-35 5

i 41 6.119 0.779 0.160 7.058

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HEALTH PHYSICS PERSONNEL 38 1

86 125 4.330 0.275 0.161 12.766 SUPERVISORY PERSONNEL 34 i

7 42 2.063 0.218 0.290 3.371 T.

ENGINEERING PERSONNEL 32 17 14 63 1.689 1.203 0.583 3.475

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It0 241 28 254 523 16.396 2.494 10.820 29.710 L

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MO* ROUTINE MAINTENANCE

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GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTHERS M-REMS

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MAINTENANCE PERSONNEL 142 9

416 567 31.773 1.440 89.695 122.916 OPERATING PERSONNEL 32 5

i 38 1.570 0.117 0.032 1.719 f"

HEALTH PHYSICS PERSONNEL 54 i

129 184 5.928 0.040 13.911 19.879

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SUPERVISORY PERSONNEL 33 2

9 44 3.932 0.i64 0.329 4.425 ENGINEERING PERSONNEL 34 22 76 132 4.115 0.929 12.121 17.165

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2.698 116.088 166.104 MO 295 39 631 965 47.310 L

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MO=IN-SERVICE INSPECTION 1

GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL

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EMPLOYEEG EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTHERS M-REMS MAINTENANCE PERSCNNEL 18 0

175 193 1.120 0.000 16.855 17.975

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7 0.438 0.687 0.004 1.129 HEALTH PHYSICS PERSONNEL 25 0

81 106 2.632 0.000 17.298 19.930

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17 2.266 0.159 2.652 5.077 I

ENGINEERING PERSONNEL 16 22 80 126 5.404 6.077 30.235 41.716 5

MO 72 24 555 449 11.860 6.923 67.044 85.82i i

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MAINTENANCN PERSONNEL 53 3

293 349 7.700 0.330 57.695 65.725 T.

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REXPR219 TENMESSEE VALLEY AUTHORITY PAGE:

O RUN DATE: 02-10-93 SGN RADIATION EXPOSURE SYSTEN

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RUN TIME 2 09:32:35 NUMBER OF FERSONNEL AND MAN-REM BY WORK JOB FUNCTION TOTAL NUNDER OF INDIVIDUALS

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GROUP STATION UTILITY CONTRACT TOTAL T

MAINTENANCE PERSONNEL 162 9

385 556

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OPERATING PERSONNEL 36 6

3 45 HEALTH FHYSICS PERSONNEL 54 i

119 176 i

SUPERVISORY PERSONNEL 37 2

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ENGINEERING PERSONNEL 43 27 136 206 T

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SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 DIESEL GENERATOR (D/G) RELIABILITY DATA REPORT FOR 1992 This report is submitted to comply with Technical Specification (TS) 6.9.2.2 for an annual data report for D/G reliability. The 6.9-kilovolt (kV) D/Gs at SQN serve as the onsite Class IE power source.

Surveillance requirements of the TSs that demonstrate operability of the D/Gs are accomplished by the routine performance of Surveillance Instructions (SI) 1-SI-0PS-082-007.A, " Electrical Power System - Diesel Generator 1A-A"; 2-SI-0PS-082-007.A. " Electrical Power System - Diesel Generator 2A-A"; 1-SI-0PS-082-007.B, " Electrical Power System - Diesel Generator IB-B"; 2-SI-0PS-082-007.B, " Electrical Power System - Diesel Generator 2B-B"; 0-SI-OPS-082-007.0, " Diesel Generator Operability Verification"; 1-SI-OPS-082-026.A, " Loss of Offsite Power With Safety Injection - D/G 1A-A Containment Isolation Test"; 1-SI-0PS-082-026.B.

" Loss of Offsite Power With Safety Injection - D/G 1B-B Containment Isolation Test"; 2-SI-0PS-082-026.A, " Loss of Offsite Power With Safety Injection D/G - 2A-A Containment Isolation Test"; 2-SI-OPS-082-026.B.

" Loss of Offsite Power With Safety Injection - D/G 2B-B Test"; and the System Operating Instruction 82 series for routine operation of the D/Gs.

The information listed below is a tabulation of D/G testing data taken from 0-SI-0PS-082-007.M " Diesel Generator Surveillance Frequency." The 3

data was taken from testing performed during the period January 1 through i

December 31, 1992.

" Valid Test" and " Invalid Test" are defined in accordance with the criteria established in Regulatory Guide 1.108, Revision 1, August 1977.

Diesel Generator Valid Test Invalid Test Egilures 1A-A 18 19 0

IB-B 14 13 0

2A-A 17 17 1*

2B-B 18 25 1**

• Failure due to a short on the voltage regulator terminal block.

• • Failure due to kilowatt load swings caused by noise interference on cables that provide input to the governor controller.

The above data indicates an average of 35.25 starts per D/G with two failures. Two failures out of 141 valid and invalid tests support a reasor.able confidence level that the D/Gs will perform when required.

SQN continues to recognize the importance of reducing the number of D/G starts as indicated by the trend below.

1988: approximately 170 starts per D/G per year 1989: approximately 55 starts per D/G per year 1990: approximately 36 starts.per D/G per year 1991: approximately 36 starts per D/G per year.

1992: approximately 35 starts per D/G per year Continued efforts will keep D/G starts as low as possible and thereby enhance engine life and D/G reliability.

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