ML20064C366

Annual Repts to NRC Jan- Dec 1993, Containing Summary of Occupational Exposure Data, RCS Specific Activity Analysis & DG Reliability Data.W/

ML20064C366
Person / Time
Site:	Sequoyah
Issue date:	12/31/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403090339
Download: ML20064C366 (11)

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A Ternme Vamy Au nny Post O!'o bom XM Soddy Dary. Tennessee 3DME)oO Rot;ert A Fenech Vu hnWmd Wpn/ah Nw ear Not February 25, 1994 U.S. Nuclear Regulatory Commission  ;

ATTN: Document Control Denk

.inshington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50 727 Tennessee Valley Authority ) 50-328 SEQUOYAll NUCLEAR PLANT (SQN) - 1993 ANNUAL REPORTS Enclosed are the 1993 Annual Reports for SQN. These reports contain a summary of the following items: occupational exposure data, reactor coolant system specific activity analysis, and diesel generator reliability data.

This report is being submitted to satisfy the requirements of Technical Specifications 6.9.1.4, 6.9.1.5, and 6.9.2.2.

Please direct questions concerning this submittal to Keith Weller at (615) 843-7527. )

Sincerely, J M

Robert A. Fenech Enclosure NI cc: See page 2 I\

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7403090339 931231 PDR ADDCK 05000327 R '

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U.S. Nuclear Regulatory Commission Page 2 February 25, 1994 cc (Enclosure):

Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 l

NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, G"orgia 30323-2711 l

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l TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 ANNUAL REPORTS TO THE NUCLEAR REGULATORY COMMISSION JANUARY 1 - DECEMBER 31, 1993 DOCKET NUMBERS 50-327 AND 50-328 LICENSE NUMBERS DPR-77 AND DPR-79 1

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e SEQUOYAll NUCLEAR PLANT l ANNUAL REPORTS  !

1993 l

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l IABLLOF_CONIFETS 1 Page Preface . . . . . ................ 1 Occupational Exposure Data . .. .... .. . .2 Diesel Generator Reliability Data . .. ... . . .6 i

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SEQUOYAH NUCLEAR PLANT (SQN)

ANNUAL REPORTS ,

1993 The following are descriptions of the items contained in this report. ,

Occupationallxposure_ Data Enclosed is the exposure data for personnel at SQN that received greater than 100 millirem between January 1 and December 31, 1993. Exposure data '

for special maintenance is based on the following activities:

Auxiliary Building Floor Drain Cleaning Foreign Material Retrieval From Unit 1 Refueling Water Storage Tank Modification of IIangers, Supports and Clamps Replacement of the Unit 1 Control Rod Drive Mechanism Cocier Colls Repair of the Unit 1 Ice Condenser Floor Replacement of the Unit 1 Reactor Coolant Pump Flange Gasket  ;

Gamma Scan Analysis ,

1 Inspection of the Unit 1 Nozzle Covers Replacement of the Unit 1 Excess Letdown Heat Exchanger Head Gasket

, Repair of the Unit 1 Containment Floor Coatings Upgrade of the Unit 1 Reactor Coolant Pump 011 Drain System '

Relocation of the Unit 2 Reactor Coolant Drain Tank Level Transmitter Removal of Two Unit 1 Steam Generator Tubes for Analysis Removal of a Unit i Incore Detector Tube Repair of a Unit 1 Reactor Pressure Vessel Stud Hole Recovery of a Unit 1 Toppled Fuel Assembly Inspection of the Unit 1 Reactor Cavity-Liner

• Modification of the Unit 2 Control Rod Drive Mechanism Duct Work ReactorlonlanLSy.s.terLSpe.ciLic_Act.ixity_ Analysis (Specific Iodine Isotopic Activity Concentration and/or DEI-131 Determination)

-i During 1993 there were no specific iodine activity results of Unit 1.or Unit 2 reactor coolant systems exceeding the limits of Technical Specification (TS) 3.4.8.a (1.0 pC1/gm) during either power operation or l reactor shutdown and/or start-up.

Di.c Ecl.M en erato r_Rel icitilliyJala 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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RE2PR219 TENN ESSEE YALLEY s' RUN DATE: 01-24-94 AUTHORITY .

SON RADIATION EIPOSGt.E SYSTEM RUM TIME 08:41:31 MUMBER OT PERSONNEL AND MAN-REM DY WORK JOB FUNCTION .

TOTAL NUMBER OF INDIVIDUALS NUMBER OF PEPSONNEL (> 100 M-REM) TOTAL MAN-REM i

MO* REACTOR OPS SURVEILLANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTPACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPIDYEES EMPLOYEES AND OTHERS M-REMS MAINTENANCE PERSONNEL 94 17 256 367 1.735 0.491 4.022 6.248 OPERATING PERSONNEL 43 2 5 50 1.046 0.357 0.126 7.529 EEALTH PHYSICS PERSONNEL 42 0 78 120 4.239 0.000 6.439 10.678 SUPERVISORY PERSONNEL 31 2 4 37 1.103 0.020 0.008 1.731 ENGINEERING PERSONNEL 34 19 50 103 2.029 0.760 1.066 3.855

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MO 244 40 3TI 677 16.752 1.628 11.661 30.041 k

MOeROUTIME MAINTENANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPI4YEES EMPI4YEES AND OTHERS PERSONS EMPI4YEES EMPLOYEES AND OTHERS M-REMS i

MAINTENANCE PERSONNEL 102 19 366 487 22.968 4.245 67.230 94.443 OPERATING PERSONNEL 29 1 5 35 1.040 0.033 0.318 1.391 HEALTil PHYSICS PERSONNEL 49 0 82 131 4.926 0.000 18.136 23.062 SUPERVISORY PERSONNEL 28 3 6 37 2.696 0.110 0.280 3.086 ENGINEERING PERSONNEL 37 17 48 102 3.234 0.499 2.654 6.387 MO 24T 40 507 792 34.864 4.887 88.618 128.369 MO=IN-SERVICE INSPECTION GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL

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

, MAINTENANCE PERSONNEL 16 1 128 145 0.315 0.016 12.936

' 13.267 OPERATING PERSONNEL 0 0 0 0 0.000 0.000 0.000 '

.0.000 HEALTH Pl!YSICS PERSONNEL 29 0 65 94 1.536 0.000 9.503 11.039 i SUPERVISORY PERSONNEL 10 3 8 21 3.050 0.692 0.895 4.637 ENGINEERING PERSONNEL 20 14 87 121 2.356 2.181 29.458 33.995 MO 75 18 288' 381 7.257 2.889 52.792 62.938 MO=SPECIAL MAINTENANCE GROUP STATION UTILITY CONTRACT TVTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OT'IERS PERSONS EMPLOYEES EMPI4YEES AND OTHERS M-REMS

[ MAINTENANCE PERSONNEL 72 8 304 384 8.167 0.150 48.441 56.758 i

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- L L REXPR219 TENNESSEE VALLEY AUTHORITT *

• RUM CATE: 01-24-94 SON RADIATION EXPOSURE SYSTEM

, RUN TIMEt 08:41:31 NUMBER OF PERSONNEL AND MAN-REM DY WORK JOB FUNCTION '

TOTAL NUMBER OF INDIVIDUALS

• NUMBER OF PERSONNEL (> 100 M-REM) TOTAL MAN-RIM 't OPERATING PERSONNEL 17 1 2 20 0.171 0.034 0.005 0.210 HEALTH PHYSICS PERSOUNEL 46 0 73 119 2.912 0.000 6.174 9.086 SUPERVISORY PERSONNEL 29 2 4 35 1.930 0.101 0.816 2.847 ENGINEERING PER$CNNEL 21 16 90 127 0.6C6 1.101 21.445 23.152 MO 18T 27 473 685 13.786 1. 3 8 ti 76.881 92.053 MO* WASTE PROCESING 4

GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTPERS M-REMS MAINYENANCE PERSONNEL 19 1 29 49 1.454 0.000 2.900 4.354 OPERATING PERSONNEL 2 0 2 4 0.563 0.000 0.866 1.429 MEALTH PHYSICS PERSONNEL 25 0 16 41 4.054 0.000 2.432 6.486 SUPERVISORY PERSONNEL 0 0 0 0 U.000 0.000 0.000 0.000 8

ENGINEERIFiG PERSONNEL 6 1 5 12 1.395 0.008 0.388 1.791 MO 52 2 52 106 7.466 0.008 6.586 14.060 MO-REFUEL CROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL

! EMPICYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPI4YEES AND OTHERS M-REMS i MAINTENANCE PERSONNEL 50 3 138 191 4.404 0.325 29.085 33.814 OPERATING PERSONNEL 20 0 0 20 .0.451 0.000 0.000 0.451 HEALTH PNYSICS PERSONNEL 33 0 54 87 3.116 0.000 - 4.331 7.447 SUPERVISORY PERSONNEL 17 0 4 21 1.870 0.000 0.317 2.187 ENGINEERING PERSONNEL 18 9 45 72 1.015 2.001 13.642 16.658 MO 138 12 241 391 sil _10.856, 2.326 47.375 60.557

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939 139 1954 3032 90.981 13.124 283.913 388.01B

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REXPR219 TENNES-SEE VALLEY AUTHORITY J .

j RUN DATE: 01-24-94 SCrf RADIATION EIPOSURE SYSTEM RUN TIMES 08:41:31 i

NUMBER CF PERSONNEL AND MAN-REM BY IWORK JOS FITNCTION TOTAL NUMBER OF INDIVIDUALS .

NUMBER OF PERSONNEL (> 100 M-REM) TOTAL MAN-REM i GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CCNTRACT M AL EMPICYEES EMPLOYEES AND OTHERS PERSONS EMPICYEES EMPLOYEES AND OTHERS M-REMS

• MAINTENANCE PERSONNEL 353 49 1221 1623 39.043 5.227 164.614 208.884 '

OPERATING PERSONNEL 111 4 14 '129 9.271 0.424 1.315 11.010 i HEALTH PHYSICS PERSONNEL 224 0 368 592 20.783 0.000 47.015 67.798 '

SUPERVISORY PERSONNEL 115 10 26 151 11.249 0.923 2.316 14.488 'I

, ENOINEERING PERSONNEL 136 76 325 537 10.635 6.550 68.653 85.838 t- ======== ======== ======== ======== --=== ======== ==,=====

j 939 139 1954 3032 90.981 13.124 283.913 388.018 .

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REXPR219 TENNESSEE VALLEY RUN DATES 01-24-94 AUTHORITY SCN RADIATION EXPOSURE SYSTEM RUN TIME: 08:41:31 .

NUMBER OF PERSONNEL AND MAN-REM BY WORK JOB IUNCTION '

TOTAL NUMBER CF INDIVIDUALS l CROUP STATION UTILITY CONTRACT TOTAL MAINTENANCE PERSCNNEL 100 21. 377 498 OPERATING PERSONNEL 45 2' 3 50 HEALTH PHYSICS PERSONNEL 52 0 90 142 i

SUPERVISORY PERSCNNEL 30 2 9 40 ENGINEERING PERSONNEL 34 16 146 196

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261 41 624 926 s

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SFTJUOYAll NUCIEAR PIWfr UtTITS 1 NJD 2 DIFI;EL CB'UtA70R (DG) RFLIABILI'IY DATA RENRr IOR 1993 1his report is autmitted to comply with Tecitnical Specification (TS; 6.9.2.2 for an annual data report for DG reliability. The 6.9 kilovolt (kV) DGs at Sg1 serve as the onsite Class 1E power source.

Surveillance rcquirenents of the TSs that demonstrate operability of the DGs are accompliched by the routine performance of Surveillance Instructions (SI) 1-SI-OPS-082-007. A, " Electrical Iwer System - Diesel Generator 1A-A";

1-SI-OPS-082-007.B, " Electrical Ibwer System - Diccel Cencrator 1B-B";

2-SI-OPS-082-007. A, " Electrical Power System - Diesel Generator 2A-A";

2-SI-OPS-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, "Insa of Of fnite Power with Safety Injection-DG 1A-A Containment Isolation Test";

2-SI-OPS-082-026.A, " loss of Offsite Power with Safety Injection-DG 2A-A Containment Isolation Test";

1-SI--OPS-082-026. B , " Loss of Offsite Power with Safety Injection-DG 18-B Containment Isolation Test";

2-SI-OPS-082-026.B, " Loss of Offsite Power with Safety Injection-DG 2B-B Containment Isolation Test";

and the SI-102 series that documents the performance of vendor roccxnmended mintenance.

'Ihe informtion listed below is a #dulation of DG testing data taken from 0-SI-OPS-082-007.M, " Diesel Gencrubar Surveillance l'requency." 'Ihe data was taken from testiny performcri duriry the period January 1 through December 31, 1993. " Valid Test" and " Invalid Test" are defined in accordance with the criteria established in Regulatory Guide 1.108, Revision 1, August 1977.

[r, DG UFARfS VAIJD TF!rfS VAIJD TI'ST INVAM D TW KS YhD)MB 1A-A 68 15 0 53 1B-D 57 18 0 39 2A-A 93 33 2* 60 2B-B 59 14 0 45 Totals 277 80 2* 197

• 'Ihe failures resulted from (1) the CG set faillig to load to 110 percent load af ter successfully loadirg to 100 percent load, and (2) fallitrj to i fast start within 10 seconds after installing new governors to resolve the l 110 percent loadirg problem. 'Ihe DG set demonstrated that it could fast I start in approximately 10.5 seconds. After adjustments, the DG set demonstrated a fast start in less than 10 seconds.

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'Ihc above data indicates an average of 69.25 starts per DG for the year with only two failures. Two failures out of 277 valid and invalid tests support a reasonable confidence level that the DGs will perform when i required.

SQN recognizes the importance of reducity the number of DG starts. As l shown below, for the operating years 1988 through 1992, a dowrrward trend j

, for DG starts was established. Due to air start urxlifications installed 1 durirq 1993, six-year required maintenance activities,18-month load sequence and endurance testing, and accelerated testing for the ?>A diesel generator, additional starts per DG set were accumulated durity calendar year 1993. The dowrunrd trend in the number of diesel generator starts is ,

expected to return during 1994.

Approxivate # of Total DG Starts per Year 'i 1988: approximately 170 starts per DG per year l 1989: approximately 55 starts per DG per year l 1

1990: approximately 36 starts por DG per year )

1991: approximately 36 starts per DG per year 1 1992: approximately 35 starts per DG per year 1993: approximately 69 starts per DG per year l

SQN will continue efforts to keep DG starts as low as possible to enhance j engine life and DG reliability, l i

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