ML20100M764

Annual Repts for Jan-Dec 1995

ML20100M764
Person / Time
Site:	Sequoyah
Issue date:	12/31/1995
From:	Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9603050512
Download: ML20100M764 (12)

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Tennessee Valley Authority. Post Office Rom 2000. Soddy-Darsy Tennessee 37379 February 28,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SON) - 199F; ANNUAL REPORTS Enclosed are the 1995 Annual Reports for SON. These reports contain a summary of the following items: occupational exposure data, reactor coolant system specific activity analysis, and diesel generator reliability data.

These reports are 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 (423) 843-7527.

Sincerely, kr k.

R. H. Shell Manager Sequoyah Site Licensing Enclosure cc: See page 2 9603050512 951231 PDR ADOCK 05000327 R PDR

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, 4 U.S. Nuclear Regulatory Commission Page 2 February 28,1996 i

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Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North .

11555 Rockville Pike i

. Rockville, Maryland 20852-2739 l

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NRC Resident inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road-Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission ,

Region il  !

101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711

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i TENNESSEE VALLEY AUTHORITY i

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 ANNUAL REPORTS TO THE NUCLEAR REGULATORY COMMISSION JANUARY 1 - DECEMBER 31,1995 .

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DOCKET NUMBERS 50-327 AND 50-328 LICENSE NUMBERS DPR-77 AND DPR-79

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SEQUOYAH NUCLEAR PLANT ANNUAL REPORTS 1995 .

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Page Preface .. ............................... 1 Occupational Exposure Data ..................... 2 '

Diesel Generator Reliability Data . . . . . . . . . . . . . . . . . . . 6 Reactor Coolant Sys' tem Specific Activity Analysis ............................. 9 l

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l SEQUOYAH NUCLEAR PLANT (SON)

ANNUAL REPORTS 1995 PREFACE The following are descriptions of the items contained in this report.

Occupational Exposure Data Enclosed is the exposure data for personnel at SON that received greater than 100 millirem between January 1 and December 31,1995. Exposure data for special maintenance is based on the following activities: )

1 Spent Fuel Pool Rerack )

Installation of Steel Platforms in Residual Heat Removal / Component Cooling System (RHR/CS) Heat Exchanger Rooms Hanger Modifications

-Installation of a Cable Drive System for Fuel Transfer  ;

Chemistry Program Upgrade in the Hot Sample Room (Units 1 and 2) i Vent Hose Installation on RHR Piping inside Lower Containment (Units 1 and 2)

Repair of Damaged Fitting at the Seal Table (Unit 1)

Actuator Repair and inspection of 1-VLV-62-70 (Unit 1)

Replace Bolts and Nuts on Reactor Coolant Pump Fireshields (Unit 1)

Replace Control Room Drive Mechanism (CRDM) Dampers and Duct Work (Unit 1)

Installation of Transfer Switches and 480-Volt Receptacle to CRDM Coolers (Unit 1)

Replace Feedwater Nozzle Transition Pieces (Unit 1)

Chemically Clean Secondary Side of the Steam Generators (Unit 1)

Weld Reactor Pressure Vessel Guide Funnels to Thermal Sleeves (Unit 1)

Repair Bent Thermocouple Column (Unit 1)

Repair Canopy Seal Weld (Unit 1)

Reactor Coolant System Specific Activity Analysis (Specific lodine Isotopic Activity Concentration and/or del-131 Determination) l During 1995, 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 Ci/gm) during either power operation or reactor shutdown and/or start-up.

1 Diesel Generator (DG) Reliability Data The reliability data for the SON 6900-Volt emergency DGs is enclosed in accordance with TS 6.9.2.2.

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'REXPR219 TENNESSEE VALLEY AUTH0RITY 5 RUN DATE: 01-24 96 SON RADIATION EXPOSURE SYSTEM -

• RUN TIME: 10:46:03 NUMBER OF PERSONNEL AND MAN. REM BY WORK JOB FUNCTION TOTAL NUMBER OF INDIVIDUALS NUMBER OF PERSONNEL (> 100 M. REM) TOTAL MAN-REM

M0= REACTOR OPS SURVEILLANCE OROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT . TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES . EMPLOYEES ANO.OTHERS 'M-REMS MAINTENANCE PERSONNE: 90 2 156 248 1.756 0.019 3.292 5.067 OPERATING PERSONNEL 53 3 7 63 7.560 0.460 0.061 8.081 HEALTH PHYSICS PERSONNEL 58 3 55 116 6.254 0.213 -7.921 14.388 SUPERVISORY PERSONNEL 13 6 0 19 0.773 0.233 0.000 1.006 ENGINEERING PERSONNEL 24 6 9 39 0.676 0.024 0.628 1.328 MO 238 20 227 485 17.019 0.949 11.902- 29.870 WO= ROUTINE MAINTEMANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMoLOYEES AND OTHERS PERSOUS EMPLOYEES EMPLOYEES AND OTHEPS M~9 EMS MAINTENANCE PERSONNEL 113 4 367 484 29.103 0.682 69.706 99.491 8 OPERATING PERSONNEL 52 5 9 66 1.556 0.145 1.197 2.898 7 HEALTH PHYSICS PERSONNEL 74 18 3

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137 25 19.400 3.385 0.083 0.158 7.288 0.000 26.771 3.543 SUPERVISORY PERSONNEL ENGINEERINO PERSONNEL 31 19 60 110 3.242 0.818 8.368 12.428 WO 288 38 496 822. 56.686 1.886 86.559 145.131 M0=IN-SERVICE INSPECTION OROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY _ CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES ANO OTHERS M-REMS MAINTENANCE PERSONNEL 16 0 48 64 2.427 0.000 9.020 11.447 OPERATINO PERSONNEL 6 1 4 11 0.714 0.126 0.079 0.919 HEALTH PHYSICS PERSONNEL 28 4 38 70 2.001 0.505 8.566 11.072

, SUPERVISORY PERSONNEL 2 5 0 7 0.076 0.810 0.000 0.886 ENGINEERING PERSONNEL 7 23 109 139 0.787 8.102 51.757 60.646 MO 59 33 199' 291 '

6.005 9.543 69.422 84.970 1*PSPECIAL MAINTENANCE l GROUP STATION UTILITY CONTRACT TOTAL -STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES AND OTHERS M-REMS

,; iMINTENANCE PERSONNEL 62 3 256 321 7.729 0.599 60.076 68.404 4

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REXPR219 TENNESSEE VALLEY AUTHORITY

• L RUN DATE: 01 24 96 SON RADIATION EXPOSURE SYSTEM ~ ' '

RUN TIME: 10:46:03 NUIEER OF PERSONNEL AND MAN-REM BY WORK JOB FUNCTION

- TOTAL NUMBER OF INDIVIDUALS

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f NUIEER OF PERSONNEL (> 100 M-REM) TOTAL MAN-REM T OROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPi.OYEES AND OTHERS PERSONS. EMPLOYEES EMPLOYEES AND OTHERS M-REMS MAINTENANCE PERSONNEL 299. 9 867- 1175 41.658 1.300 145.398 188.356 OPERATING PERSONNEL 145 12 34 191 10.836 1.165 3.604 ~ 15.605 HEALTH PHYSICS PERSONNEL 253 11 197 461 34.238 0.809 ^ 24.917 -59.964 I SUPERVISORY PERSONNEL 49 23' 2 74 6.259 1.446 0.282 7.987 ENGINEERING PERSONNEL 86 55 272 413 6.516 9.420 88.693 104.629 '

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832 110 1372 2314 99.507 14.140 262.894 376.541  ;

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RUN DATE: 01 24-96 SON RADIATION EXPOSURE. SYSTEM * ' , ,

RUN TIME: 10:46:03 fr.AEBER OF PERSONNEL AND MAN-REM BY WORK JOB FUNCTION TOTAL NUMBER OF; INDIVIDUALS OROUP STATION- UTILITY CONTRACT TOTAL MAINTENANCE PERST.?EL 114 .4 396 514 OPERATING PERSONNEL '54 5 12 -71 HEALTH PHYSICS PERSONNEL 67 2 68 137 SUPERVISORY PERSONNEL 19 6 2 27 ENGINEERING PERSONNEL 28 13 144- 185' 282 30 622 934 I

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l SEQUOYAH NUCLEAR PLANT 3

, UNITS 1 AND 2 ,

DIESEL GENERATOR (DG) RELIABILITY DATA REPORT FOR 1995 4

. .This report is submitted to comply with Technical Specification (TS) 6.9.2.2 for an annual data report for DG reliability. The 6.9 kilovolt DGs at SON serve as the onsite j Class 1E power source. Surveillance requirements (SRs) of the TSs that demonstrate operability of the DGs are accomplished by the routine performance of the following surveillance instructiona (SI)

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~ 1-SI-OPS-082-007.A," Electrical Power System - DG 1 A-A" 1-SI-OPS-082-007.B," Electrical Power System - DG 18-B,"

2-SI-OPS-082-007.A," Electrical Power System - DG 2A A" 2-SI-OPS-082-007.B," Electrical Power System - DG 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-DG 1 A-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- l DG 1B-B Containment Isolation Test" j 2-SI-OPS-082-026.B," Loss of Offsite Power with Safety injection-DG 2B-B Conte.inment isolation Test" SI-102 series documents the performance of vendor recommended maintenance.

The information listed below is a tabulation of DG testing data taken from ,

0-SI-OPS-082-007.M," Diesel Generator Surveillance Frequency." The data was taken from testing performed during the period of January 1 through Decernber 31,1995. ,

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

VALID TESTS INVALID INVALID DG DG STARTS VALID TESTS FAILURES TESTS FAILURES 1 A-A 43 18 0 25 1-1 B-B 40 16 0 24 1 2A-A 41 23 0 18 1 ,

28-B 38 13 0 25 2 TOTALS 162 70 0 92 5 e

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I .There were five invalid failures which occurred in 1995 and are described below.

t i DG 1 A tripped while being loaded to 110 percent of its rated load as required by SON TS SR 4.8.1.1.2.d.7. The trip was initiated by the Phase Imbalance (46) Relay.

-The relay had been replaced over a year ago and the new relay's setpoint drifted.

The trip capability of this relay is isolated during emergency mode operation and therefore would not have prevented the DG from performing its deoign function.

A DG 1B Valid Test was stopped to allow investigation of a Ground (64) Relay actuation. The relay has a low threshold and actuates momentarily during field l flashing. Check out of the relay identified the relay to be sticking. The relay was l

cleaned, calibration checked and returned to service. The trip capability of this relay -

is isolated during emergency mode operation and therefore would not have prevented the DG from performing its design function.

l A DG 2A Valid Test was stopped prior to completing its one hour loaded run to allow l= investigation of why voltage had appeared while in the 5-minute idle warmup period.

, The test was stopped, not due to the inability of the diesel to continue with the run, i

but to minimize the LCO time for the diesel. Trouble shooting and evaluation of the circuit identified that a relay binding problem prevented the exciter field from being -

shunted. This would not have affected emergency mode operation and therefore would not have prevented the DG from performing its design function.

4 A DG 2B Valid Test was emergency stopped prior to loading for the one hour run due j to a low lube oil pressure annunciation. The pressure switch had drifted out of calibration and could not be recalibrated. The trip from this pressure switch is isolated during emergency mode operation and therefore would not have prevented the DG from performing its design function.

DG 2B tripped on high crankcase pressure during an idle start for a maintenance outage functional test. The pressure switch had drifted out of calibration and could ,

not be recalibrated. The trip from this pressure switch is isolated during emergency l mode operation and therefore would not have prevented the DG from performing its design function.

' The above data indicates an average of 40.5 starts per DG for the year with no valid failures. This gives a strong indication that the DGs will perform when required.

SON recognizes the importance of reducing the number of DG starts. As shown below,

for the operating years 1988 through 1992, a downward trend for DG starts was F established. ' Due to air start modifications installed during 1993, six-year required l

maintenance activities,18-month load sequence and endurance testing, and i accelerated testing for the 2A-A DG, additional starts per DG set were accumulated i during calendar year 1993. Due to the speed controller modification on 2A and 2B DGs, and the increased testing resulting from valid failures on DG 2A, above average

DG starts were accumulated during calendar year 1994. A TS change was submitted i

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to and approved by NRC to revise the TS wording of SR 4.8.1.1.2.a.4, which required the diesel speed to reach at least 900 rpms during monthly testing and allowed the associated Valid Failure on DG 2A to be declared a Valid Success. As revealed by the data below, the number of DG starts in 1995 were again reduced, but not as low as 1992 due to the speed controller modification on DG 1 A and DG 1B and accelerated ,

testing on DG 2A extending into February of 1995 before NRC approval was obtained to reverse the valid failure status.

APPROXIMATE NUMBER OF TOTAL DG STARTS PER YEAR 1988: approximately 170 starts per DG per year 1989: approximately 55 starts per DG per year 1990: approximately 36 starts per DG per year 1991: approximately 36 starts per DG per year 1992: approximately 35 starts per DG per year 1993: approximately 69 starts per DG per year 1994: approximately 47 starts per DG per year 1995: approximately 41 starts per DG per year SON will continue efforts to keep DG starts as low as possible to enhance engine life and DG reliability, i

i Reactor Coolant System Specific Activity Analysis

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(Specific lodine isotopic Activity Concentration and/or del-131 Determination)

During 1995, there were no specific iodine activity results of Unit 1 or Unit 2 reactor l coolant systems exceeding the limits of Technical Specification (TS) 3.4.8.a '

(1.O pCi/gm) during either power operation or reactor shutdown and/or start-up.

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