ML20136A643
| ML20136A643 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1996 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9703100023 | |
| Download: ML20136A643 (12) | |
Text
a Tennessee Valley Authority, Post Office Box 2000. Soddy-Daisy, Tennessee 37379-2000 February 28,1997 U.S. Nuclear Regulatory Commissian 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) - 1996 ANNUAL REPORTS Enclosed are the 1996 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,
(
g R. H. Shell j
Site Licensing and Industry Affairs Manager I
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cc: See page 2
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Enclosure 9703100023 961231 PDR ADOCK 05000327 R
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U.S. Nuclear Regulatory Commission Page 2 l
February 28,1997 cc (Enclosure):
l Mr. R. W. Hernan, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 i
i NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road 4
Soddy-Daisy, Tennessee 37379-3624
'1 Regional Administrator U.S. Nuclear Regt Ntory Commission Region ll 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 1
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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 ANNUAL REPORTS TO THE NUCLEAR REGULATORY COMMISSION JANUARY 1 - DECEMBER 31,1996 DOCKET NUMBERS 50-327 AND 50-328 UCENSE NUMBERS DPR-77 AND DPR-79 4
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7 SEQUOYAH NUCLEAR PLANT ANNUAL REPORTS 1996 i
TABLE OF CONTENTS Page Preface 1
Occupational Exposure Data...................... 2 Diesel Generator Reliability Data 5
Reactor Coolant System Specific A ctivity An alysis.............................. 8 1
SEQUOYAH NUCLEAR PLANT (SON)
ANNUAL REPORTS 1996 PREFACE The following are descriptions of the items contained in this report.
Occuoational Exoosure Data Enclosed is the exposure data for personnel at SON that received greater than 100 millirem between January 1 and December 31,1996. Exposure data for special maintenance is based on the following activities:
Replace Bolts and Nuts of Reactor Coolant Pump Fireshields (Unit 2)
Replace Control Rod Drive Mechanism Dampers and Duct Work (Unit 2)
Chemically Clean Secondary Side of the Steam Generators (Unit 2)
Inspect and Repair Steam Generator Feedwater Backing Rings (Unit 2)
Replace Reactor Coolant Pump Seal and Seal Water Piping Weld Reactor Pressure Vessel Guide Funnels to Upper Head Injection Penetrations (Unit 2) j Replace Electrical Penetrations (Unit 2) l Inspect Canopy Seal Wevis (Unit 2)
Hanger Modifications Qiggel Generator (DG) Reliability Data The reliability data for the SON 6900-Volt emergency DGs is enclosed in accordance with TS 6.9.2.2.
Reactor Coolant Svstem Soecific Activity Analvsis (Specific lodine Isotopic Activity Concentration and/or del-131 Determination)
During 1996, there were no specific iodine activity results of Unit 1 or Unit 2 reactor j
coolant systems exceeding the limits of Technical Specification (TS) 3.4.8.a (1.0 pCi/gm) during either power operation or reactor shutdown and/or start-up.
1
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REXPR219 TENNESSEE VALLEY AUTHORITY RUN DATE: 01-29 97 SON RADIATION EXPOSURE SYSTEM RUN TIME: 00:01:09 NUIBER OF PERSONNEL AW IIAN. REM BY WORK JOB FUNCTION TOTAL NURBER OF IWIVIDUALS NURSER OF PERSONNEL (> 100 M. REM)
TOTAL GAAN-REII I
M0= REACTOR OPS SURVEILLANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL i
EMPLOYEES EMPLOYEES AND OTHERS PERSONS EMPLOYEES EMPLOYEES A W OTHERS M.REIB
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MAINTENANCE PERSONNEL 55 3
40 98 0.481 0.046 0.341 0.848 OPERATING PERSONNEL 45 3
1 49 5.929 0.190 0.000 6.119 f
HEALTH PHYSICS PERSONNEL 37 6
33 76 6.404 0.473 5.066 11.943 i
SUPERVISORY PERSONNEL 9
1 0
10 0.510 0.058 0.000 0.568 ENGINEERING PERSONNEL 22 6
11 39 0.395 0.137 0.344 0.876 11 0 168 19 85 272 13.699 0.904 5.751 20.354
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L M0= ROUTINE MAINTENANCE
-l GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AW OTHERS PERSONS EMPLOYEES EGIPLOYEES AW OTHERS M-REMS j
i IAAINTENANCE PERSONNEL 105 6
267
- 378 21.659 0.725 54.411 76.795 N
OPERATING PERSONNEL 49 5
6 60 1.970 0.126 1.091 3.187 HEALTH PHYSICS PERSONNEL 70 6
34 110 14.300 0.200 3.156 17.656 SUPERVISORY PERSONNEL 17 3
0 20 0.980 0.099 0.000 1.079 ENGINEERING PERSONNEL 38 to 41 89 3.741 0.394 0.708 4.843 MO 279 30 348 657 42.650 1.544 59.366 103.560 l
i M0=IN-SERVICE INSPECTION l
GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL l
EMPLOYEES EtFLOYEES AND OTHERS PERSONS EMPLOYEES ERIPLOYEES A W OTHERS M-REMS I
MAINTENANCE PERSONNEL 11 0
78 89 2.617 0.000 11.909 14.526 OPERATING PERSONNEL 5
0 5
to 0.211 0.000 0.860
'1.071 i
HEALTH PHYSICS PERSONNEL 32 1
25 58 2.556 0.003 3.496 6.055 SUPERVISORY PERSONNEL 5
0 0
5 2.902 0.000 0.000 2.902 ENGINEERING PERSONNEL 10 13 102 125 3.081 2.169 33.169 33.419 f
i MO 63 14 210 287 11.367 2.172 49.434 62.973 1
i IIO=SPECIAL MAINTENANCE i
GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL
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EMPLOYEES ERIPLOYEES AW OTHERS PERSONS ERIPLOYEES EIIPLOYEES AND OTHERS M. REMS
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f MAINTENANCE PE9SONNEL 77 4
123 204 5.840 0.258 22.815 28.913 1
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i REXPR219
' TENNESSEE VALLEY AUTHORITY l
RUN DATE: 01-29 97.
SM AADIATION EXPOSURL SYSTEM RUN TIE : 00:01:09i NUMER OF PERSONNEL AW MAN. REM BY WORK JOB FUNCTION
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TOTAL NUMER OF IW IVIDUALS NUhBER OF PERSONNEL (> 100 M. REM)
TOTAL MAN. REM
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OPERATING PERSONNEL 14 1
5
-20 0.173 0.017 0.212 0.402' l
HEALTH PHYSICS PERSONNEL 38 2
15 55 2.039 0.055 0.331 2.425 SUPERVISORY PERSONNEL 14 0
0 14 0.917 0.000 0.000 0.917
. ENGINEERING PERSONNEL 19 3
73 95 1.200 0.223 15.184 16.607 MD 162 10 216 388 10.169 0.553 38.542 49.264 i
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M0= WASTE PROCESING t
j OROUP STATION. UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT. TOTAL
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EMPLOYEES EMPLOYEES AND OTHERS PERSONS EWLOYEES EIPLOYEES A E OTHERS M-REMS MAINTENANCE PERSONNEL 17 0
8 25 0.202 0.000 0.296 0.498 I
OPERATING PERSONNEL 1
0 2
3 0.001 0.000 0.081 0.082 HEALTH PHYSICS PERSONNEL 40 2
4 46 4.065 0.011 0.721 4.797 SUPERVISORY PERSONNEL 1
0 0
1 0.007 0.000 0.000 0.007 ENGINEERING PERSONNEL 0
0 1
1 0.000 0.000 0.061 0.061 i
MO 59 2
15 76 4.275 0.011 1.159 5.445 i
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M0= REFUEL OROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES AND OTHERS PERSONS EIFLOYEES EWLOYEES A E OTHERS M. REMS i
i MAINTENANCE PERSONNEL 18 1
39 58 1.134 0.010 8.698 9.842
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OPERATING PERSONNEL 11 2
2 15 0.825 0.131 0.023 0.979 r
HEALTH PHYSICS PERSONNEL 14 1
7 22 0.356 0.130 0.335 0.821 e
SUPERVISORY PERSONNEL 5
1 0
6 1.430 0.521 0.000 1.951 EI8GINEERING PERSONNEL 8
1 17 26 0.501 0.247 9.775 10.523 f
k MO 56 6
65 127 4.246 1.039 18.83I 24.116 i
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y 787 81 939-1807 86.406 6.223 173.083 265.712
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REXPR219 TENNESSEE VALLEY AUTH0RITY
- i RUN DATE: 01 29-97 SON RADIATION EXPOSURE SYSTEM
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RUN TIME: 00:01:09 NUISER OF PERSONNEL AW MAN-REM BY WORK JOB FUNCTION
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TOTAL NUISER OF IEIVIDUALS NUtBER OF PERSONNEL (> 100 M-REM)
TOTAL MAN-REM GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT
, TOTAL EMPLOYEES EIFLOYEES A m OTHERS PERSONS EtFLOYEES EIFLOYEES A m OTHERS. M-REIIS MAINTENANCE PERSONNEL 283 14 555 852 31.913 1.039' 98.470 131.422 OPERATING PERSONNEL 125 11 21 157 9.109 0.464 2.267 11.840 HEALTH PHYSICS PERSONNEL 231 18 118 367 29.720 0.872 13.105 43.697 SUPERVISORY PERSONNEL 51 5
0 56 6.746 0.678 0.000
- 7.424 ENGINEERING PERSONNEL 97 33 245 375 8.918 3.170 59.241 71.329 I
787 81 939 1807 86.406 8.223 173.083 265.712 I
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SEQUOYAH NUCLEAR PLANT j
UNITS 1 AND 2 j
DIESEL GENERATOR (DG) RELIAEilLITY DATA REPORT FOR 1996 This report is submitted to comply with Technical Specification (TS) requirement 6.9.2.2 for an
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annual data report for DG reliability.
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The 6.9KV DGs at SON serve as the onsite Class 1E power source. Surveillance Requirements j
(SRs) of the TSs that demonstrate operability of the DGs are accomplished by the routine i
performance of the following Surveillance Instructions (Sis):
1-St-OPS-082-007 A, " Electrical Power System - DG 1 A-A" i
1-SI-OPS-082-007.B, " Electrical Power System - DG 1B-B" l
2-SI-OPS-082-007.A, " Electrical Power System - DG 2A-A"
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2-SI-OPS-082-007.B, " Electrical Power System DG 28-B" l
l' 0-SI-OPS-082-007.0, " Diesel Generator Operability Verification" i
1-SI-OPS-082-026.A, " Loss of Offsite Power with Safety injection -
l DG 1 A-A Containment isolation Test" 1-SI-OPS-082-026.B, " Loss of Offsite Power with Safety injection -
DG 18-B Containment Isolation Test" 2-St-OPS-082-026.A, " Loss of Offsite Power with Safety injection -
DG 2A-A Containment Isolation Test" 2-SI-OPS-082-026.8, " Loss of Offsite Power with Safety injection -
DG 2B-8 Containment 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 December 31,1996. " Valid Test" and " Invalid Test" are defined in accordance with the criteria established in Regulatory Guide 1.108, Revision 1, August 1977.
DG DEMANDS VALID TESTS VALID INVAllD INVALID DG
/ DG STARTS FAILURES TESTS FAILURES 1A-A 24 /24 15 1
9 1
1 B-B 22 / 25 14 0
11 0
2A-A 25 /25 16 0
10 0
2B-B 28 /34 16 0
17 1
TOTALS 99 / 108 61 1
47 2
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1 A v'alid fail'ure, two invalid failures, and an erroneous generator lockout occurred in the calendar year of 1996. The following is a description of each event:
DG 1 A-A incurred a valid start failure while being subjected to maintenance testing on February 29,1996. The starting air system to the 1 A2 engine air starters was isolated (off normal) as part of a maintenance testing activity in accordance with 0-SO-082-1 to prove the integrity of the 1 A1 engine air starters. Neither air boost cylinder appeared to raise the fuel J
rack and with only half of the normal starting torque DG 1 A-A failed to develop adequate actuator pressure to raise the fuel rack before the engine failure timer actuated. The air boost cylinder of each engine was replaced and DG 1 A-A was successfully tested. The air boost cylinders on DG 1B-8,2A-A, and 2B-B have since been replaced as preventative maintenance.
The DG 2B-B's Emergency Breaker was manually tripped open by operations to prevent the Diesel Generator from over loading on January 25,1996. This condition was determined to be associated with the DG 2B-B's governor gain and reset adjustment. While DG 28-B governor gain and reset adequately met voltage and frequency requirements for load sequencing during 2-SI-OPS-082-026.B testing, it allows a type of " reset windup" to develop when ramping up to rated load in a single step under droop mode operation. The gain and reset velues for the governor were adjusted to correct this condition. Testing indicated this condition existed on the other DGs as well but to a lesser degree and did not require adjustment. Based on this having no impact on the asynchronous operation and the safety functions of the DG this event was determined to be an invalid failure.
DG 1 A-A experienced a rough idle while in its 10 minute shutdown period on February 1,1996.
The speed dipped toward 200 RPM several times. The problem was deduced to be a contact on the SS3X relay (Square D Model KPD13) intermittently losing continuity in the de-energized position as described in operating experience report. in response to the operating experience report, the DG 18-B,2A-A, and 28-B relays had already been replaced and DG 1 A-A relays were scheduled for and replaced later that month. Based on the relay not impacting the Diesel
- Generator's ability to perform its design safety function, because this failure only impacted the iole shutdown of the DG, the failure was determined not to affect the valid test that had just been completed.
DG 2A-A experienced an actuation of its 86GA Lockout Relay when the associated trip coil indicating lamp blew. An Instrument Mechanic working near the control panel saw a flash out of the corner of his eye immediately before the click of the 86GA relay. The condition annunciated locally and in the MCR. No protective relaying flags were found dropped and the lamp in series with the 86GA relay was found to be burnt out. The lamp was theorized to have blown and a filament piece landed against the energized filament supports. The shorter filament length allowed adequate current to pass (before burning up) to actuate the 86GA relay, locking out the DG, This event was not counted as a failure based on:
- 1) The event being an annunciated condition (not a hidden failure found during maintenance or during a start attempt), and
- 2) The event would not have prevented the emergency diesel from being started and brought to load within a few minutes (i.e., without corrective maintenance or significant problem diagnosis) if needed to mitigate an accident. This capability would require an operator to be dispatched to the DG and manually reset the 86GA relay. hi.me4-
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SON recognizes the importance of reducing the number of DG starts. As shown below, for the operating years 1988 through 1996, a downward trend for DG starts has been re-established.
The downward trend started in 1988 was interrupted due to air start modification testing, six-year required maintenance testing, and accelerated testing from valid failures on DG 2A-A during 1993. The speed controller modifications and the increased testing from valid failures again on DG 2A-A maintained DG starts above the 1992 average during 1994 and 1995. As revealed by the data below, the number of DG starts in 1996 were reduced below the 1992 average. This is the result of completing the reliability improvements that had required diesel starts during 1993,1994, and 1995.
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 1996: approximately 27 starts per DG per year SON will continue efforts to keep DG starts as low as possible to enhance engine life and DG reliability.
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Reactor Coolant System Specific Activity Analysis (Specific lodine isotopic Activity Concentration and/or' del-131 Determination)
I During 1996, there were no specific iodine activity results of Unit 1 or Unit 2 reactor j
coolant systems exceeding the limits of Technical Specification (TS) 3.4.8.a
. (1.0 pCi/gm) during either power operation or reactor shutdown and/or start-up.
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