ML19309E796
| ML19309E796 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 04/02/1980 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025A817 | List: |
| References | |
| NUDOCS 8004240415 | |
| Download: ML19309E796 (32) | |
Text
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TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT A
March 1, 1980 - March 31, 1980 0
DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE ND!BERS DPR-33, DPR-52, AND DPR-68
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Submitted By:
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Plant Supe'rintendent 8 0 0 4 24 0 y /5 i
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I TABLE OF CONTENTS t
1 Operations Sunnaary.................
1 L
Refueling Information 3
Significant Operational Events.
5 Average Daily Unit Power Level...........
12 Operating Data Reports....
15 Unit Shutdowns and Power Reductions.....
18 Plant Maintenance 21 30 Outage Sununary....
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f UNITSilUTDOWNS AND POWER REs)UCTIONS DOCKET NO.
50-296 UNIT NAME B roem vorrv
' 3 DATE A/? fen COMPLETED BY nna r'ronn REPORT MONTil March TELEPilONE 205 / 7 29-68 t.6
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,E r, f',E Cause & Corrective
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E Action to 35 c2 y is, RePur8 8
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Prevent Recurrence O
118 800308 S
B Derated for turbine control valve tests and SI's.
9 119 800322:
S B
Derated for recirc pumps M.C. set srush replacement and control rod adjustments.
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4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain)
I Manual for Pseparation of Data Italaintenance of Test 2-Manual Scram.
Entsy Sheets for I.icensee C Refueling 3 Automatic Scram.
Event Repuo (1.E!Ol'ilclNUREG-D Regulatory Restriction 4-Oth r (Explain) 0161)
E-Operator Daining & IJcense Examination F AJnunistrative 5
G Operational Error (Explain)
Exhibit 1 Same Source (9p7) 11 Other (Explain) i
BROWS FERRY NUCLEAR PIANT UNIT 1
CSSC EQUIP!ENT MECilANICAL HAINTENANCE SU12tARY For the Month of March 1980 EFFECT ON SAFE ACTION TAKEN DjTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULIS OF IV PRECLUDE MAINTENANCE Tile REACTOR MAT. FUNCTION MALFUNCTION RECURRENCE 3/14/80 RilR FCV 74-66 Packing leak None Water leak None Repacked valve TR 145397 3/12/80 Diesel ID D/G No. 1 Nipple broken None Vibration None Welded line and Generator air compressor-on line causin.r returned air compress.
air leak to service TR 151383 3/13/80 llPCI Solenoid' valves Valves stickin; ; Could 1. ave !!PCI Operator of valve Valves not working Installed new valves 9
73-17A and inope r'a' Ole TR 143071 73-17B 3/17/8(
RilR Angle valve Hand wheel None Operation of Could not manually Replaced hand wheely 74-52 missing valve operate TR 151495 3/17/8f RilR FCV 74-66 Crack in weld None Repaired weld leakoff line going to packi ig TR 137644 gland 3/20/81. Radwaste Valve 77-14B Valve not None Valve would not None Tighten spring tension opening ful1y open TR 153153 3/26/80 SLC SLC shutoff Sodium buildup Nane Packing gland Leaking valve Tightened packing valve 63-11 around valve leaking TR 143979 3/23/80 Reactor "II" Recircula-Replace seal None' Normal wear Degraded seal Replaced seal with Water tion pump seal performance new one Recirculati in TR 137646 3/27/8 ) IIPCI IICV 73-587 Packing leak None Leak at packing Inoperable valve Tightened packing glai gland TR 159324
-3/12/8 ) IIPCI PT 73-4 Drain leaking Disassembled and Isolation valve excessively None Valve leaking Inoperable valve cleaned plug and seal and replaced valve TR 151473
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UROUNS FERRY NUCLEAR FIAtlT UtilT 3
CSSC EQUIPMENT MEC11ANICAL MAINTENANCE SUl21ARY For clic Montli of March 19 80 EFFECT ON SAFE ACTI0li TAKEN DATE SYSTD1 COIIFONEllT NA' LURE OF OPERATION OF CAUSE OF RESULIS OF W PRECLUDE MAItrl'EllANCE T!!E REACTOR MALFIRICTION MAT. FUNCTION RECURRENCE 1/24 EECW FCV 67-50, Filters were None Dirty filters Clogged valves hanged filters per 67-51 and 67-53 dirty schedule maintenance TR 130218 U$
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4 EROWNS FERRY NUCLEAR PIANT UNIT Common s
CSSC EOffIPMENT MECl!ANICAL MAINTENANCE SU t!ARY Fer the Month of Ma rch 19 80 EFFECT ON SAFE ACTION LEEN Il\\TE SYSTEli CO)!PONENT NATURE OF OPElbiTION OF CAUSE OF RESULTS OF
'lU PiiECLUDC 11AINTENAMCE TiiE REACTOR MALFUNCTION R\\LFl%CTION RECIIRRENCE 3/4/80 EECW Sensing line to Pipe leak None Rusted pipe Transmitter sending Installed new valves FI-67-9A false signal and pipe on flow element, FE-67-9A TR 152383 3/6/80 RilRSW D-2 pump Vent valve not None Vent valve Icak All.ows water flow thr i Tightened vent valve seating correc.ly small pipe nipple on TR 137393 top 3/10/80 RilRSW A-3 RilRSW pump Sensing line Loose llangers Vibration of discharg ? Put hangers in suppo:
loose from Norid}
piping
'.'R 137 388 hangers 3/21/80 CAD Tank B 1.cak oa weld o f None Vent valve leaking Valve will frost up Seated valve g
of inner vesse TR 151367 safety and ven P ping i
3/21/8t CAD llCV 84-511 Vent valve wil
.None Valve not seating Inoperable valve Reseated valve and (Tank A) not close stopped leak properly TR 151308 3/21/80 CAD llCV 84-551 F11ange leak-None Bonnet Icak Bonnet will frost up Tightened packing stopped leak TR 151374
w ERO'GS FERRY NUCLEAR PLA'IT UNIT 1
s CSSC FQUTPMENT ELECTRICAL liiTNTENANCE
SUMMARY
For the Month of Ma rch 19 80 I
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Effect on Safe Action Taken Dctc Systcc Ccaponent Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 3-1-80 SLC 1A SLC punp 1A SLC pump NONE Bad Transformer Transformer burned Replaced transfor'er, m
motor motor heater out in compartment.
put system back into keeps tripping operation, checked
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out.
ok, TR#151920 t
i l3-3-80 RiiR llCV 74-22 IC RilR heat NONE Switch out of Position switch out Adjusted position i
exchanger adjustment, of adjustment.
switch for red light outlet valve "P
5 checked ok TR #151952 g
(manual) open red light should be y
illuminated
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l3-3-80 RBCCU Drywell cool Drywell cool NONE Limit switch is Limit switch out of Adjusted limits to I
air inlet air inlet
- bad, adjustment, operate properly.
l valve 70-65 valve 70-65 Lights presently l
and 70-56 and 70-66 does working properly.
not show TR #151953 closed positior 8
lights when llS is in closed position 3-4-80 RllR Testable Lhecl Testable check NONE Limit switch out Red light switch was Adjusted red light valve 74-68 valve 74-68 of adjustment.
out of adjustment.
limit switch. Red red light for light now working disc position properly. TR#143442 will not work.
i 3-4-80 RilR liCV-74-22 "C" Outlet limit NONE BAD switch Position switch out Adjusted valve switch needs af adjustment.
Position switch. Check-to be fixed.
ad ok. TR #151267
w ERO'.?NS FERRY NUCLEAR PLANT UNIT 1 s
CSSC EOUIINENT ELECTRICAL lii1NTEind1CE SUM 1ARY For the Month of March 19 80 Effect on Sate Action Taken
- Dale System Ccaponent Nature of Operation of Cause of Results of To Preclude i
Maintenance The Reactor Malfunction Malfunction Recurrence l3-12-80 RWCU FCU 69-12 Repair unit 1 NONE Bad limit Limits out of Reset limit per Epil-I valve 69-12 adj us tment.
- 18. Checked ok.
.i TR #161462 3-17-80 Fire Fire pump B 4kV ACB trips NONE Bad breaker Breaker tripping Adjusted trip latch j
protection free in normal free, also breaker mechanism so breaker and emergency would not close would not trip free.
I electrically Replace limit switcher
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in closed circuit.
l Breaker operated ok.
l TR #159536 e
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BRO'.!NS FERRY NUCLEAR PIRIT UNIT 2 s
CSSC E0llIP1 TENT ELECTRICAL MAINTCIW1CE Sb72fARY For the Month of March 19 1 l
Effect on Saic Action Taken
! ' 11.-4 c Syste:
Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 3-19-80 RBCCW 2A RBCCW-2A RBCCW pump NONE Bad motor 2A RBCCW pump motor Checked vibration and noisy had some noise, temperature. Both oka
.l Greased bearing and noise cleared up.
l TR #151649 4
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3' CSSC H)!!f MU:t!T ELECTRICAL ILAINTENANCE
SUMMARY
For the Month of
!!a rch 1 910 FItfect on Sate Action Taken Ude Systes Ccaponent flature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction R.2currence i
3-20-80j RWCU FCV-69-2 Replace NONE Bad terminal Terminal block Replaced T.B. and terminal strip block needed replacement lug performed. EMI-block and run 18 A checked ok DtI-18 on TR # 145771 -
valve.
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.s BROWNS FERRY NUCLEAR PLANT UNIT 1,2&3 i
A INSTRUI1ENT MAINTENANCE
SUMMARY
CSSC Ef)lIIPMENT FOIL Tile MONTil OF Marci 19 80 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN DNIE SYSTEM COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MATNTEl&JICE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Unit 1 3-4 Control Rod RPIS Probes Drive 42-39 Replace Mone Faulty reed switcl No "00" indication None 34-59 Replace None Faulty reed switcl "o "00" indication hone 34-31 Replace None Faulty reed switcl No Full-in indication None 3-10 Stand-by TS-63 Calibrate None Setpoint Drift liigh Temp. Alarm Would None Liquid l
Not Clear Control 3-23 Control Rod RPIS Probe Replace None Faulty reed switcl Superimposed Positions None Drive 46-55 Jnit 2 O
l-24 Radiation RM-90-265 Repair None Faulty Pre-Regul-RegdLowon10 and None -
Monitoring ator 10 position snit 3 Radwaste FQ-77-16 Calibrate None Instrument Drift Indicated Flow with None -
Pump Off 3-10 Emergency IT-67-9A,B Calibrate None Instrurent Drift Showed Flow Too Low None Equipment Cooling Water l
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t. (J 30 OUTAGE
SUMMARY
March 1980 During this reporting period, the Unit 1 generator bearing grounding problem was identified and repaired. This problem did not contribute to the outage extention. MSRV 1-13 was leaking during startup.
This valve was changed out and sent to Wyle Labs for retesting.
The valve did pass the stean test and will be used as a standby spare.
The Unit 1 RPCI turbine work was critical path work during the month.
Frame straightening and pedestal replacement extended the outage by 8-10 days. The feedwater check valve 3-568 was discovered leaking. A new seal plate was placed in the valve and a hydro was conducted. Other Unit 1 items included oil level annunciator problemy on the recirc pamp and neutral bus fault problems. ModificationI started or continued during th'e month in-cluded security, low level radwaste storage (cable shed), Unit 3 condenser pullout radwaste storage area and the area outage office. The inspection of hangers and anchors associated with NRC Bulletins 79-14 and 79-02 continued with configuration inspection on NRC Bulletin 79-14 and plate and anchor grouting on NRC 79-02.
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