ML20042A407
| ML20042A407 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/01/1982 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20042A401 | List: |
| References | |
| NUDOCS 8203230395 | |
| Download: ML20042A407 (25) | |
Text
_._
TENNESSEE VALLEY AUT110RITY-3 DIVISION OF POWEk PRODUCTION BROWNS FERRY NUCLEAR PLANT
- m%
a MONTilLY OPERATING REPORT December 1, 1981 - December 31, 1981 i
DOCKET NUMBERS 50-259, 50-260, AND 50-296 7
LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 i
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Submitted By:
g 8203230395 820108
- antSupe(/ntendent PDR ADOCK 05000259 i
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TABLE OF CONTENTS 1
Operations Summary.
-~_
Refueling Information 3
Significant Operational Events.
5 Average Daily Unit Power Level.
10 Operating Data Reports.
13 Unit Shutdowns and Power Reductions.
16 Plant Maintenance 19 Outage Summary.
32 Errata.
35
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y Operations Summary December 1981 Tl'ie following summary describes the significant operations activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were 21 reportabic occurrences and four revisions to previous reportable occurrences reported to the NRC during the month of December.
Unit 1 There were no scrams on the unit during the month.
Unit 2 There was one scram on the unit during the month.
On December 29, the reactor scrammed on a f alse low reactor water Itvel signal when a wrong valve was opened on a reactor water level switch during a surveillance instruction which drained the reference leg of the switch and gave the false signal.
Unit 3 The unit was in its EOC-4 refueling outage the entire month.
Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00521 0.00424 0.00361 Feedwater nozzle 0.24939 0.18260 0.14108 Closure studs 0.20492 0.14293 0.10977 NOTE:
This accumulated monthly information satisfies technical specification section 6.6.A.17.B (3) reporting requirements.
3 d
Operations Summary (Continued)
December 1981 Refueline Information
/-
- -~-
Unit 1 Unit 1 is scheduled for its fifth refueling begi6ning on or about March 4, 1983, with a scheduled restart date of June 3, 1983.
This refueling will-involve loading 8 X 8 R (retrofit) fuel assemblics into the core, finishing the torus modifications, turbine inspection, and finishing IMI-2 modifications.
There are 764 fuci assemblies in the reactor vessel. The spent fuel storage pool presently contains 260 EOC-4 fuel assemblies, 232 EOC-3 fuel a
assemblies, 156 EOC-2-fuel assemblies, and 168 EOC-1 fuel assemblies.
The pre-capacity is 2655 l'ocations.
sent Unit 2 Unit 2 is scheduled for its fourth refueling beginning on or about July 30, 1982, with a' scheduled restart date of January 1, 1983. This refueling outage will involve completing relief' valve modifications, torus modifications, "A" low pressure turbine.insnection, MG set installation for LPCI modification, and loading additional 8 X 8 fuel assemblies into the core.
There are 764 fuel assemblies in the reactor vessel. At the end of the month there were 352 EOC-3 fuel assemblics, 156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent storage pool.
The present available storage capacity of the spent fuel pool is 160 locations. With present capacity the 1979 refueling was the last' refueling that could be discharged to the spent fuel pool without exceeding that ' capacity and maintaining full core discharge capability in the pool, liowever, 949 new high density storage locations have a
been installed and can be used after they are qualified.
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Significant Operational Events Unit 1 Date Time Event
. _ _ ~
12/01/81 0001 Reactor thermal power at 99%, maximum flow, rod limited.
12/04/81 2300 Commenced reducing thermal power for recir-culation pump MG set brush replacement; control rod sequence exchange from "A" to "B" and turbine control valve tests and SI's.
12/05/81 0110 Reactor thermal power at 50%, holding for con-trol rod sequence exchange; recirculation pump MG set brush replacement and turbine control valve tests and SI's.
0247 Turbine control valve tests and SI's complete; Reactor power at 50%.
0331 Recirculation pump MG set brush replacement complete, holding at 50% power for control rod sequence exchange from "A" to "B".
0702 Control rod. sequence exchange complete, commenced power ascension.
1315 Commenced pCIOMR from 89% thertsal power (sequence "B").
2200 Reactor the. mal power at 99%, maximum flow, rod limited.
12/12/81 2215 Commenced reducing thermal power for S1 4.7.D.1.b-2 (main steam line valve closure).
2300 Reactor thermal power at 71%, holding for SI 4.7.D.l.b-2.
12/13/81 0025 SI 4.7.D.l.b-2 main steam line valve closure complete, commenced power ascension.
0047 Reactor thermal powet' at 84%, holding for turbine control valve tests and SI's.
0125 Turbine control 'falve tests and SI's complete, commenced power h(utsion.
2
<w; at 99I, maximum tiow, 0300 Reactor there rod limited.
thermal power for turbine 12/19/81 2347 Commence
.e; control u lve testa and SI's.
2400 Reactor thermal power ;d 89*:, holding for turbine control valve tests and SI's.
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7 Significant Operational Events Unit 2 Date Time Event
- ..~%-
12/01/81 0001 Reactor thermal power at 99%, maximum flow, rod limited.
12/05/81 2150 Commenced reducing thermal power for control rod, pattern adjustment, turbine control valve test and SI's.
2400 Reactor thermal power at 64%, holding for control rod pattern adjustment and turbine control valve tests and SI's.
12/06/81 0150 Control rod pattern adjustment, turbine control valve tests and SI's complete, commenced power ascension.
0530 Commenced PCIOMR from 76% thermal power (sequence "B").
12/07/81 0130 Reactor thermal power at 99%, maximum flow, rod limited.
~
12/13/81 0122 Commenced reducing thermal power for turbine control valve tests and SI's.
0130 Reactor thermal power at 87%, holding for turbine control valve tests and SI's.
0155 Turbine control valve test complete, commenced power ascension.
0230 Reactor thermal power at 95%, holding for S1 4.3.A-2 (CRD Exercise).
0255 CRD exercise complete, commenced power ascension.
0300 Reactor thermal power at 99%, maximum flow, rod limited.
12/19/81 0725 Reduced thermal power to 97% due to demeneralizer problems.
1212 Commenced power ascension from 97% thermal power.
1300 Commenced reducing thermal power from 98% du'e to problems with "B" recirculation pump (amps and speed indication swinging).
1400 Reactor thermal power at 97%, holding due to "B"
recirculation pump instability.
1537 Commenced power ascension from 97% thermal power.
12/20/81 0110 Reduced thermal power from 98% to 82% for turbine control valve tests and SI's.
0141
. Turbine control valve tests and SI's complete, commenced power ascension.
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9 A
e Significant Operational Events Unit 3 Date ~
Time Event
. _ _ ~
12/01/81 0001 End-of-cycle 4 refuel outage continues.
12/31/81 2400 End-of-cycle 4 refuel outage continues.
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10 AVERAGE DAILY UNil POhER LEVEL DOCKET NO.
50-259 Brown's Ferry - 1 UNII 1-1-82 DATE
. _ _ ~
COMPLETED 11Y Ted Thom 205 729 6846 TELEPllONE M O N Til December 1981 i
DAY AVERACE DAILY POhER LEVEL DAY AVER AGE DAILY POhER LEVEL (Mbe Net)
(MWe-Net) 1070 g7 1068 1070 1071 2
g3 3
1070 1067 in 1049 1064 4
20 832 1069 5
3, 6
1062 1014 22 1G54 1056 7
33 1069 1055 8
1067 1060 9
25 10 in71 26 1072 1077 1069 ig 77
- y 1047 998 33 3
1043 1016 29 14 1070 1067 30 1069 1075 I5 3
i,,
1069 INSTRUCTIONS On this tormat. !nr the nerage d.nis unit power Inci in MWe Nei los each day in the reporting m. nth. C. mpute i..
t }lf 11t*JrCs! h!iole !!)epJW Jt t.
(L (9 /77 )
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12 WEl{ \\GE DAll_Y t!NI'I POh!'It LLVEL DOCKET NO.
50-296 Brom Feny - 3 UNIT DATE _1-1-82 COitPLETED tsY Ted Thom -
' ~ ~ ~
205 729 6846 TELEPflONE December 1981 SION111 DAY AVER AGE DAILY POWEll LEVEL DAY AVER AGE DAILY POWEI LEVEL (5the Net)
(SIWE-Net )
-5 17
-3
-5 2
is
-3
-3
-3
+
3
,9
-2 4
20
-3
-3 5
21
-3
-3
-3 6
yy
-2
-3 7
33
~3
-3 3
34
-3 9
25
-3
-3 10 26
-2 11
-3 27
-2
-3 12 ys
-3
-3
-3 13 39
-4
-2 14 30
-3
~
-3 15 3
-3 g3 INSTit U(. IIONS On Ilm torinat, h>: the aserage daik 6. int power toel in.\\lne Net f or each d. 3 in the rep niing in..nih. C..inpute t<>
the neJrest u hole inepaw.iit.
t est77i
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OPERATING DATA REPORT DOCKET NO. 50-259 DATE 1-1-82 COh!PLETED BY Ted Thot
' ~ ^
TELEPIIONE 205 ??9 684'6 OPERATING STATUS Browns Ferry - 1 Notes
- 1. Unit Name:
December 1981
- 2. Reporting Period:
3293 '
- 3. Licensed Thennal Power (MWr):
1152
- 4. Nameplate Rating (Gross.\\1We):
1065
- 5. Design Electrical Rating (Net MWe):
1098.4
- 6. Masimum Dependable Capacity (Gross MWe):
- 7. Masimum Dependable Capacity (Net MWe):
- 1065 S. If Changes Occur in Capacity Ratings (!tems Number 31hrough 7) Since Last Report. Give Reasons:
NA NA
- 9. Power Lesel To hhich Restricted,If Anv(Net MWe):
NA
- 10. Reasons For Restrictions. lf Any:
This Month Yr.-to.Dat e Cumulative 744 8,760 65,042
- 11. Ilours in Reporting Period 744 4,508.23 39,314.8
- 12. Number Of flours Reactor Was Critical 0
116.33 5,215.20
- 13. Resetor Resene Shutdown flours 744 4437.35 38,430.17
- 14. Ilours Generator On.Line
- 15. Unit Resene Shutdown llours 0
0 0
- 16. Gross Thermal Energy Generated (MWil) 2,404,219 13,582,546 106,874,907
- 17. Gross Electrical Energy Generated (MWil) 802,000 4,529,160 35,292,450
- 18. Net Electrical Energy Generated (MWil) 782,219 4.405, 092 34,268.909
- 19. Unit Senice Factor 100
- 20. Unit Asailability Factor 100
_ 50.7 59.1 50.7 59.1 98.7 47.2 49.5
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (U.ing DER Net!
98.7 47.2 49.5 s
- 23. Unit Forced Outa;c Itate 0
3.7 27.1
- 24. Shutdowns Scheduled Oser Nest 6 Months ('lype. Date.and Duration of Eacht:
- 25. If Shur ll..wn At Lail Of Report Perioil. Estimated Date of Startup:
- 26. Units in Test Status ti'rior to Conuncrcial Operationi:
Forceast Achiesed f
s INITI \\ L CRITICALITY
(
INIII AL ELECTRICITY
^ 1 CO\\l%1ERCl %L OPER AllGN
15 OPERATING DATA REPORT 50-295 DOCI'ET NO.
DATE 1-1-82 COSIPLETED 11Y._Tod Thom 405 729-~684 6 - ~
TELEPilOSE OPERATING STATUS
- 1. Unit Name:
Brons Feny - 3
- %e5 December 1981
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (SIWI):
115
- 4. Nameplate Rating (Gross alWe):
- 5. Design Electrical Rating INet S!We). 1065
- 6. Stasimum Dependable Capacity (Gross 51We):
1098.4 1065
- 7. Slasimuin Dependabic Capacity (Net 51We):
S. If Chan;es Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:
NA Net alwel:
NA
- 9. Power Lesel To htiich Restricted. If Any (A N
- 10. Reasons For Restrictions,if Any:
This alonth Yr.. o Date Cumulative 744 8,760 42,408
- 11. Ilours in Reporsing I'eriod 0
6,495.71 32,466.98
- 12. Number Of flours iteactor Was Critical
- 13. Reacior Reserve Shutdown llours 0
330.64 2,141.53
- 14. !!aurs Generator On.Line 0
6,360.78 31,750.78
- 15. Unit Resene Shutdown !!ours 0
0 0-
- 16. Gross Thermal Energy Generated (alWil) 0 19,493,592 93,858,620
- 17. Gro,s Electrical Energy Generated (N1Wil) 6,459,160 30,998,190 0
0 6,264,623' 30,088,946 l
- 18. Net Electrical Energy Generated (S!Wil)
- 19. Unit Senice Factor 0
72.6 74.9 0
72.6 74.9
- 20. Unit Asailability Factor
(
- 21. Unit Capacity Factor (Using AIDC Neti 0
67.1 66.6 l
- 22. Unit C.spacity Factor (Using DER Net) 0 67.1 66.6 0
7.1 9.2.
- 23. Unit Forced Outage Itate
- 24. Shutdowns Scheduled Oser Nest 6 alonths IT.s pe. Date.and Duration of Fach t:
i tiarch 1982 25.11 *> hut Dawn At End Of Report Period. Estimated Date of Startup:
- 26. Units in les Status t Prior to Commercial Operationi,:
Iorecast Achiesed k
INilIT L CRi1ICA LIIY INI TIT L ELECTRICITY
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CO\\l%IERCI AL OPER ATION
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2 UNIT Sill!TDOWNS AND POWER REDUCTIONS
. DOCKET NO.
50-259 UNIT N AME Browns Ferry -1 DATE._l-1-82 December COMPLETED IlY
~Ted Thn REPORT MONT11 TE!.l l'ItONE 205 7?9 6 &'i 1
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J.T kC Procn1 Resurrente L
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7 193 12-04-81 F
.B Derated for recirculation pump MG set brush replacement, control rod sequence exchange (A to B), turbine control valve tests and SI's.
194 15-12-81 S
B Derated for main steam line valve y
closure (SI 4.7.D.1.b-2)..
o' 195 12-22-81 F
11 Derated for control rod pattern adjustment.-
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3 4
f F.nsed Reason.
Method:
1:shiNt G. instructio.is S Ssheiluteil
\\.I.iutpment failure ll.splain) 1 Manual fin Ps ep.u.ition of D.na li M sintenance or Test
.' M.mual Seram.
1:nt > Sheets loi 1.isensee C.Refueline 4 Aui nnatic Stram.
I'.sens Repon i1.I'R11'ile INllRI G-D Iteyutatiii) Restriction -
4 Other iINplaini 01011 l'-opeiator Tranung & !.itense i samm.ition I Adiitistist ati.e G.Uper ational 1 e sos libplain) lhhibit 1 Same Sonice 19/77)
Il-O:her tinpland a
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50-296 UNIT StillTDOWNS AND POWER REDUCTIONS DOCKLT NO.
UNIT N AstE Browns Ferry - 3 DAIE l ti 2 December COMPLETED ity Ted Thom REPORT StONTil lEl.EPIIONE 205 729 6846 i
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(Cont)
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Stethod:
l'shiNi G. Instinsin is S: S, heit n!eit
\\-I ijnspment Failure (1 spl. sin)
!- Alanual t n l'i c p.n a t i. in of D.n a Italainscrunee i.r Test
' Alannat Serani.
1.nin sheets 1 n I.,eensee C Refueling
.i. Autinnatie Liain.
1.sen't Rep ui (t.! R i l'ile i NtiRI G.
D 3:eynlaton itestriction 1.Olliel t I spl.nni (1t til )
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- s. i. a a w L;a i A o L a " n.a a CSSC EQUIpME::T ELECTRIC.\\L FL\\INTE: led:CE SU."l-LiRY December 81 FOR file MO:iTil 0F 37 I
~
I 7trect-Sa[c Action 1,fes on D. t c S y s t c r-Ceeponent
': ture of 0;'e t a t i o n of Cause of Result: cf 7e peccluJe I
'Mintennnte lhe I:c.:: t e r
'.ti f :nc t ion
- tal' unction g.acurrenc_
i 11/27/81' Fire Smoke detec-The smoke None Water in the Received a false Replaced the smoke Protec-tor XA detector l
smoke detector alarm which would detector,' perform-tion 66X:t located initiated a from a undeter-have masked signale ed SI4.11.C.155.
in reactor false alarm mined source from detcetors The detector bldg. El. 565 and would not which are required operated proper 1:.
R7, N line clear to be operable TR #282106 LER#BFRO-50-259/
8187 1
1 i
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i 12/3/81 i RIIRSW 2A RilRSW Excessive None Bad top mator Excensive vibra-Replaced the top pump motor vibration bearings tion pump motor bear-a ings and changed oil per F:II 64. g The pump motor operated properly.
TR #267706 F
f 12/6/81 Fire Smoke During normal
,None Increased Received a false Replaced the smoke Protec-detector operation..the detector alarm which would detector, perform-tion (XS-39-66YD) smokedetectoy sensitivity due have masked signaln ed SI4.ll.C.155.
initiated a to normal, from detectors The detector l
natural aging which are required operated proper 1:..
false alarm and would not to be operable TR #226528 l
clear LER#BFRO-50-259/
8188 l
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o.w. ;. s e c.ed i UU;. LEAR 1%wg twad? 1 & Common CSSC EQUIPMENT ELECTRICAL MAINTE!iA? ICE SU10DU;Y F0tt THE MONTH OF December 19 81 f.1 T C C t on balc Action Ta k c ;.
Date Syster Ceeponent I:s ture of Operation of Cause of Results of To Freclude Mainten nce The Rcactor Malfunction lfalfunction Facutrence 12/20/81' Air (FC0 31-152)
FC0 31-152 None Bad modutrol FC0 31-152 failed Replaced,the Condi-
'B' emergency would not j
motor to open modutrol'cotor tioning p res su ri za--
open during and the SI was (cooling-tion modutrol the perform-successfully heating) motor ance of corJp le t ed.
SI4.2.C-2 TR #281516 LER#BFRO-50-259/
8191 i
12/22/81 Radia tior$ RA 90-259 During the None, the pro-Bad annuncia-RA 90-259 Replaced the Monitor-A or B performance tective func-tor card annudciator annunciator i
ing annunciation of SI4.2.C-2 tion of the circuitry was circuitry card, circuitry alarm for radiation
- inopcrable the alara opers RA 90-259 A monitors was ated properly.
or B failed operable TR #281217 to annunciate t'
12/24/81I Fire Fire protec-Ueckly None Low specific The ' batteries l
Replaced the bad Protec-tion batter-battery check gravity would not main-batteries per tion les in panel (EMI 4A) ?
tain a proper D!I 4.
0-25-296 charge TR #250523 cells 7-12 TR #250524 l and panel TR f257930 1-25-303 cells 7-12 1
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4 4
4 4
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E!.ECTRICAL !L\\IN rE:!ANCE SLROL'd Y Q C EOUll':!"':T FOR flit 210NTl! OF Ilecembe r 19 81 n
- - -date
- i. : rec: on tsction
.# a k e a Date System Cccronent
- a tu r e o f Oneraticn of Cause of Ec s u l.* : of To p cclud.:
ltain:enance ihe Itc;ctor
!!a l f u n e :..e n ta l f ur. :: lo..
g.2 c u r r e n c_e RCIC Verify opera-
!!one The tachometer The tachemeter was Adjusted the L2/2/81 RCIC tachometer tion of RCIC was out-of-reading approri-tachomet: r per s
calibration mately 250 RPM EMI 37A speed control circuitry low TR 8282236
!2/3/61 Fire Smoke detec-The smoke None Bad detector The detector was Replaced the Protec-tor (XA detector was Initiating false detector and tion 8 7L'S) initiating alarms performed SI inndvertent 4.11.C.165.
The i
alarns
' detector operated properly.
TR #201899 PJ i
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CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUNIARY FOR THE MONTH OF December 19 81 j
Ettect on Salc Action Taken l Date Systce Ccmponent Nature' of Operation of Cause of Results of To Preclude ltaintenance The Renctor Malfunction Malf unc tion Recurrence l
'12/7/81 Fire U-3 auxiliary Smoke detec-None Un-determined, Did not receive a Performed Protec-instrument tor failed to during the annunciation for SI4.11. C,.16 5 tion room smoke annunciate in course of one zone detector and the detec-detector the control trouble shoot-tor operated 1
room during ing the prob-properly.
l the perform-Icm cleared TR #250681 j
ance of SI TR #200634 4.11.C.2 i
I L
(12/8/81 CRD Westside CRD The west side None, the unit
'During the CRD accumulator Insulated the accumlator monitor con-was tagged out performance of monitoring cir-accumulator monitoring tinually blow-for EMI 50 EMI 50 a scram cuitry was shorted Icvel switch circuitry ing fuse accumulator and blowing fuse wires, the l
1evel switch ground'c1 cared.U$
i wires were TR #280651 l
twisted and insulation broken i
i I
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112/8/81 CRD
'3A' CRD pump The breakef' None, the unit A closing The breaker would Replaced the feeder break-closing was in ref6cl-
. circuit diode not electrically shorted diode j
er closing circuit fuses
.ing outage was shorted close and the breaker i
circuitry were blowing
. operated properly.
TR #280650 1
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1 BROWNS FERRY NUCLEAR PIANT UNIT CSSC EOUIPME!;T MECllANICAL MAINTEIRNCE
SUMMARY
For the Month of December 19 81 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMFCNENT NATURE OF, OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFU!CTION MALFUNCTION RECURRENCE 81 Off-Gas A #1 Stack Pump doesn't
,None Copper line to Disch. press. too low Made new gasket &
Sample Pump Jevelop adeqt.
breather off installed line disch. press.
TR# 226876 I 81 HPCI Press. Contr.
Faulty diaphgm.
None Jorn diaphragm Bad diaphragn caused Replaced diaphragn Valve oil leak TR# 250671 82 IIPCI Valve 73-200-A Steam Leak None Jorn bonnet Packing leak Replaced bonnet 73-202A TR# 182348 8]
Core Spray HCV-75-551B rest valve None Jnknown Leakage Installed. cap Cooling Leaking TRO 318712
. 81 LPCI
.1EN MG Couping. needs None Leaking seals Seals leaking grease Aligned motor & gen.
- reasing Replaced seals &
N greased.
TR# 316279 d
s e
i i
? 'O t
t n
BROWUS FERRY NUCLEAR FIANT ITNIT 3
CSSC EQUIPMEitT MECHANICAL MAINTEFANCE SUIDIARY For the Month of December 19 81 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF.
OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION MALFU'ICTION RECURRENCE 81 RliR 3 FCV 74-75 Valve Stuck None Gear Broken Valve stuck 1/2 way Replaced gear open TR# 203741 I
l-8-81 D/G
!!1 Comp. 3-D Blown Casket None Unknown Blown gasket on llP Replaced head gasket, Diesel head valve and valveplate TR# 227774 81 LPCI 3EA MG Set Coupling None Lock Rings had Sheared coupling Installed new lock Sheared come out rings & lub. coupling TR# 203719 81 Rx. water FCV-69-2 llandwhee l None Unknown Sheared pin on Installed new motor clean-up broken handwheel pinion gear & hand-wheel gear and shaft TR9 203766 y
e 2-2-81 Ma in S t eam FCV-1-156,153, Check packing' None Warn O' rings Valves not functioningChanged 0' rings &
167 properly added packing TR# 316289 2-4-81 CRD llCV-83-600 Valve will not None Faulty bonnet &
Valve will not close Replaced bonnet &
Module 14-39 close stem off stem assembly.
,c Torqued bolts to 220 in/lbs.
TRf 280497 2-5-81 CRD Isolation Valve Leak None Worn Packing Valve Leaking I?cplaced packing Modules 54-31 TR# 232931 38-39 54-43 t
4 l
6 PWs t
t a
LKUWho 1 LiUsY NOCLLAR Ivarg %T_Of X.263 INSTRUMENT MAINTENANCE
SUMMARY
CSSC EOUIPME!.T FOR lilE MONIll 9F Dacember 19 81 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN 1 ATE SYSTDI CO:!PONENT OF OPEPATION OF OF RESULTS OF TO PRECLUDE MAIhTENANCE THE REACTOR MALFUNCTION MAIFUNCTION RECURRENCE nit 1 2-3 84 FT-84-7 Calibration None Instrument Drift False Indication Non,e a
2-13 65 TI-65-46 Replace None Random failure False Indication None nit 2 2-15 56 TR-56-2 Repair None Obsolete Recorder Loss of Record DCR In To Replace Recorders 2-29 3
LR-3-53 Repair Mone Random failure Invalid Alarm None nit 3 2-4 3
LIS-3-l'84 Replace Switches' None Done to Improve N/A U/A U
Reliability 2-5 3
LIS-3-185 Replace Switches None Done to Improve N/A N/A -
Reliability 2-6 3
LIS-3-56C Replace Switches None Done to Improve
.N/A N/A Reliability 2-7 3 ~
LIS-3-56A Replace Switches None Done to Improve N/A N/A sReliability 2-7 3
LIS-3-56D Replace Switches None Done to Improve N/A N/A Reliability 2-8 3
LIS-3-56B Replace Switches None Done to Improve N/A N/A Reliability 2-9 3
LIS-3-58A Replace Switches None Done to Improve N/A N/A Reliability 2-12 3
LITS-3-5dB Replace Switches None Done to Improve N/A N/A Reliability 2-12 3
LIS-3-58C Replacc Switches None Done to Improve, N/A N/A Reliability 2-14 3
LITS-3-58D Replace Switches None Done to Improve N/A N/A Reliability 2-16 3
LITS-3-62 Replace Switches None Done to Improve N/A N/A Reliability 2-18 3
LTTS-3-52 Replace Switches None Done to Improve N/A N/A Reliability i
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FIELD SERVICES
SUMMARY
December 1981 The major event during the month of December was the completion of security modifications required to be complete before January 2, 1982. This was completed when ECN P0488 and ECN P0500 were completed December 29, 1981.
A number of others were previously completed.
Through approximately 60 outage days the torus internal and external modifications were approximately 4 days behind the original 127 day schedule.
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Major work started in the month of December included vent header reinforcement, MSRV tailpipe routing, box beam installation, catwalk installation, downcomer e
cutting and bar installation and dummy ramshead installation. Torus. work on elevation 519 has been light this month.
Developments of larger growth rate cracks on spindle shrunk-on-wheels at other utilities have prompted the addition of UT inspections of the low pressure B and C spindles. The work to get A low pressure and the high pressure turbine back together has been expedited.
Other major modification work underway includes the generator breaker in-stallation which is, overall, approximately 45% complete, Unit Station Service Transformer installation (40%), security modifications on going (ECN P0289, ECN PO498, ECN PO487, ECN PO463), MSRV tailpipe tee (50%), and RHR and RHRSW modi-fications'. Loop II RHR maintenance and modification work was completed this month including replacement of the RHR pump motor seal heat exchanger and eddy current inspection and cleaning of 3B RHR heat exchanger.
A major effort is being made to complete valve maintenance on the main steam isolation valves (outboard) so that the maintenanace on the stop and by-f pass valves can begin in early January.
Approximately 125 of 150 leak rate test valves have been tested with radwaste, hydrogen and oxygen analyzer, and RWCU valves remaining to be tested.
The feedwater check valves and ventilation valves
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FIELD SERVICES LUMMARY (Continued)
December 1981 Quadrex continued to der.ontaminat9 scrap unit 1 torus steel this month, being approximately 75% complete. The removal of contamination has allowed
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about 90% of the steel to be sold as scrap with the remaining 10% going to radwaste. The operation is expected to be completed by the end of January 1982.
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ERRATA Replace page 21 with attached pages 21 and 21 A in the October report.
Replace page 16 with the attached page in the November report.
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l' NIT SliU11) OWNS AND POWER REI)t$TIONs DOCKET 40. 259 UNIT NAME ___ B rowns Fc rry -1 DATE
_l..l.- 8 2 REPOR T MONTli October COMPLETE D !!Y Ted Thom TELLPHONL ;_203 779 6846 I u..:
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Report :
EC 5 '*
Present Reci trence c
- i 172 10-01-81 S
3.27 C
2 Refuel outage continues (EOC-4) 173 10-01-81 S
0.15 B
Turbine overspeed trip test (no scram) w
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173A 10-01-81 F
6.08 A
3 Reactor scram when MSIVs isolated on low pressure during turbine overspeed trip test.
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1 l'or ej R ea >on Method:
lah. bit G. Instinctio.is s
S k hei!nieil A i quipment Failore tI splaini
! 4tanual tor Prcras.ition i t Data Italaintenance i.r Test Mlanual Scr ain.
Entry Sheets tbr i : cosee C.Reinehng 3.Autoin.itic Siram.
laent Report t 1.1 R) i ile iNL R1 G.
D&. :ulat.us Resis is tnin 4-Other t I spl.un 1 01 ts i i
! -0;'eial r li.nnin;: A 1.isense I s:tuunation
! TJinir.nt.a:t.c (cuperational I inn il sp' nni i sinbu I. S.nne S.uts e to!77)
Il-Other Ii splanin i
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16 OPE!!ATING DATA REFOftT DOCKET NO, 50-260 DAIF 12-I.8T-C05fPLETED ity Ted Thom T El.EPil0NE
05_129._6846
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._W OPER ATING STATUS i
- 1. Unit Name:
3ro m Fern - 2
- Note' November 1981 2 Reporting PerioJ:
j 3293
- 3. Licen>ed Thermal Power (Mht):.1152 i
- 4. Naa:cplate Riting (Gross.\\lWeJ:
1065
- 5. Design Electrical 1: sting (Net MWe):
l
- 6. Stasimum Dependable Capacity (Gross MWe): 1098.4 1065 7 Masijuum DependJhIe Capacity (Net MWe).
If Changes Occur in Capacity Ratin;:s (Items Number 3 Through 7) Since L.nl lleport. Giie Reasunc x
UA NA
- 9. Power Lesello Which Restricted. lf Any (ANet MWe).
N
- 10. Re.nons For Restrictions,if Any:
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.1 This Month Yr. to.D:te Cumul..ris e i1. llours in Reposting Period 720 8,016 59,239, _
- 12. Number Of Hours Reactor was Critical 720 7.022.05
'G,165. 6 6_ _
- 13. Reaitor Rewne Shutdown llour, 0
965.58 13,419.06
- 14. Ilours Generator On Line 720 6,774.83 36,5M.79
- 15. Unit Resene Shutdown ilour, 0
__0 0
It.. Grow Thermal Energy Generated (Sihlt) 2,255,743 20,900',821 104,471264_
17 Grow E!cetrie.il Energy Generated (MWill 759,97,0 6.960,380 34,697,5_68 IS
.N c Electrical Energy GeneratcJ f Mh!!)
738,451
_6,755,754 33,706,061
- 19. Unit Seniec factor 100 84.5 61.6
- 20. Unit Asailainlity ractor 100 84.5 61.6 21 Unit Calueity Factor IUsing MDC Net)
__ 96.3 79.1 53.4 2.'
Unit Cap. scil 3 Factor IUsing DTR Nell 96.3 79.1 53.4 23 Unit Forced 0: stage Rate 0
9.8 29.5
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2-3 Shuidowns Scheduled Os er Nest 6 Months (Ty pe. Date.and l>uratum of I ach t 25 !! Shot Dowa At End Of Report Period. Estimated Darc of Startup-2 r.
1; nits in lest Status IPrior to Commerei:.1 Operations; f.uccast Achermi
- , INillA L CRITICA t lI Y q
IN!!! A L El.! C I RICITY CO\\l\\lERCI \\L OPER AIlON 6 J g
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