ML20136G894
| ML20136G894 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/1985 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8601080642 | |
| Download: ML20136G894 (33) | |
Text
4 o,
a TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION October 1, 1985 - October 31, 1985 i
UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:
W g
P. R. Wallace, Plant Manager 8601000642 951031 PDR ADOCK 05000327-R PDR JE 21
e 9
f TABLE OF CONTENTS I.
Operational Summary Page Performance Summary 1
Significant Operational Events 1-2 Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 3
Licensee Events, Special Reports and 3
Diesel Generator Failure Reports 4
Offsite Dose Calculation Manual Changes 4
II.
Operating Statistics A.
NRC Reports Operating Data Reports 5-6 Unit Shutdowns and Power Reductons 7-8 Average Daily Unit Power Level 9-10 B.
TVA Reports Nuclear Plant Operating Statistics (October 1985) 11 Unit Outage and Availability 12-13 Reactor Histograms 14 III. Maintenance Summary Electrical Maintenance 15-21 Instrument Maintenance 22-24 Mechanical Maintenance 25 Modifications 26-30 a
6 O
e Operations Summary October 1985 The following summary describes the significant operational activities for the month of October.
In support of this summary, a chronological
~
log of significant events is included in this report.
Unit 1 The unit remained in the cycle three refueling / modification outage the entire month. The present schedule has the unit prepared to enter mode 4 on January 1, 1986. Actual start-up is dependent upon NRC review of concerns identified in the September 17, 1985, letter from William J. Dircks (NRC) to Charles Dean (TVA). The unit has been off-line for 71 days.
Unit 2 The unit remained in the administrative shutdown the entire month due to documentation concerns relating to the environmental qualification of various electrical equipment (NUREG 0588). Outage related maintenance and modifications are being performed. The present schedule has the unit prepared to enter mode 4 on December 9, 1985. Actual start-up is dependent upon NRC review of concerns identified in the September 17, 1985, letter from William J. Dircks (NRC) to Charles Dean (TVA). The unit has been off-line 72 days.
Significant Operational Events Unit 1 Date Time Event 10/01/85 0000 The reactor was in mode 5.
Cycle 3 refueling /modificatica outage continued.
10/18/85 0200 The reactor entered mode 6.
10/23/85 2030 Began core off-load.
10/27/85 1015 Core off-load was completed.
10/31/85 2400 The reactor was in mode 6.
The core is empty and the insert shuffle is complete.
Reloading of the core is delayed due to a RHR outage. Modification and outage related
. maintenance activities continue.
W I
e Significant Operational Events (cont.)
o e
Unit 2 Date Time Event 10/01/85 0000 The reactor was in mode 5.
The administrative shutdown due to NUREG 0588 concerns continued.
10/31/85 2400 The reactor was in mode 5.
The administrative shutdown due to NUREG 0588 concern continues.
Fuel Performance Unit 1 The core average fuel exposure accumulated during October was 0.00 MWD /MTU.
On October 23, 1985, at 2059 CST, the Cycle 3 refueling process commenced by off-loading the core. The off-load was completed on October 27, 1985, at 1039 CST. The prescribed process includes a total core off-load (193 assemblies),
a fuel insert shuffle, and a total core reload. As of October 31, 1985, 2359 CST, the core off-load and shuffle have been completed.
On October 27, 1985, at 1340 CST, all new fuel (Cycle 4, 72 assemblies) was transferred from the new fuel storage vault into the spent fuel pit.
The process was completed on October 29, 1985, at 1126 CST. The transfer was structured so that the fuel was aligned in approximate order in which it will be loaded into the core.
Per TI-1, an inventory was conducted of the new fuel storage vault immediately following the last movement of Region F fuel assembly.
In addition to the refueling, an onsite removal (shipment later) of an irradiated material surveillance specimen from the reactor vessel was conducted on October 28, 1985, at 1300 CST and temporarily stored in the spent fuel pit to determine the change in material properties recognized by 10CFR50 Appendix H as specified in technical specifications. The results of these examinations shall be used to update the pressure-temperature limit curves in the technical specifications.
Unit 2 The core average fuel exposure accumulated during October was 0.00 MWD /MTU with the total accumulated core average fuel exposure of 8097.51. MWD /MTU.
A conference call meeting occurred on September 23, 1985, between TVA (Nuclear Fuel Branch and Sequoyah) and Westinghouse to tentatively establish a Unit 2 (Cycle 4) fuel delivery schedule. All parties have agreed to commence fuel receipt on February 4,1986, and ending on March 16, 1986.
)
o F
2
Spent Fuel Pit Storage Capabilities The total storage capability in the spent fuel pit (SFP) is 1386. However, there are five cell lccations which are not capable of storing spent fuel.
Four locations (A10, All, A24, A25) are unavailable due to a suction strainer conflict and one location (A16) is unavailable due to an instrumentation conflict.
Presently, there is a total of 348 spent fuel bundles stored in the SFP.
- Thus, the remaining storage capacity is 1,033.
NOTE: Since Unit 1 is in a refueling outage, as of October 31, 1985, 2359 CST, the spent fuel pit temporarily contains an additional 193 fuel bundles which will be transferred later back to the core.
Spent Burnable Poison Inserts On October 16, 1985, at 1710 CST, 52 spent burnable poison assemblies were transferred from a temporary storage area (BP plates) to permanent storage in spent Unit I and Unit 2 fuel assemblies. This transfer, entirely in the spent fuel pit, was made in order-to create additional space for future spent fuel. The movement was completed on October 18, 1985, at 0911 CST. Ten temporary BP plates remained in the spent fuel pit for any potential use.
The rest of the BP plates were removed from the spent fuel pit to the cask loading area. These remaining ten plates are located in an area which will cause no impact regarding future refueling plans.
PORVs and Safety Valves Summary No PORVs or safety valves were challenged in October 1985.
Licensee Events and Special Reports The following licensee event report (LER) was reported to the Nuclear Regulatory Commission in October 1985.
LER DESCRIPTION OF EVENT 1-85038 At 2245C, September 8, 1985, with both units in mode 5, an auxiliary building ventilation isolation (ABI) occurred due to a spike on spent fuel pool (SFP) radiation monitor 0-RM-90-102.
The spike occurred while the SFP filter was out of service for a filter 'changeout causing the radio-activity level to increase due to increased contaminants in the water.
Special Reports The following special report was transmitted to NRC in October 1985.
85-07 Fire door A-131, the unit 2 vent and purge air room door on elevation 714 of the auxiliary building, was breached from 1000C September 22, 1985, until 0830C on October 4, 1985. The door was breached to route an air hose for the performance of surveillance instruction (SI)-138 (Containment Spray - Spray Nozzle Test). While the door was breached, fire detectors were operable and an hourly fire watch was performed.
I e
3
Diesel Generator Failure Report There were no diesel generator failure reports transmitted during the month.
Offsite Dose Calculation Manual Changes No changes were made to the Sequoyah Offsite Dose Calculation Manual during the month.
e e
4
~
OPERATING DA.1A REPORT DOCKET NO. 50-327 DATE NOVEMI!ER 1, 1985 COMPLETEU BY D.C.DUPRLE TELEPHONE (615)870-6544 OPERATING STATUS 1.
UNIT NAME: SEQUOYAH NUCLEAR PLANf, UNIT-1 NUTES:
2.
REPORT PERIOD: OCTOBER 1985 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (GROSS MWE):
1220.6 5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 6.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1183.O 7.
MAXIMUM DEPENDADLE CAPACITY (NET MWE):
1148.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:_______ ____
9.
POWER LEVEL TO WHICH REGTRICfED,IF ANY(NET MWE):___.______
- 10. REASONS FOR RESTRICTIONS,IF ANY:_.___._.______.__.____ ___.__
THIS MONTH YR.-TO-DATE CUMULATlVE
- 11. HOURG IN REPORTING PERIOD 745.00 7296.00 38017.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 3797.25 24444.91
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.'00 O.00 O.00
- 14. HOURS GENERATOR ON-LINE O.00 3762.18 23871.13
- 15. UNIT REGERVE SHUTDOWN HOURS 0.00 O.00 O.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 12383285.96 77060971.91
- 17. GROSG ELECTRICAL ENERGY OEN. (MWH)
O.00 4239970.00
'3976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-1479.00 4063636.00 9 945266.00 190 UNIT SERVICE FACTOR O.00 51.36 62.79
- 20. UNIT AVAILABILITY FACTOR O.00 51.56 62.79
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 43.52 57.16
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00
- 23. UNIT FORCED OUTAGE RATE O.On 48.52 57.16 12.38 17.45
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
, ?5. IF SilllTDOWN AT END OF REPORf PERIUO, FSTIMATED nATE nF
-P'. A - 'I tp :
_.. January _1986,.pending.NRC_ revie.w of Sequoyah__tjuclear Vlant, OperjMial Readiness Plan NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE BEEN iIPDATED.
l l
9 5
' 5 K
mi d
,(
e 4,
4 d
Pf
I I
UNIT SIRITDOWNS AND POWER REDUCTIONS -
DOCKET NO.
50-327 UNIT NAME Seanoynh one
~
DATE ti_i_ns COMPLETED BY
- n. c niinron REPORT HONTl! October 1985 TELEPHONE (6i si n7n-6 544 l
m u
,1 C4 5%
"o SU j $,E Report #
y gg Prevent Recurrence No*
Date
.a 3 $
Event o4 g 4-Action to y
YC N
NEc 8
A
- c m g A
i 6
850822 745
'C 4
Refueling outage continues g
J i
i
~
d 1
2 3
4
}
F: Forced Reason:
Method:
Exhibit G-Instructions I
S:' Scheduled A-Equipment Failure (Explain) 1-flanual for Preparation of Data B-!!ai:ntenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction
'4-Cont..of Existing 0161) j E-Operator Training & License Examination Outage 4
F-Administrative 5-Reduction
)
G-Operational Error (Explain) 9-Other 5
(9/77)
H-Other (Explain)
Exhibit I-Same Source 1
AVERAGE DAILY UNIT POWER LEVEL
~
- DOCKET NO.
sn-177
~
UNIT 1
s 4
i DATE 11-1-R9 C0h!PLETED BY D.
C. Dupree
~
IILEPil0NE (615) 870- 6544 i.
I 1
MONTH OCTOBER
' !sj,.* ] ' h., ' i c
..d.; -
n-CD. l! ' DAY ~ ' AVERAGE DAILY POWER LEVEL
- DAY AVERACE DAILY POWER LEVEL
. (MWe-Net) -
OfWe Net) 0 0
s
-- 17 0
2' 0
33 l
3 n
,39 0
s 4
0 0
20 5
0 0
2g l
- 6 0
0 3
0-7 u
o 8
0 u
o 9
0 25 O
10 0
0 26 11 0
0
.,7 12 0
23 0
13 0
0 29
..0 10 14'
~
15 '
O O
31 1
16' O
INSTRUCTIONS 1 rm3t. lis he a erage daily unit power levelin MWe. Net for each day in the reporting ir.onth. Compute to i
D
~
7 1
8 e
OPERATING DATA REPORT DOCKET NO. 50-323 DATE NOVEMBER 1,
1985 COMPLElED BY D.~C.
DUPfiEE TELEPHONE (615)870-6544
-OPERATING STA1US 1.
UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT - 2 NOTES:
2.
REPORT PERIOD: OCTOBER 1985 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (CROSS MWE):
1220.6 5.
DES]GN ELECTRICAL RATING (NET MWE):
1148.O 6.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
1133.0 7.
MAXIMLIM DEPENDADLE CAPACITY (NET MWE):
1148.O 8.
IF CHANCES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, G I VE R E ASONS :.___.__._ __ ___ __
_ _. _ _. _. _. _ -. ~
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):._________-
. _ - _ _.. _ _ _. ~ -. _. - _. _. _. _ _ _ _ _ _ _ _ _ _. _ _ _
- 10. REASONS FOR RESTRICTIONS,IF ANY:._._
.__.-_._-_. _ _.__._.---_.~ _._.__ --_.___
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 745.00 7296.00 29977.00 12., NUMBER OF HOURS REACTOR WAS CRITICAL O.00 5289.42 21984.54 13.' REACTOR RESERVE SHUTDOWN HOURS 0.00 O.00 O.00 14 HOURS GENERATOR ON-LINE O.00 5224.24 21494.42
- 15. UNIT RESERVE SHUFDOWN HOURS 0.00 O.00 O.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 17128966.35 69127977.22
- 17. GROSS ELECTRICAL ENEfiGY GEN. (MWH)
O.00 5345S49.00 23337229.00
'. 3. NET ELECTRICAL ENERGY GENERATED (MWH)
-3743.00 5618509.00 22639597.60
- 19. UNIT SERVICE FACTOR O.00 71.60
- 71. '/O
- 20. UNIT AVAILABILITY FACTOR O.00 71.60 71.70
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 67.03 65.79
- 12. UNIT CAPACITY FACTCR(USING DER NET) 0.00 67.08 65.79
- 23. UNIT FORCED OUfAGE RAIE 100.00 23,34 14.32
~
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DA1F, AND DURATION OF EACH):
.5.
IF SHUTDOWN AT END C:- REPOR'1 PERIOD, ESTIMATED DATE OF STARTUP:
January _1986, pending.NRC review oL Sequoyah. Nuclear. Rant _ Operation _aLReadiness "lan, NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE I<EEN I!PDATED.
5 Y
8 r
_n w$
4 4
Vp.
1-s.
Q
$g
.geg y
t l
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-328 UNIT NA!IE Sequoyah Two DATE 11-1-85 COMPLETED BY D.
C.
Dupree REPORT !!ONT1! October 1985 TELEPHONE (615) 870-6.544'
~
mu u
MO
- "8""
En Cause & Conective C^
O No*
Date E4
~
OE E
yj g Event o.g g.g-Act. ion to e
.R tj S E
,8 if y Report #
Qe ge Prevent Recurrence H
w :=
c u :s m
o 5"
$d5 8
9 850821 F
745 D
4 NUREG 0588 Documentation Concerns 1
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1 -!!a nua l for Preparation of Data B-!!aintenance or Test 2-Manual Scram.
Entry Sheets'for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction C-Operational Error (Explain) 9-Other 5
(9/77)
' !!-Other (Explain)
Exhibit I-Same Source 9
i
=.
J.
AVERACC DAILY UNIT POWER LEVEL DOCKET NO.
50-328 2
UNIT g
DAR 11-1-85
~
l CO.KPLETED BY D. C. Dimree (615) 8 70-6544 I-TELEP110NE i.
MONIll OCTOBER
~
'lh[ ' DA
' AVERACE DAILY POWER LEVEL
-DAh AVERACE DAILY POWER LEVEL
. (MWe-Net)
(MWe Net)
I n
_, 17 0
2 n
13 0
3 0
,39 0
4 0
20 0
5 0
0 21 6
0 0
3 7
0 0
3 8
0 0
l y
9 0
33 O
10 n
26 0
II O
27 o
12 0
23 0
13 0
29 0
.0 14
' 30 0
IS 0
3g o
16 0
INSTRUCTIONS
~
~
On this format, list the sverage daily unit power leye!in MWe Net for each day in the reporting the r.carest whcte megawatt.
9
.a
~%
10
~
e a
r.,.e..
2
- + -. >. '
1
,rva nsaa torw+ati NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant Period Hours Month 19 ltem No.
Unit No.
UNIT ONE UNIT 'lHO PLANT I
Averaoe Hourly Gross Load. kW 0
0 0
2 Maximum Hour Net Generation, MWh 0
0 0
3 Core Thermal Energy Gen. GWD (t)2 0
0 0
4 Steam Gen. Thermal Energy Gen., GWD (t)2 0
0 0
5 5
Gross Electrical Gen., MWh 0
0 0
j 6
Station Use, MWh 1479 3743 5222 E
7 Net Electrical Gen., MWh
-1479
-3743
-5222 8
Station Use, Percent N/A N/A N/A i
N/A*
8098 8098 9
Accum. Core Avg. Exposure, MWD / Ton 6
10 CTEG This Month,10 BTU 0
0 0
11 SGTEG This Month, IC6 BTU 0
0 0
12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use. Hours. Min.
0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 y
16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 5
0 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 h
19' Reactor Avail. Factor. Percent 0.0 0.0 0.0 u.
20 Unit Avail. Factor. Percent O.0 0.0 0.0 21 Turbine Startuos 0.0 0.0 0.0 22 Reactor Cold Startuns 0
0 0
23 g
24 Gross Heat Rate, Btu /kWh N/A N/A N/A j
25 Net Hea* Rate, Btu /kWh N/A N/A N/A 5
26 D
27 g
28 Throttle Pressure, psig N/A N/A N/A d-29 Throttle Temperature. F N/A N/A N/A
',8 30 Exhaust Pressure, inHg Abs.
N/A N/A N/A E
31 Intake water Temp., *F N/A N/A N/A l-32 33 Main Feedwater, M lb/hr N/A N/A N/A i
34
[
35 36 37 Full Power Capacity, EFPD N/A*
363.65 363.65 38 Accum. Cycle Full Power Days, EFPD N/A*
210.8416 210.8416 j
39 Oil Fired for Generation, Gallons 14,322 2
40 Oil Heatino Value. Btu / Gal.
138.000 41 Diese.1 Generation. MWh 217 4?
Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
3 43 N/A N/A N/A N/A N/A N/A o
Remarks: IFer brNP tt.is value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.
(
8 2(t) indicates Thermal Energy.
I 5
- Lnit one off-loaded, refueling in progress.
l Oi l
Date Submitted Date Revised Plant Superintendent u
~.. -.
c.
. _ +,
--a u,
)
i t
t
' e n
I Z-9:
w u>Z
<$9_
I e
u
= =.
>.~
CZJ l
S_e:t I
t I
u e
=
. t I
t n
1 e
i j
I l
"1J ii' l
i l al.
!j
, i f
a f
t.h 0 N r_
3 2 +<
l
.d l
x e
4 i
E 5 Z(Zm J
N d U$h t
q 1l l
f kl b'
w I}
co c Ez zo
- h. n - <
4 U
N a
1 2:
C *3 I h!
1 l
s I
e
'. j a
y
[.
W m
i u
u
)
s c
I 9
U W
> 4 o
e t.s y
a y o
h 3
.Z ec
- 1 t
4 0
f 3
W Q
v Z
C W
.I e
,s 4
,/ -
c.
g o
Z N
f E
D E c
3 O %
3 gg 3
.t c;
- o
/s a
I a
y; 3
o 8 o Ceo O
.c.g u.8 o o e O o of e o CC gCL. 8 o e o 60 0
=.e eo cssss.e s sem e
esse v= a i r 4
4 4 4 4
4 4
4 e
4 4
4 4
4 4
4 4
444 4
4 e
a A
N N ce N NeN N
NN N
N N Ne4N N
NsN N
N NNN N
e4 4l m w.s4 4 NN e4 ed NN N 2
3 g
..o.
8 C. e. o..c..o
. l o_. b.4.o.......ot b8
....o. o. 8 b..
.of
- b...8
+
g e
E o 4 4 4o 44 44 4
4 4
4 4
4 4
4 44 4
4 4
4 44 m o 4 4 e
.(
N N eeN NNN NN N
P4 N
N N
N N
P4 N
N N
N N
NN N
ed 64 e4N N 4
h, Yo S o o o c o o C o c o o oo o o c o o C Oo o o g
g
....o..C..__.C..o_.c o...q o.o_.CC. o_c..o..o..o.o o.. o_o d* C f.I.
.o o C o c o oo
<.< <.s a n e r
.r.r a r
.r.t
.r.e < < <
< < m e
l f N NNN ee NN N
N N
N N
N N
N N( N NN N
N N %NN N ef N[ f 4N 4 I
el s
g s c o o o c o o ol po o c o o o c o 6 8 o c o c a8 o oo o o o o o o o 8c o o
3,.s c o c o c o c o o o o o o o e c a c
gn 4 4 < < < < <<
< < < < < < < <m e n
< e n
s.
_r-m N
NN N
N NN N
N N
N N
N Pf N s
N Nt N N N
NN N
N N
N N
N N
e9et 4 c.
e
=
s 3
2 s
o a
a z
a E F q
^
A 3 i j
f 8co do d
- g y
.g.s.8 8e e c o c o o oo e
ooo o
.oo 88 c.
m e
.c.o..c.
.c..c_o__c_c..o_
c.oc.._.o.
8g E_
6 g
_ e oc..a c-o,n c o c_.o p
N gg g g
e c o e c o ele o
N e
o e
o 0 0 o
cic c o c c o e
. ci c c c c o o,g ge c
g q cio c o e c i
E
.?
E 5
3 8
S ele 3
~
ei e eo o e o e o e e o g e o e o e o o e o a8 g - m i s o c c'g_,
y.__ _
_ _oc...
...y._ _o
_..g
...c_o.
c o c c o i
c c o o o o o o c c i ~
E E8 8 8 8 8 88 8 8 8 8 8 8 o88 8 8 8 88 8 8 o88 8 8 8 83 8 x
o z o 3
1 t
e 5
e c
> -wm
, o e N e e o m m m m
-- e e N e m o 3
3 m m 308 g
e o e N e e e n ~ ~~
~ ~ ~~m m- ;;
e
. 3.
a
~
O f
4 e
=-
c:
.i i
b$z l
l
!)
<WE i
i i
i-j5C l
I I
i
-e
+
i li
,i li i
vs r,
x 3
l l
W "E'
I !l lf
'l f,I 3
t t
b 0
55 I
t l
- ,ilI i
.i,
!<l i
i li e
~
v 2
b
+
l i
}
Z<s<f t
1 i'; i;j-
=
5 l
= ;
li
'GEsp ll!,l
,I ll
'p 5 e F,
l' l
l i
L,.
c*Zo I-!
cv e 0: 2C <
- 25$ 1 i
53
=
l
[\\
l u
m 5
E y
c 3
y V
f 0
t 2
u J
W 5 I i
g lI O
i J
8 fI 2
t 8
c o
E E
5 l- -.._
_ /
w Ec C =
.S i:
e a <
m
- e e
a 3 5 c
3 m
e
.O e
3 3
I
_ L(
3
_ d
- f e
z I
y 1
I n
T 2
. _ _o.. q. _o,_j _
g_n_ey n. q _td n y a n d n,=, _n kgbi:
p O
y @ -.13-i r..C C
oe
_-.C_
e 3
- :,x d ;~
e4 c, n g
- r. n ddd.,_ed8_1g=tdaad,s,_dde8 add.q_d_d88 @ eg m8 a
s, !, _58 8
_3 g.._8
.1.L_._
~ A g _ tet_.
1-.
c r..
j ej e,d
(
e4 e4 e4 ea e4 cal ci N e4 e4 e c4 e e4 ed e4 q c4 e4 NN f4 fa Np ejm g e4 i
c o ci e eldddo el ei d d e ~
e d a d a d o cc e ceo d es e c
a 6; j _3.
o ci c q 'lc
.j _]O ooo$oa
_.ag_ 4j_ __..q c4ci bcqCcop _;_
_ ;. 4 _
..q o o o oo Q Os o I
- iiW 9fHnq 14f n1 t991998:P f 4: E i
t
_ l _:_ L.'d 8 S Eph _'I.Ef 8 8!8 o ?
8 8
.j_
..... a _i_ LT"} 8
- n qn.q:;: : g.l'J_'l J_b'8 88 8 8 "..
8c s
a 8cp q8 8
_f a
_i_ L na.n.n,n a-.
e< t e q : n n, a,, da..
- i: ~:
2 5
$ 5 l
l l
l l
s 4_
C p
_i 2
i s
ooddoodddoodd doe dado e eb do e
8e qooooQQoccoqQh8cqcoqqo=6 e
c c
2 C
c o ce q0 e
t f
_.3 3
je-
> q _e _i_ h 4 a _ L v. 4_ - 4. + 4
_ L 4.
4_
..J _
2 C:
I r
'1
- 9docoac4N9d edo g d d d d e odddooco
_...p.. q _
N t o o c e ce e 9 "1
,9999 9 9 9 c' :'
r 9=
i
- ? I J
E 3
o*eielo c o 8 8 a d o o e c'c el doc d o o o oe ie eceloc u
i s oc e
qoqqa 4 _i_ h. 4 4 4_l_q q+q c e
c oqc q q o ac c ccc o
j s
_pla Ej a 85 8'9 8 Ej a q E E
_ 4.. 4.J _ L. A. J. J., _LLij__.
si 4_
i
~ I j,
~ ! 8;8 E E E 8 59 El8888 888'88 8 2
s e
E ! 7
- * * * * *
- 2 CS C Z f f 2 3
- R E U E R R E R R$
~
3 2
3 J d 3
SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -
90 -
g 80 -
W 70 -
E 60 -
b 3
50 -
O 40 -
go O
30 -
6 m
20 -
10 -
0-
-10 g
O 4
8 12 16 20 24 28 32 OCTOBER 1985 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -
80 -
N 70 -
I
.0 6
60 -
4 i
y 50 -
a 40 -
x0 30 -
O j
h 20 -
10 -
0 --
l 3
I I
3 3
3 3
3 I
g g
g g
g g
0 4
8 12 16 20 24 28 32 l
OCTOBER 1985 a
14
k 12:31:27 11-04-65 ELECTRICAL MAltHEt1AllCE (10ilTHLY REPORT FOR OCTOCER PAGE 1 DATE....
CCMP0 t;EN T.....
FAlllME DESCRIPTIDH......
CAUSE OF FAILURE.........
CCRRECTIVE ACTION........
MR. tiO..
~
08--16-85 2-CEMB-087-000 2A-A DIEGEL CEHER/. TOR DIRTY 2A1 COVERNGR CLEANED 2A1 GOVERNOR A534055
~
1/i-A UGULD t!OT LOAD TO OVER COMMECTOR (dD HYDRAULIC COMMECTOR AfD (DJUSTED 4200 L'U, LGADl!!C~ SLOULY GCVEP,NGR DROOP AND SPEED HYDRAULIC COVERHCR DROCP EETTItlG UAG OUT UF AND SPEED SEFTINGS ADJUSTMEllr 08-28-85 2-3 RR C-099-k H/
LKE/EER UtillD HOT CLOSE C0tlIROL FUSES UERE 01RTY, CLEAHED CONTACIS ON AS43032 319 Ff,Uil ELECTRICAL THE LOCKHUT Otl PLUG UAS CONTROL FUSES AllD PUSHUUITON GROKEH AND IllSULAT1HG REFLACED BROKEH LIlfX Oli BRE/EER UAS ELECTRICAL PLUG, REPLACED CHIPPED CHIPPED IhSULATING LIHX ON BREAKER (JD PERFORMED MI-6.20,MI-10.9,6.1.1 -
7.2 09-01-03 2--XFD-313-Y10 REPAIR FIRE DAMPER ON U2 Orb THERMAL LIttX REPLI.CED ELECIRO THERMAL A533955 4009 ShulD0Gli EDARD R11 LINK AND LUGS 2Al-A 09-01-05 2 M D-313-YO7 REPAIR Flf E Di.hhR BAD THERNAL LINK REPLACED ELECTRO THiRUAL A542182 LINK AND LUGS 09-03-85 1-CD48-032-000 UGGDUARD GOVCRh0R C.T.
UMHNCUM REPLACED LUG AHD A539555 18-B UIRIi40 HAD A BROKEri LUG RETERMINATED UIRING PER ON CONDUCTOR MSAI-7 Al10 MI-6.20 09-03-85 1-GEN 8-082-000 REPAIR DIESEL CENERAlDN PCCDABLY CAUSED BY DIRT REPLACED DEFECIIVE INTER A518232 IB-B 18-C EXCITER CUa1CLE AtID ACCUhULATION PANEL UIRIt4G, REPLACE 0 REPLACE DEFECTIVE TUO SUTURABLE REACTORS COMPOWNTS AllD REPLACED PARTS DAMACED ON CT1 AND CT2 1
i 09-08-05
?-XS-013-133 DETECTCR HAD PICKED UP DETECTOR XS-13-161H UAS REPLACED DETECTOR A534180 FOR 1;0 APP /SENI REASOH DAD XS-13-161H (J4D CHEC'dD AND UCULD t!DT CLEAR FOR PROPER OPERATION PER i
e i
j 15 t
O 12:31:27 11-04-85 ELECTRICAL I air 4TEl4N4CE flG4THLY REPORT FOR OCI0BER PAGE 2 DATE....
CCMP0l4ENT.....
FAILURE DESCRIP TION......
CAUSE OF FAILURE.........
CORRECTIVE ACTION........
MR. HO..
~
SI 234.2 STD' 7.3 AfD MI 6.20 09-08-65 0-LCCL-013-061 DETECTOR XS-13-164U UGULD BAO DETECTOR REPLACED DETECIOR A529873 0
liOT PICK llP SICHAL XS-13-164U ZONE 144 AND CHECKED FOR PROPEP, OPERATION 09-18 2-HS-062-014GA IIANDSUITCH ELOUS R-58 SLRtu HAD FALLEN ON10 REMOVED SCRBI AND A534227 FUSE UhEN DPERATLD TO THE RELAY riUXI CAUSING RETURNED TO SERVICE Otl POSITIO;4 C0;4 FACTS TO SHORT OUT 09-21-05 0-L CC L-013-P31 PANEL TROUCLE Alieri UGULD BAD THERtlAL DETECTOR N40 INSTALLED I?EU THERMAL A548962 NOT CLFAR CONTROL nGOULE DETECTOR AtID ZA30 CONTROL r100ULE.N4D GlECKED FOR PROPER OPERATIDH 09-22-65 1-LS-040-00700 LEVEL SUITCH UAS NOT LEVEL SUITCH UAS BAD 0:1 REPALCED LOW LEVEL SUIfCH A536852 B
SHUTTIt4G PUitP OFF UhEH PunP D ON PUMP D LEVEL IS LOW 10-04-85 0-FCV-026-0183 DELUGE Vf.LVE UGULD NOT 140 CONTROL FUSES K15 A!!D REPALCED FUSES AND Plc.CED A536429 ACTUATE Uititi TESTED FROM K16 IN 1-R-79 JUMPER ACROSS AUX (10 AUI PYROTR014ICS PA:EL TERMINALS AT Pt4L-0-L-612,0-FCV 123 10-05-83 C-CRil-303-AB TRAVEL INTERLOCK C0ll BURMED UP REPLACED BURED COIL A543859 SUITCH(S) BURNED UHILE USING MI 6.20 A!4D SI-104 CPERATING CCANE.
10-06-85 0-M TR B-040-000 SUf1P PunP 8 IS SlOPP1tiG DIRT IH JUNCTION GOX AND CLEAT 4ED JUtiCTIOH BOX (J;0 A534662 1B BEF0hE THE LEVEL IS LEVEL EllITCHES LEVEL SUITCRS AND PUNPED DCUH BELOW THE LOW CLEARED GR0l140 OH COHIROL LEVEL TRIP VALVE CIRCUIT 10-06-85 0-PMP-040-0001 Sutip PUMP A 1 RIPS THE DIRTY LEVEL SUITCH (J40 CLEANED LEVEL SUITCHES A534661 a
16 1-
12:31:27 11-04-83 ELECTRIC /L MAINTE14ANCE f10lTilLY REPORT FOR OCTOSER PAGE 3 DA1E....
CDMP0HE11T.....
FAILURE CEECF IPTION......
CAUSE OF FAILURE.........
CORRECTIVE ACTI0tl........
MR. NO.,
A f3REiA W AFTER 1 TU 1.5 GEGUND ON CONTROL CIRCUIT At0 CLEARED GROUND Gl MIHUIES OF CPERA1104 CONTROL CIRCUIT 10-06-05 0-MTR S-040-007 REPAIR OR REPL6CE ERCU PUND MOTORS UERE DAD DISCONNECTED ND ret 0VED A121943 10 SUUP PUllPS IN StD 20-0 PUt1PS REPLACED PUMP MOTORS A 10 PER M&AI-7, 4
CLEANED LEVEL SUITCIES NiD PUMP C0tHROLS PER MI-6.20 AND CIECKED FOR PROPER OPERATION 10-08-85 2-XS-013-0203 SMOKE DElECTOR /LARl1 DID EUCKE DETECIOR HEADS UERE REPLACED SMOKE DETECTOR A529897 NOT C0 GFF UHILE DEFECTIVE HEADS AfD PERFUld1ED SI PERFORMING SI 234.7 234.7 ON 2.0fE 375 i
10-15-05 2-RM-090-01008 BOTH RADIATION fl0MITOR MOTORS BURilED UP REPLACED D-3.70 OVERLOA3 A289327 MOTORS OR PlWS UERE HEATER IN 480V MANUAL BURMED UP STARTER AtID REPL ACED t10 TOR ON lli Pt41P 10-15-SS 1-HIPA-082-000 LGU JACKEl n0 TOR TEMP CONTRCL CIRCUIT FUGE
' REh0VED FUSE N4D AS46187 18/4-8 ALAh!1 IS Ill 6!!D WILL tiOT LOOCE TICHTENED FtGE 110LDER AND RESET REINSTALLED FtM 10-15-85 1-H fR A-082-000
" LOU JACKET UATER lEMP" CONTROL CIRCUIT FUSE REMOVED FUSE AlD A546187 18 /4-8 ALARM UGULD NOT RESE1 DUE LOOSE TIGHTENED FUSE HOL9ER TO IMMERSIGH HEATER HOT THEN REIL 4STAiLED FUSE CPERATIMG 10-15-05 1-hV0P-067-005 LIrllTS SHOUING EDfH RED LIMITS UERE OUT CF A0 JUSTED LIMITS #4D A536007 3
AHD GREET 1 AT 1-h3 o7-65A ADJUSTMEt4T CilECKED FOR PROPER 1
011 0-fi-27A OPERATI0tl.
10-17-85 1-H1CK-234-011 HEAT TRACE circuli 117P LODSE TEMPERATURE TIGHTENED LOOGE A543396 79 DID HOT ENERGIZE.LilLE C0i1TRCLLER lEMPERATURE C014 TROLLER PERFORMIt4G SI-16 4
+
17
\\
x
12: 3A:27 11-04-85 ELECTRICAL MAINTEt;AllCE M0t41HLY REPCRT FOR OCTOBER PAGE 4 CATE....
CDMPO NENT.....
FAltliRE DEECRIPTIOH......
CfEE OF. FAILURE.........
CORRECTIVE (CTI0il........
MR.HO..
~
.~
10-17-65 2-RM-090-0100A PAR 11CULATE LOW FLOW BAD MOTOR AND OVERLOAD REPLACED Purp MOTOR AND A545119 L
. ALARM UQULD HGT CLE/R I: EATERS Ili MOTOR ST(RTER OVERLOAD PEATER FH-31 IN MA14UAL MOTOR STARTER 10-17-65 1-BKR C-099-KE/
REPLACE LN RELAY ON ill. S 'dORMAL WEfR REPLACED BAD LN RELAYS A538537 319 DB-50 BREAKERS IN POWER STORES 10-17-85 1-ZS-30-20 LIMIT SUI 1CH IliDICATES It40ICATING LAMP ll0LDEN DEPLACEO INDICATItiG Lard' A536411 CONSTANT OPEli POSITIGH UAS FAULTY HOLDER IN MCR I'ER MI-6.20
'I'0-18-85 2-HS- 077-0017 THE ECCKET FOR THE FED OGSTitUCTION Ill LIGHT UMPLUGGED SWITCH BOX AND A534233 ItiDICATING LIGHT UCM D SOCKET REMOVED 085TRUCTIO'l FROM 110T A! LOW EULG TG BE LIGHT SOCKET TilEH PtACED IN IT REPLUGGED AND REMOUNTED TO PAtEL 2-M-15 10-18--85 2-CENB-082-000 REFLACE ELECTRICAL WIRING UNKNOUN INSTALLED UIRING A539668 IB -8 HAaNESS ASSEMBLY BETLEEH HARHESSES ON 20-1 AND 1HE ENGIt!E CONTROL 2B-2 GOVERNORS PEP, CABINETS AND FIYDRAULIC MI-6.20 AND.M&AI-7 GOVERHORS(EGG-13P) 10-19-05 0-XS-013-0096 DETECTOR ALARr1 DIO NOT CO UtMoud REPLACE 0 SMOKE DETECTOR AS45513 0FF UHILE PERF0i?MIt:G SI-234.4 10-19-85 0-XS-013-0093 DECTOR ALARM DID NOT GO UlrKHOUH REPLACED Sn0KE DETECTOR AS45514 0FF !!HILE PEnF0d11HG SI 234.4 TEST 10-20-85 1-BKR C-G82-TT/
REPLACE 125V DC BREAKERS UtlKNOWN REPLACED 4 20 AMP A546189 2-A IN DISTRIBUTIDH PANEL FOR BREAKERS IN lHE 125V DC D/G ENGINE CONTROL PANEL, DISTRIBUTION PANEL mig GEN. PROTECTIDH RELAYS, CLEAVID DIL OtJT OF 18 s
12:31:27 11-04-85 ELECTRIC /L Malt 11EMAllCE 110llTHLY REPORT FOR OCTOBER PACE 5 DATE....
CDNPO NDIT.....
FAILliRE DECCR IP TIDH......
CAUSE OF FAILURE.........
CORRECTIVE ACIION........
(12.NO..
~
DC LUS OH PunPS, BOTTOMS OF PAtELS
.~
EXCITATICl1 PAHEL, f,iG DAliERY CHARGER 10-20-65 2-CENE 2A-A REPLACE THE ELEC1RICAL UtWriGU 1 REPLACED UIRING HARIESS A539669
'UIRING HART!ESS ASSEMSLY PER lil 6.20 AND MIAI-7 BETUEEN THE EtiGIllE CONTROL CAB 1tlETS AllD THE -
HYDRAULIC COVEkliORS(EGG-13h) 10-22-63 1-CRil-79 REPLACE TEE LS-6 ACTUATOR ARM UAS BROKEH REPLACED ACTUATOR HEA')
A551209 ACTUATIHC apt 1 A!D CHECK DUE TO LIllIT SUITCt!
THE SUITCH (ND REPLACE IF STRIKING HAND RAIL DOLTS DAMAGED 10-23-05 1-LS-79-16 LEVEL SUITCH UAS NOT tmhoull REMOVED LS-16 (J40 A545515 OPERATING PROPERLY REPLACED WITH LEVEL SUITCH FROM llNIT 2 MANIPULATOR CRAME 10-25-85 1-MTR S-30-4'25 A MOTOR THERMALS 001 UHEN MOTOR PULLING EXCESSIVE REPLACED MOTOR AND A525886
--A STARTED CURRENT CHECKED FOR FROPER OPERATION 10-26-85 2-RL Y-68-333 REPLACE DEFECTIVE CRYOOM RELAY BURNED 00T DUE TO REPLACED CRYDOM RELAY A116679 RELAY 2Al-164 FOR TSC HATURAL EliD OF LIFE OF POINT 2-FCV-68-333 RELAY 10-26-85 2-RLY-72-0039 REPLACE CRYD0f1 RELAY RELAY SURNED OUT DUE TO REPLACED CRYD0ri RELAY FOR A1166EO 2AI-147 FOR TSC POINT NATURAL EtD OF LIFE OF 2-FCV-72-39 2-FCV-72-39 RELAY 10-26-85 0-BATA-250-GU-CLEAT 1 CORR 03910H FROM ENVIRONMEttrAL CONDITI0t1S CLEANED CORROSSION FROM A544596 i
VARICUS CELLS ON VITAL POSTS AND REC 0ATED WITH BATTERY I AN OXIDE INHIBITING AGENT 19 s
12:31527 11-04-85 ELECTRICAL MAINTD4ANCE M0llTiiLY REPORT FOR OCTODER PAGE 6
?DATE....
- CDilPONEN T.....
FAILURE DESCRIPTI0ii......
CAUSE OF FAILURE.........'
CORRECTIVE ACTION........
hR.NO..
10-27-05 1-RLY-72-22 REPLACE DEFECTIVE CRYDGM LELAY 00 filed OUT DUE TO REPLACED CRYD0t1 RELAY A116682 RELAY 161-153 FOR TSC
.NAlDRAL END CF LIFE OF POINT 1-FCV-72-22 RELAY 10-27-85 1-RLY-74-3 REPLACE.CEFECTIVE CRYD0f1 RELAY BURNED OUT DUE TO REPLf.CED CRYDON RELAY A116683
~
RELAY 1Al-161 FOR TEC HATURAL END OF LIFE OF POINT 1-FCV-74-3 RELAY 10-27-85 31-RLY-63-153 REFLACE DEFEC11VE CRYDOM RELAY EURIED OUT DLC TO REPLACED CRYDON RELAY A116681 RELAY 181-46 FOR TSC HATURAL END OF LIFE OF POINT 1-FCV-63-153 RELAY
10-28-85 EFSV-030-0010 CIRCUIT B-29 UAS ULGUIi1G WIRES WERE DAMAGED DUE TO. LIFTED WIRES, REMOVED A534130 FUSES AND NAD DEAD CROUlO EXCESS WIRE FORCED INTO COVER FROM C FITTING AND WHEN FUSES UERE INSTALLED FITTIllG CUT OtE WIRE TO CLEAR GROUND. REPLACED "C" PER M1AI-6 AND RETERMINATED CABLES PER MCAI-7 10-28-85 1-BKR-202-1 A-A THE BREAKER UCULD NOT DIRTY C014 TACT ON 30 RX CLEANED CONTACT AND A545227 CLOSE RELAY CHECKED FOR FRUPER OPEPATION 10-29-85 1-ZS-30-15/2-8 LIl1IT SUITCM IliDICATOR OPEN LIMIT SUITCH UAS OUT ADJUSTED GPO4 LIMIT A536410 LICHT UGULD 140T CLEAR OF ADJUSTMENT SUITCH AND DEGED FOR UHEN VALVE IS FULLY OPEN PROPER OPERATIUM PREVENTING VALVE FROM REMAltlIl4G OPEl4 UHEN IT GOES BACK TO A-Ab70 POSITION 10-30-85 1-FCV-61-193 VALVE UGULD NOT CDEM COIL UAS DEFECTIVE DUE TO REPLACED COIL AS43868 UHILE NAND SUITCH UAS 140RMAL UEAR fELD IN CPEN POSITIOil L
20 l
t
12:31:27 11-04-85 ELECTRICAL FIAINiENNiCE IDITHLY REPCRT FOR UCTOBER PAGE 7 DATE....
CCr!P 0tlEi f f.....
FAILURE DESCRIPTION......
CAUSE OF FAILURE.........
CORRECTIVE ACTION........
riR. NO..
10-30-85 2-ZS-69-303-1 LIllIT INDICATOR LIGliT LINIT SWITCH DUT OF ADJUSTED LIr!IT SWITCH A546132 WOULD IIOT CLEAR LiiEH f.DJUSTMENT W.LVE UDIT FR0il GPEN TO CLOSC POSITI0ti 45 records listed.
INSTRUMENT MAINTENANCE Unit 1 Completed modifications on. Solid State Protection System per ECN 5828 and 5957. The changes consisted of adding a time delay to the SI reset function and modifying the actuation logic far containment vent isolation.
~
~
Completed Westinghouse modification to Reactor Vessel Level Indication
. System (RVLIS) circui.t cards per FCN-TVAO-40558A. This was necessary to eliminate seismic drift problems identified with the associated electronics. Functional testing of the rack instruments is currently underway.
During performance of SI-484, instrument mechanics experienced a problem with calibration of the RVLIS transmitters. A maintenance request was initiated and later revealed a problem with the sealed sense line fill.
.As SMI-0-68-26 was be'ing performed to refill the lines, a defective hydraulic isolater was also identified. The isolater will be replaced and the system refilled after the unit enters mode 5.
Containment vent isolation occurred on October.20, 1985, as a result of containment purge air exhaust radiation monitor, RE-90-131, high radiation signal (PRO-1-85-325). The monitor's pump motor failed and created electrical disturbances which generated the high rad signal. The motor was replaced but failed again while the radiation monitor was being returned to service.
Investigation is continuing.
Unit 2 Completed replacement of defective auxiliary feedwater pump' header pressure transmitter, 2-PT-3-153, from a GE-MAC to a Rosemount transmitter. This work was authorized on ECN-6444 and was necessary because spare parts are no longer available for GE-MAC transmitters.
Completed rescaling and'recalibration of the cold overpressure protection system instrumentation per ECN-6394.
Common Completed inspection of. all PIDC lugs that are crimped on solid wire without solder. Special maintenance' instructions are being prepared to correct these terminations by.either soldering or replacement of the lugs ~.
Auxiliary building isolation occurred on October 31, 1985, as a result of Fuel Pool Radiation Monitor, 0-RM-90-103, power failure (PRO-1-85-337).
The AC power plug for this monitor was connected to a nondivisional power outlet instead~of the correct Train B outlet. Nondivisional power was lost during load switching activities and caused the monitor to initiate
.the isolation signal. A maintenance request was initiated and the power plug was reconnected to the proper Train B outlet.
F i
22
^
'w' INSTRttENT MAItITENANCE MGt;THLY SUWinY 11 ;-1 05
. PAK 1 C( 13 '
MR. COMP I! filNC SYS f f t9EF.S, DATF.... OE U F. !et.........
... C0RCCCTIVE ACTI0tl.......................
A278555. I Gn
'070 11'T 10
.-1. 5 ; En-070-12. firPaIF FPP 'e mra e!N r?: NTE t1EW INSTALLATION. IWE U nDING3 OER UPl.1??2 NODIFICATION TO GROUND PORTION OF B00ULE PFR OP117.92 A293556 1 Ff1 090 10c8 IW,..t
- r:n -0 N-Nu.. d.PAI R RP 30~ 10 ub 1 A T N TSC N0idE fcEW ltri1 ALLATION. t%E MCO 10 GEA0;NC PE2 LP11772 Ci:UUND PORTIC!I 0F tiODULE FER UP11792
.A33dOO4 0 PS 032 88A 10/16/85 0-PS-032-68A,*In ConPR IS CYCLIt.G EVERY UNKN0'N SU FOUND IN TOLERANCF. FND BAD FEU REC LDADER/121 LOA;;ER VUJ UN ANOTHER MR i
A536124 i LT 02
' r? 10/;,'/55 1-L! < 2-12*7, LVL :cTR LN '.'C IS NOT IMD SHAFT STUCK. DISLOCGED AND CHECKED INDICAT1HG LVL CN N6 IN EGHTECL RM FOR PROPER OPER A535557 1 SIS CS2 50358/1 10 '25/S5 1-SIS- 082-S0319 /1, REPL ACE CLFECT IVE DEFECTIVE T6CHCNETER. REPLACED DEFECTIVE
.ZPEE0 TACHOMETCR TACNOMETER IN SPEED SU
.A339507 1 XX 092 5008 10/30/63 1-XX-072-5003, CHECK RATE CIRC' TIME NONE. TESTING RATE CIRC TIME CONSTANT CC4STANT A539510.1 A ' 09'2 5C~7 10C0/051-XX-072-G07 CHECK RATE CIRC TIME N0f'E TESTING RATE CIRC TIME CONSTANT j
CCHSifJ4TE A537511 1W 092 5006 10/20/85 1-XX-072-5006. CHECK PATE CIRC TIME N0tE. TESTING RATE CIRC TIME CONSTANT i
CCN3 fi14T I
A539512 2A W2
'5003 10/31'35 2-XX-072 5009. CHECK RATE CIRCUIT TIFE' NCNE. TESTING HOOKED UP EG37 CHECK RATE 1
ce!CIANT CIRC TIME CONSTA.fr l
A539514 2 XX 092 500610/31/85 2-XX-072-5006, CHECK RA1E CIRC TD E NONE. !!CNE CHECKED RATE CINC tit 1E i
C0!GTA'IT CG!KiTANT A539515 2E 072 5005 10/31/85 2-XX-072-5005, CHECK RATE CIRC TIME HONE. !!CNE HJ0KED UP TEST EGPT TO CHECK CONSTANT RATE CIRC TIriE CONSTANT l
A539516 2E 092 5007 10/31/85 2-XX-092-5007.CHCCK RATE CIPCUIT TIME HOME. TESTING RATE CIRC TIME CONSTANT CONSTANT AS41720 0 RE 090 12210/03/85 0-RE-070-122 t Cd FLCu AlfRn NO TROUBLE FOUND. OPERAlED PLUNCER AND E
VERIFIED SETPHT AS41747 2 FI ' 003 ISSC 10/31/55 2-FI-003--155C, aNPRDn G;UGE IS SHOUING It;D AND SG RT C0tNERTER CUT OF CAL.
f AE00T 15GPt1 AUX FCUTR FLOW EVEN WHEN RECAL FLOW IND Am SG ROOT CONVERTER j4 THERE ARE NO PMPS RUNilING iC AS41750 2 FI 003
.163A 10/31/85 2-FI-003-163A, nHPRDu CAUCE INDICATES SG RT Cott> DUT CF CAL. RECAL SG RT lY APPROX 65 GPM FLOW TO S/G 1 UtEN THE CONVERTER i b)
-PMPS ARE OFF
'C A541921 1 FT 063 170 10/25/85 1-FT-063-170,ANPRDn SENSE LINES NOW CD NDHE. RCUTE SENSE LINES FROM TCP CF XMTR i ff..
TO TOP OF XMTR. SHOULD BE CHANNEL TO GO TO BOTT0n
.Ed TO THE BOTTOM TO (LLOW EETTER VENTING OF iE XnIR
!!h A541922.1 FT 063 2010/25/85 1-FT-063-20, aNPRDA SCH3E LINES GO T0 THE NONE. ROUlE SENSE LINES FR0n TOP CF XMTR
- .~
TOP GF THE XnTR. 910ULD EE CHANGED TO CD TO DOITOM R
TO THE BOTTOM TO /tLOW BET TER VENTING OF lb-XnIR 23 s
INi m it1D H FA[NTCMAhC E MGMTHLY SUN 1ARY 11-04-85 PACE 2 r in?
r.R. COMP U I UNC S) $ ADDR ESS. D..I E.... DESCR IP T ION............................. CORRCCTIVE ACTIDN...........
~
A542423 1 LT 077 125 10/07/05 1-LT-077-125, REPLACE BROKEN WIRE LUG FRAYED WIRE ON LUG. REPLACFD LUG ON WIRE A342426 1 PDT 062
'8 10/15/85 1-PDT-062-8,WILL NOT CALIB BAD STRAIN BAD STRAIN GAUGE ON XMTR. REPLACED GAUCE STRAIN GAUGE AND RECAL XMTR AS42427 1 PDT 062 34 10/15/C5 1-PDT-062-34, WILL NOT CALIB BAD DP UNIT BAD STRAIN GAUGE. REPLACE STRAIN GMJGE AIID LINEAP.IZED CARD AS42420 1 LT 077 12510/07/85 1-LT-077-125.REPL/CE WIRE LUG ON BLACK BROKEN WIRE LUC. REPLACED LUG ON WIRE T,
WIRE A542429 1 LT 077 126 10/07/351-LT-077-126, REPLACE WIRE LUGS ON FIELD FRAYED WIRE AT LUG. REPLACFD WIRE LUGS CABLE ON FIELD CABLE A542430 1 LT G77 410 10/07/E5 1-L1-077-410, REPLACE WIRE LUGE ON FIELD FRAYED CABLE AT. LUG. REPLACED LUCS ON C*SLE WIRE A5-12431 1 L1 07/
411 10/07/85 1-LT-077-411, REPLACE WIRE LUGS ON FIELD., FRAYED WIRE AT LUG. REPLACED LUGS ON CA3t E WIRE A5424SO 2 FT!
Ct3-910 10/15'85 2-Fn-0$P918, aFPRDa DIODE ACROSS BAD DIODE. INSTALLED NEW DIODE TERMU4ALS M9 AND M10 0F 2 R 23 IS LCADItlG DOUN INDICATOR AS45807 2 PS 032
$025/4 10/0945 2-PS-OE2-5025/4, REPLACE CR ANKCASE PRESS NO FAILURE REPLACED EVERY 5 YRS PER MFG DETECTORS PER MI 10.1 STEP 5.6.11 SUGGESTION. REPLACED SW AND FUNCTIONALLY CHECKED AS4:309 7 PS 092 5026/4 10/09/85 2-PS-082-5026/4, REPLACE CR ANKCASE PRESS NO FAILURE REPLACED EVERY 5 YRS PER MFG CETECTOR PER MI 10.1 STEP 5.6.11 SUGGESTION. REPLACED SW AND FUNCTIONALLY CHECKED A541210 0 FN 070 141 A 10/27/85 0-EM-090-141 A, CHECK CUT AND REPAIR MON BAD PWR SUPPLY. REPLACED PUR SUPPLY IS EEAL AS4t300 ' LI C Oc2 17010/23/351-LIC e:,2-175. Ala CALIS AND CR REPAIR AS EENSE LIllE PLUSGED. UNSTPODPED LINE i-EEDED BACFILLED AND FUNCTIONALLY CHECKED LIC A550553 i Lr 03S 372 W ;1/55 1-LT-O'.M.'2 FtTFCG:n PREFS TEST TO AIR IN SENSE LINE. WORK TO BE PERFORME0 VERIFY r!lL N01IFf STS FHGR OF RESULTb ON IIR A299279 AND A299298 IF DATA' 15 LW,CCEPTABLE PEF.rGEM SMI O 60 24 Am M
.b
.v.
13 M 1715 1-FM -0_0-IN, !/r UU.
N" CALIC. REPAlR FLAPPER N0ZZLE REl.ATIONSHIP OUT OF ArO PECAL PER SI 597 ADJUSTMENT. READJUSTED AfD RFCAL FM A%071o '
Qi H. 1h 17/05 2--035-Hm CHECK C.etC/ Colt CONTINUITY NONE. CHECK FOR ELECT
. NO PP F1JF f SECONDARY IN',ULATION
}
I a.lCT M E AND WitOIhG 10 CR0uMD I
F C t.; t / CF A!50Vid 57
?i3 151 I?. '..'
i-
- r
+ :
CDARD AfD RECAL
- 4.j,w 0.
-4
'+
I-W-r W CFEG FMF CIkC TIMC HONE. TESTING RATE CIRC TIr;E CGNSTANT Qiule 24
Mechanical Maintenance Section October 1985 Unit 1 (1) Aligned and retorqued the #1 reactor coolant pump motor.
(2) Set the "B" LP rotor and checked clearances.
(3) Cleaned the unit one fuel transfer canal.
(4) Performed bolt stretch on reactor coolant pump #1.
-(5). Completed motor runs on reactor coolant pump #1 and #2.
(6) Completed the alignment of the main turbine.
Unit Two (1) Performed SI-138 on RHR header "B".
(2) Changed out the solenoids on 2-VLV-43-2, 2-VLV-43-77, 2-VLV-43-201_per QMDS.
(3) Lapped the seats in 2-VLV-63-545.
(4) Replaced the CAM roller on the 690' airlock.
Common (1) Cleaned FE-77-5006.
(2) CCS heat exchanger 'C' tubes were cleaned, leaking tubes identified and plugged and the heat exchanger was returned to service.
'A' heat exchanger was returned to service also.
(3) Performed the semi-annual inspection on diesel generator 2A-A and the air start valves on diesel generator 2B-B.
Performed the annual inspection on generator 1A-A.
The monthly inspection was performed on generator 2A-A.
SI-26.1B was performed on generator IB-B.
~
25 i
SUMMARY
.0F WORK COMPLETED MODIFICATIONS OCTOBER 1985 NUREG 0588 Work this period included additional field verification, workplan writing, anel splice rework.
APPENDIX R ECNs 5265, 5435, and 6343 - Fire Doors We are awaiting instructions from the door manufacturer to complete door C-50.
Work will then begin on door C-49.
No other work was pe rfo rmed.
ECN 6235 - Reroute Various Cables Work. continues with nine workplans in work.
Workplan writing is in progress on one additional workplan.
ECN 6305 - Elevation 714 Fire Barrier Work continues.
ECN 6311 - Operator Extension on PORV The workplans for units 1 and 2 have been approved. Work has not begun.
ECN 6315 - Replace Fuses Work on this ECN remains on schedule.
ECN 6319 - Fire Protection Piping No work was performed.
OTIER ITEMS ECN 2783 - Fifth Diesel Generator Work is complete.
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel "B" train piping to the unit I upper compartment coolers has been replaced.
"A" train piping has been prefabricated and will be 26 1
- Lic,
}
OTHER ITEMS (Continued)
ECN 5009 - ERCW Piping Changeout From_ Carbon Steel to Stainless Steel (Continued) installed later.
Because of the failure of the unit 2 check valves,
~
consideration is being given to doing unit 2 work during this outage. The workplan for unit 2 was prepared and placed in the approval cycle. The replacement of the 1-inch-diameter piping to the "A" train auxiliary air compressor has begun.
ECNs 5034, 5713, and 5743 - Various Platforms in Lower Containment Work continues on the installation platform between No. I and No. 4 steam generators. Prefabrication activities were begun on the No. 2 and No. 3 platforms.
ECNs 5111 and 5503 - Office and Power Stores Facility Work is complete.
ECN 5198 - Technical Support Center Unit 2 Moore isolators were installed this period.
ECN 5200 - Postaccident Sampling Facility Rework of postmodification test deficiencies is on hold for the final design of one level loop.
ECN 5202 - Fifth Diesel Generator Tie-ins have been made. Backfilling and tape-coating activities remain.
ECN 5237 - Laundry Facility The HVAC system has been completed and is operable. More work will be~
required when additional walls are completed.
ECN 5252 - Label Node Voltages in Manholes No progress on this job this period.
E_CN 5347 - Replace Doors C-49 and C-50 (Electrical Portion)
This work is on hold.
ECN 5373 - Condensate Demineralizer Air Compressor The new coupling was received; however, upon startup, the filters became plugged with water and oil.
It was discovered that.a drain needed to be installed. This will be done in the future.
l l
l 27
\\
1 OTHER ITEMS (Continued)
I j
ECN 5489 - Parking Lot No. 1 Work is complete.
ECN 5613 ~- Installation of Emergency Lights
^
t
-This work is complete.
ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump
)
. Conduit work has commenced, with remaining work placed on hold because of material availability problems.
ECN 5645 - Replacement of Flow Control Valve 2-329 i
The valve has been replaced. We-are awaiting the arrival of the vendor representative to modify the controller.
i ECN 5657 - Installation of MSR Drain Valves-l The unit 2 workplan to install approximately 150 drain valves is
~
.in the approval cycle.
Insulation reinstallation on unit I still remains incomplete.
ECN 5795 - Field Services Building Fire detection system work is on hold'for materials.
t j
ECN 5865 - Relocate Level Alarm LA-77-129 This work is complete.
r l
ECN 5914 - Improve Reliability of Steam Dump
. Conduit is complete; valve remains to be wired in.
i l
ECNs 5938 and 6506 - Feedwater Heater Replacement
}
l The unit.1 heaters.are 99 percent complete. The reinstallation of l
some miscellaneous small piping and reinsulation ectivities remain.
l On October 26, the decision was made to replace.the unit 2 feedwater l
heaters. The insulation has been removed and heater removal started.
[
The extraction steam elbows and-reducers have been replaced on unit 1 and will be included in the unit 2 work.
i ECN 6057 - Cable Tray Covers r
~
Approximately 240 'out of 290 cable tray covers have been remanufactured or replaced.
b
. W 28
OTHER ITEMS (Continued)
ECN 6152 - SPDS ASE consoles have been installed. Work is delayed inside the horseshoe until after core reload.
ECN 6196 - Pressurizer Hangers and Valves The mirror insulation representa:ive reported on October 28 and is supervising the modification of the mirror.
The safety valves have been installed, and work has begun on the safety valves that were removed from unit 1.
Work continues on the seven remaining supports.
ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and' fuse block installation are complete. We are waiting for a Technical Specification change to place the circuits in operation.
ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement All new bundles have been inserted into the moisture separator reheaters. Twelve bundles have been welded out.
Internal modification work continues. Work will be complete by November 11, 1985.
ECN 6263 - Feedwater Hangers Lower Containment Work continues on these hangers.
ECN 6352 - Fire Protection Isolation Valves The unit 2 isolation valves have been installed and hydro completed.
The remaining unit i valves will be installed later.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation The two holes have been core drilled, instruments relocated, and connecting pipe work is in progress.
Because of NUREG 0588 requirements, the unit 2 portion of ECN 6439 will be done during this outage.
ECN 6417 - Install Alternate Seal Water for Pumps, CDWE' Electrical drawings remain to be issued.
ECN 6487 - Replacement of 0588 Solenoids All solenoids have been replaced.
l e
29
F 4 '
't OTHER ITEMS (Continued)
ECN 6494 - ERCW Pipe Replacement at CCW Heat Exchangers A spool piece, an elbow, and a tee have been replaced with "Belzonia" coated piping. An additional elbow is being replaced.
ECN 6495 - Modification of Pressurizer Pots This workplan has been prepared and placed in the approval cycle.
9 l
l
{
i 30 i
Pl TENNESSEE VALLEY A'JTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 7'
1 l
November 14, 1985 f
i Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - OCTOBER 1985 Enclosed is the October 1985 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region II Director, Office of Management Nuc.b.ar Regulatory Commission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Fbrietta Street Washington, DC 20555 (2 copies)
Suite 3100 Atlanta, GA 30323 (1 copy)
INPO Records Center Suite-1500 Director, Office of Inspection 1100 circle 75 Parkway and Enforcement Atlanta, CA 30339 (1 copy)
Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, CA 94304 (1 copy)
Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation Pittsburgh, PA 15230 (1 copy) l Mr. K. M. Jenison, Resident NRC Inspector I
Sequoyah Nuclear Plant g,
\\ \\
1983-TVA SOTH ANNIVERSARY An Equal Opportunity Employer