ML20132H274
| ML20132H274 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/31/1985 |
| From: | Hollomon T, Wallace P, Wilbourn G TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8510020108 | |
| Download: ML20132H274 (30) | |
Text
_ _ _ _. _. _ _
o TABLE OF CONTENTS l
I.
Operational Summary Pm Performance Summary 1
Significant Operational Events 1-3 Fuel Performance and Spent Fuel Storage capabilities 3
PORCs and Safety Valves Summary 3
Licensee Events, Special Reports and 3
Diesel Generator Failure Reports 4
Offsite Dose Calculation Manual Changes 4
i Changes, Tests, and Experiments Not Requiring 5
[
Authorization From NRC Pursuant to 10 CFR 50.59 (a) l l
II. Operating Statistics I
A.
NRC Reports Operating Data Reports 6-7 Unit Shutdowns and Power Reductons 8-9 Average Daily Unit Power Level 10-11
)
B.
TVA Reports i
Nuclear Plant Operating Statistics 12 4
Unit Outage-and Availability 13-14 Reactor liistograms 15-16 l
i III. Maintenance Summary Electrical Maintenance 17-19 l
Instrument Maintenance 20-23 Mechanical Maintenance 24 Modifications 25-29 I
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Operations Summary July 1985 The following summary describes the significant operational activities for the month of July.
In support of this summary, a chronological log of significant events is included in this report.
Unit 1 Unit I was critical for 691.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, produced 742,300 MWH (gross), resulting in an hourly gross load of 1,106,919 kW during the month. The capacity factor for the month was 84.3 percent. There are 46.21 full power days estimated remaining until the end of cycle 3 fuel. The cycle 3 refueling / modification outage is scheduled to begin September 27, 1985..
t During the month the unit experienced one reactor scram, one power reduction, and no manual shutdowns.
I Unit 2 Unit 2 was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />, produced 852,220 MWH (gross), resulting
[
in an average hourly gross load of 1,145,457 kW during the month. The capacity factor for the month was 96.8 percent. There are 173.49 full power days estimated remaining until the end of cycle 3 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached February 21, 1986.
During the month, the unit experienced no reactor scrams, manual shutdowns or power reductions.
Significant Operational Events i
Unit I t
Date Time Event 07/01/85 0001 The reactor was in mode 1 at 100% power, l
producing 1150 MWe.
i 07/05/85 1705 HSR C-1 was removed from service.
The turbine i
dropped 6.0 MWe.
07/19/85 0349 The reactor tripped on a lo-lo level in #3 steam generator. An A3E was swapping the feeds I
to Turbine MOV Board B when the main oil pump t
tripped causing the high and low pressure stop
[
valves to the main feedpump turbine to close.
The auxiliary oil pump started but failed to produce the required pressure to keep the valves open. The unit operator inserted the rods to adjust for feedwater fluctuation but no runback occured.
There was a manual runback,
[
MFPT A came up to full speed and the motor operated ArW pumps started.
The generator i
was at 850 MWE when the reactor tripped.
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Significant Oparational Events (Cont.)
Unit 1 4
i Date Time Event 07/21/85 0756 The reactor was taken critical.
0914 The reactor was at 3% power and in a chemistry hold.
07/22/85 0100 Began power ascension.
0157 The reactor entered mode 1.
.i 0315 The reactor was at 12% power and rolling turbine.
0435 The turbine tripped on first out electrical i
problem- - too much excitation.
07/22/85 0524 The unit was tied on-line and increasing power.
e 0600 The reactor was at 26% power and holding while the feedwater heater were being placed inservice.
0720 Began power ascension.
1040 The reactor obtained 30% power and entered a chemistry hold.
2125 Began power ascension.
t 07/23/85 0625 Reactor was at 43% power and preparing to pump forward.
0750
- 3 Htr Dr Tk Pmps A & B tripped.
0852
- 3 Htr Dr Tk Pmps B & C tripped.
0940 1-FCV-6-106 maintaining level in #3 Htr i
Dr Tk.
Began pumping forward.
0945 Began Power Ascension 07/24/85 0115 The reactor obtained 100% power.
l 07/26/85 0358 1-LCV-6-105B opened.
The turbine was ranback to 67% GV position. The reactor was at 78% power.
0446 The controlling setpoints were adjusted on
- 3 HDT.
Began power ascension.
I l
07/26/85 0930 The reactor obtained 100% power.
1 j
07/31/85 2359 The reactor was in mode 1 at 100% power i
producing 1145 MWe. The unit has been in j
continous operation since July 22, 1985 at I
0524C (9 days).
i 1
Significant Op rations 1 Events (Cont.)
Unit 2 Date Time Event 07/01/85 0001 The reactor was in mode 1 at 100% power producing 1150 MWe.
07/31/85 2359 The reactor was in mode 1 at 100% power producing 1145 MWe.
The unit has been in continous operation since May 24, 1985 at 0141C (68 days).
Fuel Performance Unit 1 The core average fuel exposure accumulated during July was 1033.83 MWD /MTU with the total accumulated core average fuel exposure of 12418.71 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during July was 1189.46 MWD /MTU with the total accumulated core average fuel exposure of 7303.08 MWD /MTU.
SPECIAL NUCLEAR MATERIAL SAFEGUARDS & ACCOUNTABILITY SYSTEM ANNUAL AUDIT The annual review of the plant's special nuclear material (SNM) safeguards and accountability system was performed on July 30-31, 1985.
In addition to the records audit, a physical inventory was performed on July 31 in the new fuel storage vault on new fuel, 72 bundles, (Unit 1 Cycle 4).
There were no discrepancies.
Spent Fuel Pit Storage Capabilities The total storage capability in the spent fuel pit (SFP) is 1386.
However, there are five cell locations which are not in 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 276 spent fuel bundles stored in the SFP.
Thus, the remaining storage capacity is 1105.
PORVs and Safety Valves Summary No PORVs or safety valves were challenged in July 1985.
Licensee Events and Special Reports The following licensee event reports (LER) were sent during July 1985 to the Nuclear Regulatory Commission.
1 LER DESCRIPTION OF EVENT 1-85025 With unit 1 in mode 5 and unit 2 in mode 1 at 100% reactor power, the service building radiation monitor 0-RM-90-132 was declared inoperable on May 28, 1985 at 1010C.
The plant technical specifications require a noble gas sample to be taken every eight hours for up to 30 days or suspend all releases. The required sample at 1810C on June 1, 1985, was not taken until 2055C.
Liernsas Evsnts and Spreini Rsports LER DESCRIPTION OF EVENT (Cont.)
1-85026 On June 11, 1985, at 0130C with unit 1 in mode 4 at 270 F a main feedwater (MFW) isolation occurred.
The isolation was initiated from a high high steam generator (S/G) level in steam generator
- 1.
Makeup water to the generators was being supplied from the auxiliary feedwater system and the main steam isolation valve (MSIV) bypass valves were opened to heat the steam lines downstream of the MSIVs.
The warming continued until the indicated AP
> 25 psid across the MSIVs was obtained.
When the MSIV to S/G #1 was opened, the water level indication increased from 35 percent to 100 percent. The feedwater isolation signal is generated by any 2 of the 3 level indicators on any one generator being greater than or equal to 75 percent. Thus the feedwater isolation occurred.
1-85027 On June 25, 1985, at 0914C with unit 1 in mode 3 at 525 F a main steam line isolation occurred. The isolation resulted in steam generators loops 2 and 4 coincident with a operating temperature below 540 F (Lo-Lo'Tavg). The isolation valves went to the closed position as required.
The safety injection (SI) signal that is initiated by high steam line flow coin-cident with Lo-Lo Tavg was blocked, as allowed by STS; therefore, no SI occurred.
1-85028 At 0800C on July 4, 1985, with unit 1 in mode 1 at 100%
power, the hourly fire watch for the unit 1 additional equip-ment building was not conducted because door A-183 would l
not open. The defective door was returned to operable status and the hourly fire watch r aumed at 0906C.
l 2-85008 On July 12, 1985, at 1234C with unit I and unit 2 both in mode 1 at 100 percent power, an inadvertent trip of the i
normal feeder breaker on the 6900 volt 2A-A shutdown board l
initiated the actuation of the engineers safety feature (ESF) system. The trip occurred while a modification was being performed on the alternate. feeder breaker. The alternate feeder breaker was racked out and personnel were not actually performing work immdiately before or during the trip.
There i
was no actual blackout condition during the event.
Special Reports No special reports were transmitted during the month.
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.
Chtngts, Tcsts end Experiments Not Requiring Authorization From The NRC Pursuant to 10 CFR 50.59(a).
A.
Change Description The condensate demineralizer waste evaporator is part of the liquid radwaste processing system.
Chapter 11 of the Final Safety Analysis Report is currently being revised to agree with the current "as-configured" system description.
This change is part of this documentation.
The current configuration of the liquid radwaste system in brief, is to use the CDWE as the primary method for processing station leakage (floor drains). Portable demineralizers are available onsite to provide backup for the CDWE in case of its failure or excess leakage (over and above the CDWE capacity).
B.
Unreviewed Safety Question Determination 1.
The addition of the CDWE adds a permanent enhancement to the overall plant capability to process liquid radwaste. The CDWE is used continously and thereby provides a constant demand upon the component cooling system which provides cooling water to the CDWE.
The CDWE requires approximately 1600 gpm at full flow conditions and is capable of operation at lower capacities under situations of high CCS loading.
The component cooling system, with the CCS pump in operation, can j
produce 6,000 gpm (SQN FSAR Section 9.2.1.2) per unit, to train B safety related loads.
The capacity of the component cooling water system is adequate to assure that the demands of the CDWE during its normal operation, even though continous, does not impact the cooling capability for engineered safeguard loads.
Sufficient precautions are provided in the system, including automatic isola-tion of CCS to the CDWE, to assure that a break in the system does not divert extra flow to the CDWE portion of the system away from l
the safeguard loads.
l 2.
The CDWE as a part of the liquid radwaste system is a portion of a system that could be part of a long-term recovery from a design basis accident.
However, this part is not an integral part and is not essential to safe shutdown of the unit.
The interface of the CDWE with the CCS as a cooling medium is addressed in the discussion of No. 1 above.
Since the system (CCS) is automatically isolable and provides adequate measures to manually isolate flow in the case of failure of this automatic function, the evaluation is that the system as currently configured and operated poses no additional possibility for creation of a new accident.
3.
The Component Cooling System (CCS) interfaces with the CDWE as its primary cooling medium.
Further the CCS is included in Technical Specifications requiring operability of two trains during power
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operation. The design features of the system providing isolation i
and the assurance that engineered safeguards loads are not deprived during neither normal or accident conditions proves assurance that the margin of safety defined in CCS specification is not decreased.
i The CDWE provides additional, permanent, enchancement of the liquid radwaste system therefore the margin of safety of this system is l
increased, i
OPERATING DATA REPORT e
DOCKET NO. 50-327 DATE AUGUST 7 1985 COMPLETED BY GENE R WILBOURN TELEPHONE (615) 870-6544 OPERATING STATUS 1.
UNIT NAME: SEQUOYAH NUCLEAR PLAN 1, UNIT 1
NOTES:
- 2. REPORT PERIOD:. JULY 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):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, G IVE REASONS : --__--_-_-__
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):_----_--
-v
- 10. REASONS FOR RESTRICTIONS,IF ANY:--_----___---_-________
THIS MONTH YR.-TO-DATE CUMULATIVE i1.
HOURS IN REPORTING PERIOD 744.00 5087.00 35803.00 i2.
NUMBER-OF HOURS REACTOR WAS CRITICAL 691.90 3269.25 23916.91 r3.
REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
$4. HOURS GENERATOR ON-LINE 670.60 3234.30 23343.25 i 5.
UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 i6. GROSS THERMAL ENERGY GENERATED (MWH) 2206077.60 10603301.96 76280987.91 i.7.'
GROSS ELECTRICAL ENERGY GEN. (MWH) 742300.00 3643040.00 25379456.00 LO. NET' ELECTRICAL ENERGY GENERATED (MWH) 716172.00 3494071.00 24375701.00 9.
UNIT SERVICE FACTOR 90.13 63.58 65.19 1
- 30. UNIT AVAILABILITY FACTOR 90.13 63.58 65.19
$1. UNIf CAPACITY FACTOR (USING MDC~ NET) 83.85 59.83 59.30
$2. UNI 1' CAPACITY FACTOR (USING DER NET) 83.85 59.83 59.30
$3. UNIT FORCED OUTAGE RATE 9.87 12.44 17.57 34.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, Befufl1DS/39difi.fniSS :_SePle@_eJ_31t_1.251__j]_d_ays_@y_c}g_3_)AND DURAT ION OF EACH) :
- 35. 'IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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OPERATING DATA REPOR1 DOCKET NO. 50-328 DATE AUGUST 7,
1985 COMPLETED BY GENE R WILBOURN TELEPHONE (615) 870-6544 OPERATING STATUS 1.
UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2
NOTES:
2.. REPORT PERIOD: JULY 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 DEPENDABLE 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 RESTRICTED,IF ANY(NET MWE):________
- 10. REASONS FOR RESTRICTIONS,IF ANY:___ ____.___. __________
4 THIS MONTH YR.-TO-DATE CUMUL ATIVE
- 11. HOURS IN REPORTING PERIOD 744.00 5087.00 27768.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 4789.22 21484.34
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 O.00 O.On
- 14. HOURS GENERATOR ON-LINE 744.00 4724.17 20994.35
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 O.00 O.00
- 16. GROSS THERMAL-ENERGY GENERATED (MWH) 2535400.80 15435603.15 67434614.02
- 17. GROSS ELECFRICAL ENERGY GEN. (MWH) 852669.00 527'7519.00 22969199.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 822669.00 5077706.00 22098714.60
- 19. UNIT SERVICE FACTOR 100.00 92.87 75.61
- 20. UNIT AVAILABILITY FACTOR 100.00 92.87 75.61
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 96.32 86.95 69.32
- 22. UNIT CAPACITV FACTOR (USING DER NET) 96.32 86.95 69.32
- 23. UNIT FORCED OUTAGE RATE O.00 7.02 8.24 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
Refuellrg/Mnmien H nn _Jehruary_LRBh_.10_ days.(Cycle _31.________._____
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED..
UNIT Sl!UTDOWNS AND POWER REDUCTIONS DOCKET N00 50-327 UNIT NAME Seouoyah one DATE August 5, 1985 COMPLETED BY T. J. Hollomon REPORT MONTl!
JULY TELEPHONE (615) 870-7132 m
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Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual 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)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other.
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SQNP ATTACHMENT I AI-18 AVERAGE DAILY UNIT POWER LEVEL Apendix A Page 3 of 8 Rev. 24 FILE PACKAGE NO. 55 DOCKET NO.
50-327 REPORT REQUIREMENTS UNIT One DATE Aucust 6. 1985 COMPLETED BY T. J. Ho11omon TELEPHONE (615) 870-7132 MONTH July 1985 Day AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(tNe-Net) 1
_1113__,._ ____
17 1107 2
1113.
18 1J04 3
1117 19 1050 4
1119 20 NA 5
1115 21 NA 6
1119 22 227 7
1120 23 659.6 8
1121 24 1097 9
1120 25 1103 10 1118 26 1075 11 1119 27 1104 12 1117 28 1104 13 1115 29 1109 14 1115 30 1107 15 1114 31 1105 16 111_2 INSTRUCTIONS On this format, list the average daily unit power level in rNe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
'SQNP ATTACHMENT 1 AI-18 AVERAGE DAILY UNIT POWER LEVEL Apendix A Page 3 of 8 Rev. 24 FILE PACKAGE NO. 55 DOCKET NO.
50-328 REPORT REQUIREMENTS UNIT Two DATE August 6. 1985 COMPLETED BY T. J. Holloman TELEPHONE (615) 870-7132 MONTH JULY 1985 Day AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1107 17 1105 2
1107 18 '
1104 3
1106 19 1101 4
ling 20 1104 5
11n7 21 1103 6
1107 22 1103 7
111n 23 1102 8
iiii 24 1102 9
1119 25 1103 10 iii2 26 1104 11 11nR 27 1105 12 i i i t, 28 1106 13 iiii 29 1106 14 iii9 30 1111 15 iiin 31 1110 16 1in7 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. -
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UNIT OUTAGE AND AVAILABILITY SEQUOYAll Nuclear Plant
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l Lecensed Reactor Power 3411 MW(th)
Unit No.
ONE l
Generator Rating 1220. 5 MW(e)
Month / Year JULY 1985 Design Gross Electanal Rating
!!83 Mw p,,,g
,, 744 METHOD OF UNIT time unit Ava.latise Yeme Not Amletale CORRECTIVE ACTION fT Total Gen.
Not (Aed Turtune Gen.
Reactor Unit Ou N
DUR G Day Has ' u,n ms un ms ! uin as ; u.n as ' u,n as ' w.n ms l u.n ms!u m, ! u,.
REACTOR OUTAGE I
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UNIT OUTAGE AND AVAILABILITY SEQUoYAH Nuclear Plant l
Lnensed Reactor Power 3411 MW(th)
Unit No.
l Generator Rateng 1220.5 MW(e)
Month / Year
_IULY 1985 Deugn Gross Electrical Rating 1183 MW Period Hours 744 METHOD OF UNI T Time Unst AvailaWe Tome Not AvaelaWe CORRECTevE ACTION Totae Gen.
Not Used Tuntuvie Gen.
Reactor Unit Ou in N
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- u,n REACTOR OUTAGE I
24 soo 24 ; oo l
00 too oo soo oo ;oo 00 00 i
2 24 800 24i 00 00 :oo 00 ;00 00 soo 00!00 3
24 :oo 24e 00 00 ioo 00 goo oo 300 oo ; oo 4
24 ioo 24 ; oo 00 s oo 00 soo 00 foo 00 : 00 e
5 24 ioo 24 00 i
00 800 00 :00 00 ;oo 00!o0 e
6 24 foo 24 e oo e
oo ' oo oo ioo 00 foo 00 i 00 8
7 24 '00 24' 00 00 :00 00 f oo 00 l00 00e00 e
8 24 :oo 24' 00 l
00 :00 00 ioo 00 soo oo ; oo i
8 9
24 00 24i 00 i
00 foo 00 'oo oo 'oo 00 e 00 i
l 10 24 ioo 24 e 00 I
oo ioo 00 00 00 ioo 00!00 l
11 24 soo 24' 00 l
00 e 00 00 ioo 00 soo 00j00 12 24 800 24' 00 i
00 100 00 !oo oo ;oo 004 oo 13 24 !o0 24i 00 00 foo oo :00 00 ioo 00 ! 00 e
14 24 ;oo 248 oo oo 100 00 ioo 00 'oo 00 : 00 is 24 :oo 24! 00 i
oo s oo oo !oo oo ;oo oo i oo i
i 16 24 soo 24: 00 i
oo :00 00 100 00 !oo 00s 00 i
e 17 24 800 24 ; oo 00 i oo 00 !oo oo ;oo 00 ! 00 i
18 24 f oo 24 00 oo ' oo 00 lo0 00 soo oo ; oo e
i 19 24 00 241 00 e
00 i00 00 too oo ioo oo i oo 8
20 24 ;oo 243 00 e
00 ! og oo foo 0o fog og, oo 21 24 ioo 24i 00 oo ;oo 00 ioo 00 ;oo ooI oo i
oo loo 00 foo 00 #00 00 ' oo i
t 1
22 24 loo 24I 00 e
23 24 !oo 241 00 00 f oo 00 ioo 00 :00 00 ; 00 e
24 24 Ioo 24! 00 oo i 00 00 f oo 00 ioo 00 i 00 I
25 24 ;oo 24i oo i
oo 800 oo lo0 oo 'oo 00 e 00 26 24 ;oo 24 00 i
oo ;oo oo ioo oo :00 00600 i
27 24 soo 24! oo oo 'oo oo s oo oo.00 00 ! 00 i
e 28 24 loo 24i oo i
co ! 00 00 f oo 00 ;oo 00 ; oo 29 24 ' oo 24! 00 00 soo 00 :00 00 too 00 i 00 nn inn nni nn i
t 30 nn l nn nn inn s
l 31 i
60 i OO 00 s oo 06 !66 661 00 i
l Total 744[00 7_4A __oo 00 !OO 00 l00 00 iOO 00 ; 00 g X
_X X
e e
SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -
1 4
90 -
-h 80 -
U 6
70 -
a.
y 60 -
a 50 -
b 40 -
b h
30 -
6 20 -
10 -
NI O
i i
i
.- i O
4 8
12 16 20 24 28 32 JULY 1985 SEQUOYAH TWO REACTOR HISTOGRAM 110 100 -
90 -
h 80 -
O 6
70 -
o.
f 60 -
a 50 -
b 40 -
0 30 -
20.-
10 -
0 i
i i
i i
i i
i i
i i
i i
O 4
8 12 16 20 24 28 32 JULY 1985
.~.
-..-- _ ~
Reactor Histogram Comments July 1985 Unit 1 1.
07/19/85 0350 Reactor Tripped - Lo-Lo level #3 steam generator.
2.
07/21/85 0755 The reactor was taken critical 3.
07/21/85
' 0907 Chemistry Hold 4.
07/22/85 0531 Tied on-line 5.
07/22/85 0600 Placed feedwater heaters inservice 6.
07/22/85 0726 Chemistry Hold 7.
07/23/85 0628
- 3 HTR Dr TK Pmps tripped 8.
07/26/85 0405 Manual runback when 1-LCV-6-105B opened.
4 ;
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-., -. - -n,
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14:08:29 O H 2-85 ELECTRICAL MAINTENANCE MENTH.Y REPORT FOR AR.Y PAGE 1 DATE....
01rF0*ENT.....
FAILURE DESCRIPTION......
CAUSE OF FAILLRE.........
CORRECTIVE ACTION........
79t.le..
06-18-85 i-BCTD-313-5/
AIR COPOITIOER WOULD NOT OVERLOAD RELAY BLAtlED OUT REPLACED DVEPLOAD RELAY A518125 110-A RLM 06-19-85 1-FCV-062-0073 VALVE Il@ICATING LIGHTS ACTUATOR BOLT WAS nner REINSTALLED ACTUATOR BOLT A528961 SHOWING INCORRECT VALUE PREVENTIls LIMITS FROM AlO CECNED FW PROPER POSITION MAKING UP NERATI(M 06-20-85 1-TS-13-200AtB TRCUBLE ALARM IS IN ON BAD DETECTOR REPLACED DETECTOR A528425 SMONE DETECTGt 06-20-85 2-BCTC-77-125A PUFF WILL RLM FOR 30 SEC.
BAD AUXILIARY CONTACT ON REPLACED AUXILIARY A526388 TEN TRIP DN TERMAL BREAKER CONTACTS ON BREANER OVERLDAD 06-21-85 0-CHGB-250-GE-CHARGER NEEPING 142 VOLTS CHARGER DUT OF ADJUSTPENT ADJUSTED FLDAT VOLTAGE A531041 D
ON VITAL BATTERY BOARD CAUSING FALE VOLTAGE Ale E4UALI2E V(LTAGE READING 06-21-85 1-FCV-30-19 PLRGE AIR DerFER LIMIT SWITCH BRACHET WAS ADJUSTED AE TIGHTEED A528964 IlOICATOR LIGHT IS LOOSE LIMIT SWITCH BRACHETS SiOWIls INC(RRECT VALVE POSITION 06-24-85 2-HTCK-234-106 POINT 10 CIRCUIT 106 VIBRATION CAUSED LOOSE REPAIRED LOOSE Col #ETION A528213 TERR 10 STAT WILL NOT TERfCiTAT CODGECTION OPERATE i
06-29-85 2-HTCK-63-54 TEFFERATURE LESS THAN BAD CONTROLLER REPLACED CONIROLLER A528448 TECH SPEC REGUIREPENT 07-10-85 1-LSV-62-110A VALVE POSITION IPOICATOR ACTUATOR ARM LOOSE (N ADJUSTED AC1UATOR AftM Ale A528292 SHOWING INC(RRECT VALVE STEM CAUSING FALSE CECMED FGt PRWER POSITION READING OPERATI(M 07-10-85 2-INVB-250-eP-FAN FAILURE ALAftM IN DIRT IN SWITCH CLEAED AIR FLOW SWITCH A528416 E
l# FILE FAN IS RtDNING ADO CECNED FOR PROPER 14:08:29 06-02-85 ELECTRICAL MAINTENANCE MMTM.Y REPORT FOR JLA Y PAGE 2 DATE....
GRF0ENT.....
FAILlRE DESCRIPTION......
CAUSE OF FAILLRE.........
CGtRECTIVE ETION........
Nt.ND..
WERATISI 07-10-85 1-PM.A-60-341F CONTRCL BAl#( &
BAD SILICON CCHTROL REPLACED SILIGBd CONTRM.
A527920 PRESSLRIZER EATERS WAS RECTIFIER RECTIFIER NOT MOOLLATING TO CONTROL PRESSLSE 07-10-e5 1-LSV-062-0118 VALVE ISOICATING LIGHTS ACTUATIDN ARM OUT OF ADJJSTED ACTUATION ARM A528292 A
SHOWI E INCORRECT ADJUSTENT Ale CECNED FGt PROPER POSITION OPERATIS4 07-15-85 2-FCV-63-063 BOTH IMICATGt LIGHTS ARE ACTUATOR ARM SHIFTED ON ADJUSTED LIMIT SWITDI A526450 ON LREN VALVE IS IN OPEN STEM ACTUAIGt ARM OR CLOSE POSITIG4 07-15-85 2-FSV-63-21 ELECTRICAL SOLENDID THAT MISSING RETAIER CAP REPLACED RETAIER CAP A528053 OPERATES VALVE IS NOT FIRftY ATTACED CAUSING ERRATIC VALVE OPERATION 07-15-85 2-FCV-063-0063 VALVE IleICATOR LIGHTS LIMIT SUITCH ACTUATGt ARM ADJJSTED LIMIT SWITCH A526450 WILL NOT CLEAR L&EN VALVE OUT OF ADJUSTENT ACTUATOR ARM Ape CEDED IS @EED OR CLOSED FOR PROP 9t WERATION 07-16-85 2-MTR B-313-JJ CHILLER WILL RtM 5-10 AIR FLOW SWITCH OUT F MAAJSTED AIR FLOW SWITCH A541052 st-e SEC. nEN Shur Om ADJuSTENT I
07-19-85 2-FCV-063-0084 VALVE IBOICATOR LIGHTS VALVE ACTUATOR ARM OUT OF ADJUSTED VALVE ACTUATOR A5313BB SHOWING IDEGtRECT VALVE ADJUSTENT ARM POSITION 07-21-05 1-FCV-001-0025 VALVE WILL leT OPEN BRONEN Hale SWITCH REPLACED ROTARY SWITCH A533531 07-24-85 1-9NR A-030-015 BREANER BLOWS CONTROL CRYDOM RELAY ON DAMER REPLACED RELAY Ate A537148 7
POER FUSES WAS FALLTY DECNED FOR PRWER NERATISI 14:08:29 0942-85 ELECTRICAL 11AINTDWCE FEBmt.Y REPGtT FOR JA.Y PAGE 3 DATE....
GN900ENT.....
FAIL 1RE DE90tIPTI(N......
CAUSE OF FAILtRE.........
CORRECTIVE ACTION........
fWt. M3..
07-25-85 14CTB-030-003 REPAIR 480V ACB FGt 1B-9 SHORTED CRYDort RELAY REPLACED OtMNI RELAY IN A537135 9
CONTADfENT AIR RETIRN C(MTR(L CIRQlIT FAN 20 records listed.
I 1
e INSTRUMENT MAINTENANCE Unit 1 1.
During full power operation, while operations was switching a 480V AC MOV board supply, IB main oil pump lost power. A subsequent decrease in oil pressure caused the main feed pump turbine stop valves to close but did not cause a feed pump turbine trip.
Power was immediately returned to the oil pump causing an increase in pressure which did not allow the turbine to runback or to initiate a start of the auxiliary feedwater pumps.
Without manual actuation the stop valves would not reopen. With only A pump operating a lo lo level occurred in the #3 steam generator which caused an ESF actuated reactor trip.
2.
During the forced outage, following maintenance on FCV-3-103, the #4 steam generator level increased sharply to 75% when the valve was unisolated which resulted in a feedwater isolation. An inspection of the valve indicated that the valve was not seated. The valve stroke was readjusted and the valve was returned to service.
3.
During startup from the ice outage the RVLIS PMT showed that the control room indicators did not respond as expected. A calibration check was performed on the sections of the RVLIS electronics that were expected to be causing the error.
This check showed that some cards had drifted from their calibrated values.
The recalibration of the affected cards was completed.
4.
Performed a calibration of UHI level switches, SI-196. Two switches, LS-87-21 and 23, were found out of technical specification tolerance.
I PRO 1-85-228 was written.
Unit 2 i
1.
The initial calibration of RVLIS has been completed.
Installation of the system was completed during U2C2 outage.
l 2.
Performed a calibration of UHI level switches, SI-196.2.
One switch, LS-87-23, was replaced because of a stripped setpoint screw.
3.
The process computer malfunctioned eight times. The problem was determined to be an intermittent amplifier on a read head for the disk. This caused the P250 to stop and wait for data, which never arrived. Troubleshooting was difficult because no error messages were generated.
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INSTR 01ENT MAINTENANCE MONTHLY SUIT %RY 08-07-85 PAGE 1 COMP MRoCOMP U FUNC SYS ADDRESS. DATE.... DESCR IP T ION..................................... CORRECTIVE ACTION.......................
A237837 2 F3 030 195 07/25/85 2-FS-030-195, REPAIR AS REG'D FLOW CONTROLS OF PROBLEM WITH 2 FS 30 194. WROTE LP TO PEN RM CLR FAN 2BB HAVE ABOtE SW CALIB A292790 2 TS 068 3/6 07/19/85 2-TS-068-3/6 CHECK CALIB 0F 2TS 68 316 RECALIB BISTABLE OUT OF CAL. RECAL BISTABLE l
IF REG'D A292792 2 TS 068 317 07/19/85 2-TS-068-317, REQ'DK CALIB 0F 2TS 68 317 RECALIB BISTABLE OUT OF CAL. RECAL BISTABLE IF REG \\D l
A527102 2 PIS 087 23 07/15/85 2-PIS-087-23, INDICATOR NOT WORKING PROPERLY PRESS IND INOP. REPLACED IND-RECALIB.
(
A527109 2 FT 070 81E 07/24/85 2-FT-070-81E, CHECK CALIB 0F FT IT IS CAUSING XMTR WAS OUT OF CALIB. RECALIB XMTR.
PERIODIC ISOL OF ISOL VLUS FCV 70 90 AND 133 A527116 2 TI 074 38C 07/25/85 2-TI-074-38C,NIN TEMP IND HEEDS TO BE CALIB RESIDUAL HEAT REMOVAL SYS OUTLET HEAT NEEDED TO COMPLETE SI 3 MONTH _Y DUE BY 7/29/85 EXCH
'A' lEMP CURRENT TO CURRENT REPEATER WAS FOUm SLIGHTLY OUT OF CALIB. f1DDIFIER WAS RECALIB.
l A527904 1 LIC 003 172 07/03/85 1-LIC-003-172,LCV-3-172 IS TAKING TOO LONG TO HO PROBLEM FOUND. OPER. CHECK AND INDICATE FULLY CLOSED STROKE OK.
l A528245 1 FT 070 149 07/11/85 1-FT-070-149, PERFORM LOOP CALIB CK ON FT 70 149 FLOW SW WAS OUT OF CALIB. RECALIB SW.
A528246 1 FT 070 150 07/11/85 1-FT-070-150,PERFmM LOOP CK CALIB ON FT 70150 XMTR AND FLOW SW OUT OF CALIB. RECALIB XMTR AND FLOW SW A528247 0 FT 070 20 07/11/85 0-FT-070-20, PERFORM LOOP CK CALIB ON FT 70 20 XMTR OUT OF CAL. RECAL Xf1TR A328250 2 LI 003 173 07/08/85 2-LI-003-173,LI IlOICATING SLIGHTLY LOWER THAN CURRENT TO CURRENT REPEATER HAD A BAD OTHER N2 S/G LEVEL INDICATING SOURCES.
CAPACITOR IN IT. REPLACED BAD CAPACITOR;RECAL; AND RETURNED TO SERVICE A528952 1 fR 030 241 07/03/85 1-f1R-030-241, RECORDER HAS FAILED LOW BAD DEW CELL. REPLACED DEU CELL A331376 2 TE 070 154 07/11/85 2-TE-070-154,PERFmn LOOP CALIB ON TE 70154 TEMP MODIFIER WAS OUT OF CALIB. RECALIB THE TErP F10DIFIER A531378 2 FT 070 150 07/10/85 2-FT-070-150,PERFmM LOOP CK CALIB ON FT 70150 FLOW MODIFIER WAS OUT OF CALIB. RECALIB THE FLOW #10DIFIER A531379 2 FT 070 149 07/10/85 2-FT-070-149,PERFmf1 LOOP CHECK CALIB ON FT 70 FLOW MODIFIER WAS OUT OF CALIB.
149 RCCALIB. FLOW T10DIFIER A531382 2 TS 068 316 07/19/85 2-TS-068-316.TS-68 IS KEEPING ALARM PZR SPARY BISTABLE OUT OF CAL. RECAL PER tR LIHE TEfP DN IN WEH INDICATOR READUS 550 292790 DEGREES F A533588 1 FI 003 1038 07/22/85 1-FI-003-1038, LOOP #4 FEED FLOW CHANNEL DOES HOT FDUTR FLOW XMTR WAS OUT OF CALIB.
'ImICATE FLOW. IHWSTIGATE AHD REPAIR. PLACE RECALIB XMTR BISTABLES IN TRIPPED CONDITION PER INST.
A533639 0 PS 082 271 07/26/85 0-PS-082-271.PS WILL NOT START AC ON LOW LACK OF LUBRICATION. LUBRICATED APO RECEIVER PRESS CALIB SW A533698 2 085 88 07/17/85 2-085-88, NIN RPI SEEMS TO IMVE A LOUSE LOOSE C0tM CTION. REPAIRE0 PLUG ON IND.
CONNECTION A537115 1 LI 063 49 07/06/85 1-LI-063-49,LVL Ito SHOWS LOWER THAN ACTUAL AIR IN LIES AND HEAT TRACE TOO HIGH.
BLEW DOWN LINES AHD RESET HEAT TRACE TO I
INSTRlfENT FIAINTENANCE r10NTtLY Surt1ARY 08-07-05 PAGE 2 8
COW
~
r1R.Com U FUNC SYS ADDRESS. DATE.... DESCR IP TION..................................... CORRECTIE ACTION.......................
PROPER POINT.
A538647 1 PIS 001 13 07/23/85 1-PIS-001-13,RECAL SW PRESS. SW OLIT OF CAL. RECAL SW.
A541822 0 fE 046 1830645 07/03/85 0-SC-046-1830645, REPLACE ANLIFIER GAIN BAD POTENTI0rIETER. REPLACED POT APO l
POTENTI0r1ETER. CECK OUT SPEED CONTROL F1000LE RETURED TO PWR STORES FOR SPARE I
FOR PROPER OPERATION A>0 RETIRN TO POERSTORES l
A541823 0 SC 046 1929411 07/03/85 0-SC-046-1929411,01ECK FIO0lLE FOR PRODER HOE. CECKED PROPER OPERATION APO SENT l
OPERATION A>0 RETLRN TO PSTORES FOR SPARE BACK TO PSTORES l
AS43789 1 FS 030 103 07/03/851-FS-030-103, VERIFIED 1A SUPPLY FAN AUX BLDG IS BAD SW.
REPLACED SW Af0 RECAL l
RLM4ING WITH ALL DAW ERS OPEN A545843 2 LS 087 22 07/10/85 2-LS-087-22,EED TD REPLACE SW WITH ANDTER SW SCREW STRIPPED OUT ON SW.
REPLACED SW.
BECAUSE ADJUSTrlENT SCREW IS SlRIPPED ON OLD SW l
25 records listed.
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r INSTRlfENT rAINTENANCE f10NTM.Y SumARY 00-07-05 PAGE 1 CON
~
rR. HIST U FUNC SYS A00R ESS. DATE.... DESCRIP TION..................................... CORRECTIVE ACTION.......................
A292778 1 LT 068 320 07/01/851-LT-068-320, PLACE A RECORDER ON TE THREE NOE TESTING. HOOK UP RECORDER TO 3 PZR PRZR/LVL CHAlNELS 1 LT 68 320;335;339 COMECT LVL CHAMELS FOR TESTING PURPOSES TE RECORDER TO TE C0f1PUTER POINTS IN 1 R 26 AIO 27 One record listed.
e Mechenien1 Maintensnee Section July 1985 Unit 0 1)
Performed the monthly inspection on the diesel generators.
2)
Performed the five year inspection on 2B-B diesel generator.
3)
Performed the six month inspection on IA-A diesel generator.
4)
Installed a threshold on an ABSCE boundary, door A118, to repair a two inch gap.
5)
Rebuilt the "B" waste gas compressor.
6)
Rebuilt the fuel oil pump on the 2A-A diesel generator.
7)
-Rebuilt the "B" auxiliary air compressor.
Unit 1 1)
Welded a nipple and valve onto the drain of the 1B2 moisture seperator reheater.
2) 1-FCV-63-84 was leaking through. Replaced the plug, the stem, and the packing.
3)
Tightened the expansion joint on A&B main feedwater pump turbines to lower air inleakage.
4)
Replaced the main turbine bearing oil lift pump and relief valve.
Unit 2 1)~
Rebuilt 2-VLV-67-582D relief valve.
2)
Repaired a 3/4" schedule 40 letdown sample line which was broken at the heat affected zone of a joint weld. The joint was replaced with a 4" section of piping.
= - _ _ _ _ _ _ _ _ _ _ _ _
i l
t
SUMMARY
OF WORK COMPLETED MODIFICATIONS JULY 1985 NUREG 0588 ECN 5970 - NOV Operator Replacement The last operator was replaced this period.
Appendix R ECN 5435 - Install Weatherstripping on ABSCE Doors We finished installing weatherstripping on ABSCE architectural doors. We are awaiting material for heavy equipment doors.
ECN 6235 - Reroute Various Cables Work continues with five workplans in work.
l ECN 6305 - Elevation 714 Fire Barrier We have finished installing baseplates and prefabricating structural j
steel framing for the wall.
ECN 6308 - Bypass Switch This ECN has been completed.
ECN 6309 - Breaker Indicator Lights This ECN has been completed.
l ECN 6319 - Fire Protection Piping We have rerouted approximately 30 percent of the heads required to be relocated. Work is ongoing to plug sprinkler heads that are to be j
abandoned (approximately 70 percent complete). We are adding heads on elevations 714, 734, and 749 of the Auxiliary Building. The workplan to install two new deluge valve systems has been written and is in the approval cycle.
I Other Items.
ECNs 2783 and 5202 - Fifth Diesel Generator Permanent power tie-ins have b~een made. The system is waiting for removal of temporary feeds prior to being energized. Work continues on providing permanent power to the building. A punchlist has been prepared for remaining work items and cleanup.
I l
Other Items (Continued)
ECN 5009 - ERCW Piping Changeout from Carbon Steel to Stainless Steel Work continues on train A.
ECN 5111 - Semipermanent Power to Temporary Facilities This project has begun.
Seven handholes have been installed.
Approximately 35 percent of the conduit in areas A, B, and C is complete.
ECN 5111 - High-Pressure Fire Protection to OE Complex Piping is complete, and hydrostatic testing will be performed within a few days.
ECNs 5111 and 5503 - Office and Power Stores Facility Power Stores began moving into the new facility on July 15.
The modification to the NRC office on elevation 710 has been completed.
Work has begun on the installation of the windows in the stairwells.
Work is continuing to complete the remaining punchlist items.
Most of the outstanding work consists of exterior items, such as sidewalks, handrails, manhole covers, and landscaping.
The modification to the vending area of elevation 710 will begin within the next two weeks.
ECN 5119 - Install Radiation Monitor Cables in Conduit The last monitors have been completed. This ECN is complete.
ECN 5194 - Iodine Monitor The two security doors have been functionally tested. This ECN is complete.
ECN 5200 - Postaccident Sampling Facility Rework of postmodification test deficiencies is on hold for the final design of one level loop.
ECN 5237 - Laundry Facility Remaining work is on hold until the last wall is built.
ECN 5373 - Condensate Demineralizer Air Compressor This project is almost complete, with the exception of the installation of the motor coupling and pressure control instrument.
The materials are onsite. Functional testing and minor repairs will be done with the help of a vendor representative during August.
We received a new differential pressure control box to replace a faulty one found on the new compressor.
Once Construction installs the control box, the new air compressor can be functionally tested by the vendor representative.
9 **.
Other Items (Continued)
ECN 5489 - Parking Lot No. 1 This project has begun and is underway at the present time. The work area was blocked off, and a temporary access to the parking lot was made. Grading is in process for both additions to the parking lot.
ECN 5599 - Fifth Vital Battery The Appendix R-related conduit wrap is approximately 95 percent complete.
The wrapping will be completed when additional materials are available.
The protective coating in the battery room will be applied during August.
ECNs 5609 and 5610 - Makeup Water Treatment Plant This project is near completion.
A walkdown was performed on July 29.
The participants in the walkdown indicated items which need to be completed, and a punchlist has been compiled. The septic tank and piping have arrived, and digging has begun for their installation.
Still awaiting design procurement are the stainless steel sump pump and the air compressor.
ECN 5613 - Installation of Emergency Lights Work has been completed on eight of nine lighting systems. The last one is being held because of defective equipment.
ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump Conduit work has commenced.
ECN 5657 - Installation of MSR Drain Valves The unit 2 workplan to install approximately 150 drain valves is in the approval cycle.
Insulation reinstallation on unit I still remains incomplete.
ECN 5660 - Blocking Diodes This modification is approximately 50 percent complete.
ECN 5664 - Replace Relays in Wells Fargo Alarms Remaining work has been restarted and will continue during Power Block reconfiguration.
ECN 5795 - Field Services Building Fire detection system work is in hold for materials. -
I*
t 0ther Iters (Centinuzd)
ECN 5841 - Hot Machine Shop This project has been completed as designed under ECN 5841. The addition of a monorail and electro polisher in the decontamination room will be accomplished under ECN 6411.
ECN 5855 - Replace Air Lock Doors A56 and A57 We have finished chipping the concrete column between doors and have installed the air tank and control panel.
The workplan to install door A56 is in the approval cycle, and the one for door A57 is ready for approval.
ECN 5865 - Relocate Level Alarm LA-77-129 Preoutage work is in process.
ECN 5878 - Modify Entrainment Separator - CDWE l
This work is essentially complete.
I ECNs 5932, 5935, 5959, and 6105 - Security Power Block All cameras and watch towers have been completed. One fence sector, three gates, and three doors remain incomplete at this time. The E-field for the ERCW has been completed as well. The anti-intrusion devices around pipes in the Turbine Building have been installed.
Other remaining work includes CCW pump E-field, high mast lighting, s
painting of ERCW coffer / cells, and high intensity lighting for the ERCW pumping station.
[
ECN 5938 - Feedwater Heater Replacement The three monorails have been installed and tested. Work continued on fabrication and installation of steel platforms required to transport the Nos. I and 2 feedwater heaters to elevation 685 of the Turbine Building. Some building windbraces were removed to allow feedwater heater movement to begin. Tests were conducted on the internal cleanliness of the new Nos. I and 2 feedwater heaters, and they were found to be acceptable for installation without further cleaning.
ECN 5990 - Add Condensate Divert Valve to CDWE This work is essentially complete.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced.
, - ~.
I i
j o' eO Other Items (Continued)
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 6326 - Install Temporary Drain Hose from CDWE to Floor Drain Collector Tank Work was corf.leted on the rubber hose that was run from the CDWE to the floor dr,2in collector tank.
ECN 6351 - Install Demineralized Water Booster Pumps for CDWE Operations requested that the booster pump tie-in point be located further upstream on a demineralized water line to help boost the water pressure for the entire CDWE Building.
This change required drawing revision and new material, which will add approximately five days to the original outage duration.
ECN 6362 - Install Pad Flanges and Valves for Sample Skid - CDWE This work is essentially complete.
ECN 6417 - Install Alternate Seal Water for pumps - CDWE Mechanical drawings from OE were issued, and the workplan was written.
ECN 6447 - Incore Detector Ten-Path Cart Modification The following modifications have been completed for units 1 and 2 to qualify the incore detector ten path cart to withstand a seismic event:
(1) Existing 3/8-inch bolts in ten path cart anchorage were replaced with 3/8-inch ASME SA-193 grade B7 bolts.
(2) Removable sections of platform grating in the cart area were mechanically secured.
(3) Existing 12 bolts in ten path frame assembly were replaced with 3/4-inch ASTM A325 bolts.
In addition, frame members were increased in size.
(4) For unit 2 only, additional braces for cart anchorage were installed.
Training Buildings This project has been completed, and the buildings are being occupied at this time.
l 9
TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 August 13, 1985 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAll NUCLEAR PLANT - MONTilLY OPERATING REPORT - JULY 1985 Enclosed is the July 1985 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTIIORITY OR. A P. R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region II Director, Office of Management Nuclear Regulatory Commission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta 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, GA 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 jf P. O. Box 355 Pittsburgh, PA 15230 (1 copy)
/p ff n
Mr. K. M. Jenison, Resident NRC Inspector
' l Sequoyah Nuclegry}jnkVA 50m ANNIVERSARY An Equal Opportumty Employer
-