ML20207C681
| ML20207C681 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/30/1986 |
| From: | Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8607210417 | |
| Download: ML20207C681 (44) | |
Text
.
W TENNESSEE VALLEY AUTHORITY 0FFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT
~~
MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION
" APRIL 1986" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 i
UNIT 2 DOCKET NUMBER 50-328 I
LICENSE NUMBER DPR-79 i
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Submitted by:
g P. R. Wallace, Plant. Manager i
i 8607210417 860430 PDR ADOCK 00000327
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i TABLE OF CONTENTS
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I.
Operational Summary Page_
e Performance Summary 1
Significant Operational Events 1
Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 2
i Licensee Events and Special Reports 2-4 Offsite Dose Calculation Manual Changes 4
II.
Operating Statistics A.
NRC Reports Unit One Statistics 5-7 Unit Two Statistics 8-10 B.
TVA Reports Nuclear Plant Operating Statistics 11 Unit Outage and Availability 12-13 Reactor Histograms 14 i
III. Maintenance Summary Electrical Maintenance 15 Instrument Maintenance 16 Mechanical Maintenance 17-19 Modifications 20-24 4
IV.
Environmental Qualificat' ion (EQ) Summary 25-31
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OPERATIONAL SUMfARY l
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OPERATIONS
SUMMARY
April 1986 The following summary describes the significant operational activities for the month of April.
In support of this summary, a chronological log of significant events is included in this report.
i The units remained in an administrative shutdown the entire month due to i
design control review, configuration control updating and resolution of I
significant employee concerns. Outage related maintenance and modifications are being performed.
Unit I nas been off-line 251 days.
Unit 2 has been off-line 252 days.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 4
Date Time Event 04/01/86 0001C The reactor was in mode #5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
04/30/86 2400C The reactor was in mode #5.
The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
Unit 2
~
Date Time Event 04/01/86 0001C The reactor was in mode #5. The administrative j
shutdown due to design control review, config-j uration control updating and resolution of j
significant employee concerns contindes.
i 04/30/86 2400C The reactor was in mode #5. The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
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J FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during April was 0 MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2
~~'
The core average fuel exposure accumulated during April was O MWD /MTU
~
with the total accumulated core average fdel exposure of 8097.51 MWD /MTU.
There was no fuel movement within the reactor. However, the final shipment of l
cycle 4 new fuel (8 assemblies, I spare control rod) was received during the month.
A total of 80 fuel assemblies and three spare control rods have been received, j
inspected, and properly stored in the new fuel storage vault.
Of that total, 44 assemblies possess 3.4% enrichment and 36 assemblies possess 3.6% enrichment.
All pertinent documentation has been properly transmitted.
An inventory of the new fuel was performed by Reactor Unit personnel on April 16, 1986 in the new fuel storage vault per TI-1.
No discrepancies were observed.
SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386.
- However, there are five cell locations which are incapable 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 con-flict. Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,033.
PORVs AND SAFETY VALVES
SUMMARY
i j
No PORVs or safety valves were challenged in April 1986.
i LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in April 1986.
LER Description of Event i
1-86006 A roving firewatch could not complete his route because door A-123 was found inoperable at 0810 est, on March 18, 1986.
A screw backed out of the pull handle made the handle useless and prevented the door from being pulled opened. The door was 4
returned to service and the firewatch resumed his route.
LICENSEE EVENT REPORT (S)
(continued)
LER Description of Event 1-86007 During an NRC audit on March 12, 1986, it was discovered that manual testing of the safety injection reactor trip function was not being performed.
Plant staff was made aware of this problem. This performance is required on an 18 month-cycle in j
accordance with surveillance requirement 4.3.1.1.c.19, notation 4.
Also, this performance is required prior each unit startup.
A program will be implemented for verification by April 30, 1986.
1-86008 On April 1, 1986 at 1300 CST, the newly formed Technical Speci-fication (T.S.) Review Committee discovered that a monthly check for the steam generator (S/G) narrow range level remote shutdown
~
instrumentation was not properly performed on SI-3, " Daily, Weekly, and Monthly Logs".
SI-3 had been incorrectly written to check the wide range level instruments.
It was determined that the wide range level indicators at the auxiliary feedwater turbine control panel (panel L381, EL 669) were the proper indicators.
This instruction will-be rewritten for correction by July 31, 1986.
1-86009 An auxiliary building isolation (ABI) occurred when power was lost to radiation monitor (RM)-90-101 at 7:40 CST, April 4, 1986.
This was caused by maintenance personnel accidently disconnecting the power switch to the monitor while climbing down scaffolding in cramped quarters.
1-86011 An error was discovered by the Plant Technical Specification Review Committee in the Technical Specifications for limiting condition for operation (LCD) 3.3.2, " Engineered Safety Feature Actuation System Instrumentation", Item 9.A of Table 3.3-3 for units 1 and 2.
The containment sump level setpoint was found to be incorrect. The LCD stated that the setpoint to be 30 inches above elevation 680 feet when it should be 30 inches above elevation 679 feet, 9 inches. Error in the technical specifications upon initial issuance by the NRC has been determined as the cause.
The containment sump level transmitters for units 1 and 2 will be recalibrated to take into account the existing technical specifications.
SPECIAL REPORT (S)
The following special reports were submitted to the NRC in April 1986.
Report #
Description 86-02 Fire door A-130 was found inoperable during the performance of Surveillance Instruction-261, " Visual Inspection of Fire Doors",
on March 7, 1986.
It is the airlock door to the main steam valve room on elevation 714 in the auxiliary building. A breaching permit was immediately issued per Technical Speci-fication 3.7.12.
Inability to restore A-130 to functional status within seven days required submittal of this special report.
i SPECIAL REPORT (S)
(continued)
Report #
Description 86-03 On March 22, 1986, fire door A-38 was discovered to be inoperable during an informal walkdown of fire doors to verify maintenance
^'
deficiencies.
It is the door to the auxiliary building waste j
evaporator package room. A breaching permit was immediately
[
established in accordance with Technical Specification 3.7.12.
Because of the poor condition of the door due to normal usage, a replacement has been put on order.
Inability to restore A-38 to operable status with seven days requires submittal of this special report.
OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah Offsite Dose Calculation Manual during the month of April.
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OPERATING STATISTICS (NRC REPORTS) e
OPERATING DATA REPORT DOCKET NO. 50-327 DATE MAY 9,1986 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6544 i
OPERATING STATUS 1.
UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 1
NOTES:
2.
REPORT PERIOD: APRIL 1986 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, GIVE REASONS:
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 719.00 2879.00 42360.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00.
- 14. HOURS GENERATOR ON-LINE O.00 0.00 23871.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-4088.00
-14275.00 24928462.00
- 19. UNIT SERVICE FACTOR O.00 0.00 56.35'
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 56.35-
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 51.26-
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 51.26
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 25.60 l
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED.
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL i
DOCKET NO. : 50-327 UNIT : ONE DATE : MAY 12.1985 I
"A COMPLETED BY : D.
C.
DUPREE 1
TELEPHONE :CG15)B70-6544 j
MONTH: APRIL 1986
- )
i AVERAGE DAILY POWER LEVEL.
AVERAGE DAILY POWER LEVEL DAY (MUs Net)
DAY (MWe Net) l 01 0
16 0
}
02 0
17 0
03 0
18 0
04 0
19 0
}
05 0
20 0
05 0
21 0
07 0
22.
O
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08 0
23 0
l 09 0
24 0
i 10 0
25 0
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11 0
26 0
f le 0
e7 0
13 0
28 0
14 0
29 0
4 15 0
30 0
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P s
,f s
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAME sequoyah one DATE May 2, 1986 f
COMPLETED BY D. c. Dupree
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REPORT MONTH APRIL 1986 TELEPIIONE (615)870-6544 J
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Cause & Corrective w
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Action to No.
Date g
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Design Control, Configuration Updating, 7
851220 F
719 F
9 and Employee Concerns.
.a 4 Exhibit G-Instructions 3 Method:
2Eeason:
3F:
Forced S:
Scheduled A-Equipment Failure (Explain) 1-itanual for Preparation of Data B-!!aintenance or Test 2-!!anual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & Li, cense Examination Outage F-Administrative 5-Reduction G-Operaticnal Error (Explain) 9-Other sExhibit I-Same Source ll-Other (Explain)
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OPERATING DATA REPORT I
DOCKET NO.50-32D l
DATE MAY 9,1986 COMPLETED BY D.C.DUPREE f
TELEPHONE (615)S70-6544 I
OPERATING STATUS 1.
UNIT NAME: SEGUOYAH NUCLEAR PLANT, UNIT 2
NOTES:
~~
~
j 2.
REPORT PERIOD: APRIL 1986 3.
LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (CROSS MWE):
1220 4 5.
DESIGN ELECTRICAL RATING (NET MWE):
1148.0 6.
NAXINUM DEPENDABLE CAPACITY (GROSS ht!E):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY (NET MKEs:
1148.0 1
l S.
IF CHANCES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST HEPORT, GIVE REASONS:
I 9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
1 4
i THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 719.00 2879.00 34320.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00; I
- 14. HOURS GENERATOR CN-LINE O.00 0.00 21494.42 1
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00-t
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22'
- 17. GROSS ELECTRICAL ENERGY GEN. (NWH) 0.00 0.00 23536780.00,
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-6828.00
-18330.00 22613627.60-3 j
- 19. UNIT SERVICE FACTOR O.00 0.00 62.63.
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 62.63 1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 57.40:
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 57.40
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 26.97:
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
4
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
I.
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING. AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
I r
E NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
I
- I i.
SEQUOYAH PluCLEAR PLANT i
j AVERAGE DAILY POWER LEVEL l
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DOCKET NO. : 50-328 UNIT : TWO j
l DATE : MAY 12,1986
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i COMPLETED BY : D. C. DUPREE l
i 1
i TELEPHONE :CS15)B70-6594 MONTH: APRIL 1986 i
1 l'
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL i
DAY (MWe Net)
DAY CMWe Net) 01 0
15 0
02 0
17 0
I 03 0
18 0
04 0
19 0
05 0
20 0
06 0
21 0
4 07 0
22 0
08 0
23 0
09 0
29 0
1 10 0
25 0
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.11 0
26 0
i 12 0
27 0
13 0
28 0
14 0
25
.O 15 0
30 0
1 i
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.-.,,.,,. ~ -. - - -,
,. -, -, =, -. -
, - - - = - -
4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE May 2, 1986 COMPLETED BY D.
C.
Dupree REPORT HONTH APRIL 1986 TELEPHONE (615)870-6544 cause & Corrective' gg N,
oy Licensee g s, e,
Action to No.
Date g
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Design Control, Configuration Updating, 7
850821 F
719 F
4 and Employee Concerns.
2 aMethod:
4 Exhibit G-Instructions IF:
Forced Reason:
S: Scheduled A-Equipment Failure (Explain) 1-itanual for Preparation of Data B-!!aintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source II-Other (Explain)
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e se OPERATING STATISTICS (TVA REPORTS)
iV A 7382 A (DF@ 6 84 NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant 719 APRIL 86 Period Hours Month 39 Item No.
Unit No.
UNIT ONE UNIT TWO PLANT 1
Average Hourly Gross Load kW 0
0 0
2 Maximum Hour Net Generation, MWh 0
0 0
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3 Core Thermal Energy Gen GWD (t)2 0
0 0
4 Steam Gen. Thermal Energy Gen., GWD (t)2 0
0 0
8 5
Gross Electrical Gen., MWh 0
0 0
5 6
Station Use, MWh 4,088 6,828 10,916 7
Net Electrical Gen., MWh
-4,088
-6,828
-10,916 8
Station Use, Percent N/A N/A N/A 1
0 0
0 9
Accum. Core Avg. Exposure, MWD / Ton 6
10 CTEG This Month,10 BTU 0
0 0
6 11 SGTEG This Month,10 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
~k 16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 g
e 18 Turbooen. Avail. Factor Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0
20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuos 0
0 0
22 Reactor Cold Startuos 0
0 0
23 p
24 Gross Heat Rate, Btu /kWn N/A N/A N/A j
25 Net Heat Rate, Stu/kWh N/A N/A N/A 1
26 E
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature, 'F N/A N/A N/A d
30 Enhaust Pressure, InHg Abs.
N/A N/A N/A g
31 Intake Water Temp.,
- F N/A N/A N/A 32 33 Main Feedwater, M lb/hr N/A N/A N/A i
34 h
35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 9
39 Oil Fired for Generation, Gallons 3.168 5
40 Oil Heatina Value. Blu/ Gal.
138.000 41 Deu! Generation. MWh 48 42 I
Max. Hour Net Gen.
Man. Day Net Gen-Load MWh Time Date MWh Date Factor, %
3 43 N/A N/A N/A N/A N/A N/A Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
l 2(t) indicates Thermal Energy.
Oi Date Submitted Date Revised
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12 18 20 24 28 32 APRIL 1988 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -
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t SUmfARY OF MAINTENANCE ACTIVITIES I
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ELECTRICAL hhlHTEdhWCL nDHTHLY SUdnARY 05-02-86 PAGE 1 COMP i
MR.CDNP U FUNC SYS i:DDRESS. DATE.. DESCRIPTIDH......
CORRECTIVE ACTION.
6?00531 2 CABL 361 2V21020 04/11/86 2-CABL-361-2V21028, MAIN PWR CABLE AUT 10 PESOLVE BREAK 0UT PRGBLEM 2V2102B HAS DAMAGE TO THE INSUL ARGUND THE INDIVIDUAL CONDUCTORS THAT ARE TERMINATED AT TERMINAL STRIP A5?t096 1 f!V 030 0134 04/C8/86 1-fSU-030-0134-B, REBUILD ULU W/NEW PER QMDS. INSTLD HEW ELAS'9dERS PARTS ELASTDMERS. RETURN DLD ELASTunERS TO MR GRIC. WORK REG'D TO UERIFY LIFE EXT DF ELASTDnERS 84 ACCUM RM EL 718 AZ 291 o
0164179 1 H0R 352 04/03/86 1-HGR-352-,ulu REM 00E HGRS TO ALLOW JOB WILL TAKE 40 HR$ TO INSTALL TORQUINC Of AUX FWSC LCU 00PHETS 1 LCV 3 171 AHD 1 LCU 3 148 0112590 1 HTRA 063 0036 04/04/86 1-HIRA-063-0036-D,B.I.T. 1HK STRIP HEATERS CHECKED UK. MEGGARED T1T2T3 AT HEA1ER 1B-D POSSIBLE CAD STRIP HTRS MDU EUAFD STARTER. HEATER ELEnENTS CHECK AND REPAIR AS NEEDED CHECKED: A=7.5A 0=7.5A C=AT.5A Ds4.5A E=4.5A AND f=4.4A D112590 I:315307 0 XfD 311 0233 04/07/86 0-XfD-311-0233, REPAIR UR REPLACE CAD FUSIOLE LINK. REPLACED ELEC1RICAL DAMAGED PARTS TU ELECT FIRE DAnPER. I FUSIBLE LINK. C 115307 LIHK 45H 1630.76 CCHIRDL 732 1115'i46 1 HIR 003 0037 04/01/86 1-HIR-063-0037-A, REPLACE EAD STIP HEAT HEATERS HAD BURNED DUT. MEGSAR CHECKED DH BIT TARK T1 T2 T3 ATMcV 00ARD. REPLACED 2 HEATERS. CHECKED A5P READIHS OF EACH HEATER: A=7.4A B=7.3A C=7.3 D=4.4A E=4.5A F=4.1A B 115546 0110325 1 Zi 067 0308 04/04/861-ZS-067-0348, LIMIT SW DDES HDT MAKE UP LIMIT SWITCH ACTUATOR WAS DUT Of PsDPERLY ADJUSTMENT. ADJUSIED LIMIT SWITCH ACTUA1DR 8118325 0115899 0 CHR 311 0141 C4/14/86 0-CHR-311-0141, CHILLER PKC CYCLES TD BAD nECHANICAL SEAL. REPLACED MECHANICAL FULL LCAD HOWEUER IT IS NOT CODLING.
SEAL D119899 CUNTRDL 732 MECH EQ RM 0119901 1 MUSP 0?0 0013 04/08/86 1-nUDP-070-0013-D,THIS ULY FAILED TO CLOSE LIMIT WAS UUT DF ADJUSTnENT FULLY STRDKE DY UCR AND SWITCHGR INDICAT!DH-ChK LIMIT SWITCHES AGAINST ACTUAL ULV POSITIDH FOR POSSILLE ADJUSTMENT AD 690 A36.3.
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MAINTENANCE SU? DIARY (INSThUMENTATION)
INSTRUMENT MAINTENANCE MONTHLY REPORT ITEM FOR APRIL 1986 UNIT 1 Installed new sensor bellows assembly on LT-68-320.
Work is continuing to return the instrument loop to service.
Initiated PRO-1-86-095 for failure to perform the quarterly functional test 2
surveillance requirement on Condenser Vacuum Exhaust Flow Monitor (SR 4.3.3.10.D.3.a).
Procedures were revised to incorporate this requirement.
Initiated PRO-1-86-091 and 1-86-060 for calibration errors on the cold leg accumulators and containment sump level channels respectively. Work is continuing to resolve the scaling on these instrument loops. This item applies to both units.
Completed wiring changes to the reheat control circuit which enables manual control of the reheat control valves during times when the high temperature relay was energized.
- ' PRO-1-87-069 was initiated based on the Technical Specification Review Committee's finding on failure to functionally test on a 31 day interval "all associated circuitry" as required by note 1 of table 4.3-2.
This item applies to both units.
During replacement of the UHI level switches, under ECN 6359, we identified that the system response time would change. No analysis was performed to j
support this change so a contract with Westinghouse is being initiated to resolve this issue. This is applicable to both units.
UNIT 2 Completed wiring changes to the reheat control circuit which enables manual
~
control of the reheat control valves during times when the high temperature relay was energized.
Completed writing workplan to record heatup data for RVLIS during startup.
PRO-2-86-030 was initiated based on Technical Specification Review Committee's findings on failure to functionally test the turbine stop valve closure verification prior to startup following automatic trips. This PRO applies to both units. e m
4 9
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9 O
M MAINTENANCE
SUMMARY
(MECHANICAL)
O
d Mechanical Maintenance Monthly Report - April COMMON 1.
Completed coupling work on "A" RW purification pump 2.
Completed exhaust silencer inspection on 2BB D/G 3.
Reset injector racks on 1BB D/G 4.
Mechanical work complete on "B" RWP pump 5.
Mechanical maintenance work complete on IBB D/G monthly and quarterly 6.
Peplaced diaphragm in "A" & "B" BAEP 7.
Lompleted work on aluminum sludge pond pumps 8.
Alignment complete on "C" RCW pump a
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Mechanical Maintenance Monthly Report - April
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UNIT 1 1.
Work complete on 1-HV0P-003-67 & 81 2.
Work complete on 1-FCV-72-503 i
l 3.
Completed work on 1-VLV-70-725B l
i 4.
Work complete on 1-VLV-70-63 5.
Completed dome paint inspection 6.
Ccmpleted seal inspection on IB/IC Hotwell pumps v
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Mechanical Maintenance Monthly Report - April 1
UNIT 2 e
i 1.
Seven of eight limitorques rebuilt i
i 2.
Completed work on 2AA feedwater heater
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3.
Mechanical work complete on 2-FCV-3-191 and 192 4.
Rebuilt 2-VLV-43-460 f
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SUMMARY
(MODIFICATIONS)
SUMMARY
OF WORK COMPLETED MODIFICATIONS APRIL 1986
~
NUREG 0588 ECN 6231 - Remove Interferences The Division of Nuclear Engineering (DNE) is continuing their reanalysis on ERCW piping to the unit 2 upper compartment coolers.
Indications are that one support will be removed and three supports will be added.
ECN 6552 - 0588 Solenoids Functional testing has not been performed because of other work in progress on these valves.
ECN 6632 - Restrict Valve Room Flow Drains (Supersedes ECN 6609)
DNE is revising the USQD.
APPENDIX R ECNs 5435 and 6343 - Fire Doors The replacement and repair of the doors and doorframes continue; 10 are incomplete.
ECN 6235 - Reroute Various Cables Nine workplans are in work on conduit / cable reroute.
Insulation is in progress at various locations.
ECN 6311 - Operator Extension on PORV r
This work has been completed except for final cycling at startup.
ECN 6315 - Replace Fuses Fuse installation is in work.
ECN 6319 - Fire Protection Piping Some minor hanger enhancements, paintwork, and installation of spray nozzle shields are continuing.
ECN 6642 - Annulus Fire Protection and Sealing Containment Penetrations The ECN and USQD were received, and the workplan was placed in the approval' cycle.
Fieldwork should begin in early May. e
OTHER ITEMS ECN 2783
-Installation of Fifth Diesel Six electrical-related workplans for the fifth diesel installation have been placed in the workplan closing cycle.
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of isolation valves remains in the approval cycle. Some insulation activities remain incomplete. DNE is revising the USQD.
ECNs 5034, 5713, 5743, and 6064 - Various Platforms in Lower Containment The mechanical platform work was completed.
Some paintwork and cleanup remain. A trolley for the monorails was returned to the vendor for modification. When it is returned, it will be tested; and, if satisfactory results are obtained, the others will be sent to the vendor for modification.
ECN 5202 - Interface of Fifth Diesel With Other Diesels Workplans for the interface of the fifth diesel with other diesels for trains 1A-A and 1B-B are in the approval cycle.
ECN 5252 - Label Node Voltages in Manholes The manholes have been completed. This ECN will be complete by May 11.
ECN 5373 - Condensate Demineralizer Air Compressor Final postmodification testing (PMT) continues.
ECN 5451 - Installation of Diesel Generator Pressure Switch Isolation Valves 4
All work was completed.
ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump Work is on hold.
ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete. Caps are being installed on the valve nipples.
ECN 5667 - Double Isolation Valves for Flow Orifices (Unit 2)
Work was completed. e
o OTHER ITEMS (continued)
ECNs 5703 - Reinforcement of Block Walls DNE and Plant staff concluded that the installation of restraints was the best solution. Work has begun on the unit 2 walls, c
ECN 5724 - CVCS/RHR Supports Work was restarted on the installation of the remaining nine hangers.
ECN 5795 - Field Services Building Fire detection system work is on hold for materials.
ECN 5914 - Improve Reliability of Steam Dump Functional testing remains.
ECNs 5938, 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe Insulation on unit 2 is complete. Mechanical craft is supporting PMT on both units.
Insulation work on unit I has resumed.
Building steel reinforcement for Nos. 3 and 4 feedwater heater replacement on unit 2 was completed.
Installation of the monorail was begun.
ECN 5977 - Steam Generator Blowdown Demineralizer The tie-in was completed, thus completing all work planned at this time.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced.
ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete.
ECN 6156 - Replacement of Diesel Generator ERCW Isolation Valves This work was completed.
ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.
ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete. We are awaiting a technical specification change to place the circuits in operation. e
s OTHER ITEMS (continued)
ECN 6259 Moisture Separator Reheater Tube Bundle Replacement Insulation activities are continuing.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work is complete except seal welding fill tees. This will be completed after Instrument Maintenance completes fill and calibration.
ECN 6417 - Install Alternate Seal Water for Pumps, CDWE Electrical drawings remain to be issued.
ECNs 6491 and 6534 - ERCW Supports Work remains for one original support. Seven additional supports have been identified. DNE is issuing drawings.
ECN 6580 - Relocation of Diesel Generator Control Panel Support This work was completed.
ECN 6599 - Unit 2 Shield Building Anchor Problem All deficient anchors have been replaced. Variances are being prepared to document the deviations.
ECN 6601 - Removal of EGTS Backdraft Dampers The workplan was written and approved. Work will begin in May.
ECN 6610 - Modify Air Return Fan Supports Work was started on the unit 2 fans.
Dry Active Waste Building (DCR 1898)
Approximately 99 percent of the concrete foundation work has been completed. Modification to the structural steel frame will start during May if the required design drawings are available. Some structural steel members are being sandblasted and painted.
Additional Office Buildings (DCR 2260)
The construction work on the two office buildings on the west side of the Design Services Complex is progressing well.
i l
c OTHER ITEMS (continued)
Welding Project Support was provided to Welding Project personnel as requested.
Walkdown Field Verification Support SMI-0-317 Unistrut Clamps SMI-0-317 Concrete Edge Distance SMI-0-317 79-14 Enhancement 0-b f
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4G ENVIRONMENTAL QUALIFICATION (E.Q. ) SU? DIARY
Estimated Date of Completion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Conments EQP 8501 Disconnect 1-and 2-HS-62-61 6524 Peters 11901 C
C U-2 QIR submitted.
EQP 8502 Replace penetrations 23 and 48 6490 Peters 11801, 11802, C C
Conplete QIR submitted.
11810, 11811 EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Conplete field verification sheets are in binder. No Q1R needed.
EQP 8504 Spilce methods not correct N/A Stockton 80 MRs C
C Conplete QIR submitted.
EQP 8505 Drawing N/A N/A N/A N/A N/A EQP 8506 Seal containment isolation 6514 Kimsey 11880 C
C Seals installed, new gaskets, valve top hat arrived 2/7, will install 2/9.
EQP 8507 Rcwire MOV N/A Rutledge 11866, 11853 C C
EQP 8508 J3 weepholes (press) 6523 Alas 11898 C
C Conplete QIR submitted.
EQP 8509RI Condait seals 6529 Kimsey 11903, 11904 C C
EQP 8509R2 Conduit seals 6615 N/A N/A N/A No field work remaining.
EQP 8510 Disccanect local handswitches 6527 Peters 11901 C
C EQP 8$11 Submerged JB inside 6549 Peters 11901 C
N/A containment EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 C C
All rewired.
,=
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Estimated Date of Completion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Comnents EQP 8513 Weep holes (moisture) 6547 Alas 11898 C
C Conplete QIR submitted.
l EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C
C Canplete QIR submitted.
EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C-Canplete QIR submitted.
EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C
C EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C
Maint.
EQP 8517 ABGTS htsnidity control 6578 Gonzales N/A C
EQP 8518 Submerged cables 6533 Various/6 Various 5/15 5/15 Rework of terminations is in progress.
EQP 8519 Tee drains N/A Electrical N/A C
C Conplete QIR submitted.
Maint.
EQP 8520 Expired cables 6553 Gonzalez 11902 C
C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C
EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C
EQP 8522R2 Rewire local panels N/A Instrument 5/11 5/11 Maint.
EQP 8523 Missing bolts and washerss N/A Stockton 11914, 11915 C C
and misplaced brackets
Estimated Date of Coneletion SCR No.
Description ECN Engireer Workplan No.
U-l U-2 Conments EQP 8524 Change setpoints 6551 Instrument 11916 C
C Maint.
EQP 8525 Rotenninate hydrogen N/A Electrical N/A C
C
. Conpleted by Electrical Maint.
reconbiner (m)
Maint.
EQP 8526 Replace FSVs, U-l 1 U-2 11 6552 Mechanical 11897 C
C
- Mods, EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C
(MR)
EQP 8528 Solder strain gauge Barton IMI Instrument N/A C
C QIR submitted 1/24.
transmitters Maint.
EQP 8529 PDT-30-42, -43 6554 Legg 11912 C
C EQP 8530 Casket, Namco L/S N/A Electrical N/A C
C (m)
Maint.
EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C
EQP 8532 Delete L/S 1, 2-43-201, 6630 Alas N/A N/A No longer an issue.
-202, -201, and ~208 EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C
^
EQP 8534 Resplice valve positioner N/A Maxwell MR C
C Conplete QIR submitted.
3-174 and -115
. = _ _..
Estimated Date of Canoletion SCR No.
Description ECN Engineer berkplan No. U-1 U-2 Conwnts s
EQP 8535 Replace limit switches, 6556 Stockton 11927 U-2 5/30 C
Holding for limit switch delivery.
U-1 10. U-2 12 11928, U-1 Delivery expected 5/20.
EQP 8536 Valve room subnergence 6561 Mechanical 11939 C
C Cap drains 6632 Mods.
5/30 5/25 OE to redo ECN to orifice drains.
EQP 8536R1 Valve room sotwocrgence 6612 Electrical C
C Mods.
EQP 8537 Rebuild or replace JB 3078 6579 Mturn N/A C
EQP 8538 Replace capacitors FCO-31-475, N/A Maxwell 11977 N/A C
-476 EQP 8539 Replace capacitors N/A Instrument C
C Maint.
EQP 9540 Replace pigtails to Target 6581 Maxwell 5/10 5/5 Rock wienoid valves l
EQP 8541 Delete brakes 6582 Branham 11980 5/10 N/A 1-FCV-63-93, -94, 1-FCV-63-93 is conplete. Parts to be delivered 5/5.
EQP 8542 Replace unqualified cables N/A Hall Various 6/15 N/A Two cables will be replaced in accordance with a new issue.
EQP 8543 Replace JB wire N/A Mburn 11855, 11856 C C
4 L
e 9,
e
Estimated Date of Cmoletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Coments EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 5/11 5/11 Will require replacement. Transfer upgrade 2-PT-1-28, -278 from WBN in progress. Material delivery set for 3/15. Upgrade kits have 5-to 7-week delivery.
OE is pursuing alternates.
EQP 8602 Rercute control cables for AaaaAAAAA"AA " a" " " " "A" " " " " A"A" " a No longer an issue.
1 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 6627 Kimsey N/A 5/30 Will splice in Additional Equipment Building and Elevation 759 Transformer Room.
EQP 8604 Cable 1PL3'd41A not qualified aaaaa" A A A" A"aa A Aaaaaaaa A A A"aaaaaaaa A A A"a i4o longer an issue.
EQP 8605 1, 2-IS-74-43, -44, -45, -46 6589 Branham 5/10 5/10 Has been held up by 1/4-inch bolt not qualified problan.
EQP 8606 Undervoltage concern on 6611 Rutledge 6/15 6/15 Delivery of solenoids expected 4/4.
feedwater isolation valve brakes EQP 8607 Delete IB for 1, 2-PT-1-2A, 6626 Instnsnent 5/11 5/11 Will work same time as EQP 8601.
-27A Maint.
EQP 8608 Enabic/ disable MOV brakes 6621.Rutledge 5/30 5/30 6622 6667 EQP 8609 Replace cable IV79738 5/1 N/A Ncw item.
. t i
~
e Estimated Date of Concletion SCR No.
Description ECN Engineer Workplan No. U-l U-2 Comments EQP 8611 JB has weephole in top N/A Anburn N/A C
EQP 8612 Replace zone switches N/A 5/30 EQP 8614 Weep holes in JB C
C I
f.
I
= - _
9 Estimated Date of Cnneletion SCR No.
Description ECW Engineer Workplan No. U-1 U-2 Consnents N/A Move surge suppression network 5773 Kimsey 11883 C
C U-2 couplete. On U-1, 1-PCV-68-340 for PORV in hold. Holding for maintenance to conplete.
EEB 8523 Penetration overcurrent 6606 Legg 5/30 5/30 During closure process, it was found that 6 circuits had not been addressed by ECNs. ECN 6606 addresses this.
N/A Work FCR to delete 1,
5883 Hall C
C Need SI-166.
2-PS-3-160A, -1608, -165A, and -165B N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrument N/A 3/21 N/A
-108, -21A, -218, -28A, -288 Maint.
NES 8510 Relocate LT-68-320, 6439 Carrasquillo various C
C PT-68-323, -320 Peters Remoun. 63-71,68-308 64 %
Legg 11865 C
C Replace LS-65-4, -5 6504 Legg 11865 N/A C
MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C
Delete brakes FCV-62-61 6521 Branham 11905 C
C EEB 8S17 Replace pressure transmitter 6488 Branham 11931 C
C PDT-6's -20, -82, -90, and -S7 t I
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D.
O 98' M
TIIIS PAGE INTENTIONALLY LEFT BLANK
Tu TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 J
May 13, 1986 Nuclear Regulatory Commission Office of Management Information end Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - APRIL 1986 i
Enclosed is the April 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY N.
g/
P. R. Wallace Plant Manager i
j Enclosure cc (Enclosure):
Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100
)
101 Marietta Street Atlanta, Georgia 30323 (1 copy)
Director, Office of Inspection and Enforcement Nuclear Regulstory Commission Washington, DC 20555 (12 copies) e r
l Mr. A. Rubio Electric Power Research Institute P. O. Box 10412-Palo Alto, California 94304 (1 copy)
INPO Records Center.
Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy)
Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant i
6' Q>N 9
1983-TVA SOTH ANNIVERSARY
~
I I-I An Equal Opportunity Employer
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