ML20237K937
| ML20237K937 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1987 |
| From: | Dupree D, Nobles L TENNESSEE VALLEY AUTHORITY |
| To: | NRC |
| References | |
| NUDOCS 8708200008 | |
| Download: ML20237K937 (54) | |
Text
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TENNESSEE VALLEY AUTHORITY l
0FFICE OF NUCLEAR POWER t
l SEQUOYAH NUCLEAR PLANT l
MONTHLY OPERATING REPORT d
TO THE NUCLEAR REGULATORY COMMISSION
" JUNE 1987" s
UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 I
1 I
UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER OPR-79 Submitted by:
O L. M. Nobles, Plant Manager
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TABLE OF CONTENTS
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Page I.
Operational Summary Performance Summary 1
Significant Operational Events 1
Fuel Performance and Spent Fuel Storage Capabilities 2
i PORVs and Safety Valves Summary 2
Special Reports 2
Licensee Events 3-4 Offsite Dose Calculation Manual Changes 5
II.
Operatin6 Statistics i
A.
NRC Reports Unit One Statistics 6-8 Unit Two Statistics 9-11 B.
TVA Reports Nuclear Plant Operatin6 Statistics 12 Unit Outage and Availability 13-14 Reactor Histo 6 ram 15 III. Maintenance Summary Electrical Maintenance 16-17 Mechanical Maintenance 18-30 Modifications 31-41 j
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OPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
June 1987 The following summary describes the significant operational activities fer the month of June.
In support of this summary, a chronological log of significant events is included in this report.
The units remained in an administrative shutdown the entire month due to design controi review, configuration control updating, and resolution of significant employee concerns.
Outage related maintenance and modifications are being performed.
Unit 1 has been off-line 677 days.
Unit 2 has been off-line $78 days.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 06/01/87 0001E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
06/30/87 2400E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating, and resolution of significant i
employee concerns continues.
Unit 2 j
Date Time Event 06/01/87 0001E The reactor was in mode 5.
The administrative shutdown due to. design control review, configuration control updating, and resolution of significant I
employee concerns continues, j
t 06/30/87 2400E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
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s FUEL PERFORMANCE Unit 1 l
The core average fuel exposure accumulated during June was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
i Unit 2 The core average fuel expostrre accumulated during June was 0 MWD /MTU with the total accumulated core, average fuel exposure of 8097.51 MWD /MTV.
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 conflict.
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
NoPORVsorsafetyvalveswerechallengedinJune1987.},
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SPECIAL REPORTS The following special report was submitted to the NRC in June 1987.
87-05 Fire detection instrumentation was declared inoperable on.
May 14, 1987, and remained out of service greater than 14 days.
This equipment provides fire detection for several zones on the refueling floor.
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LICENSEE EVENT REPORT (H The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in June 1987.
Description of Event LER 1-85018 Conduits were found penetrating a fire barrier without being Rev. 2 sealed due to a design error in drawings.
This revision changed the completion date for the corrective action and changed the LER to the new format.
1-87025 On May 6, 1987, during a technical review of SI-305.2, " Hydrogen Mitigation System Operability Unit 2," it was determined that SR 4.6.4.3.a acceptance criteria was not being fully implemented.
SR 4.6.4.3.a states that inoperable igniters must not be on corresponding redundant circuits which provide coverage for the same region; however, the SI and TS do not define what constitutes a region.
As a result, it would be possible for two inoperable igniters from different trains to be in the same region.
SI-305.1, " Hydrogen Mitigation System Operability Unit 1," also has the same procedural inadequacy.
The root cause is an inadequate procedure to comply with TS requirements.
The sis for both units will be revised before startup of their respective unit to group the igniters by region, thus meeting the acceptance criteria of SR 4.6.4.3.a.
2-85003 Conduits were found penetrating a fire barrier without being Rev. 2 sealed due to design error in drawings.
This revision changed the ' completion date for the corrective action and changed the LER to the new format.
2-87006 On May 18, 1987, a qualification of the incore monitoring computer program, "INCORE," was being performed due to a recently approved QA requirement.
The qualification by the Core Performance Methods Section (CPMS) revealed an error in the core cycle exposure and height dependent power factor, W(2),
calculation.
For unit 2, cycle 3, Westinghouse provided W(Z) data that required quadratic interpolation.
The CPMS developed an interpolation routine for the INCORE computer program to utilize the new W(Z) data for unit 2.
The interpolation routine produced erroneous W(Z) values for unit 2 core operation beyond 6075 MWD /MTU resulting in improper calculation of the heat flux hot channel factor, Fn(Z), transient limit.
As a result of this error, the July 17 and August 13, 1985 performances of SI-126, " Hot Channel Factor Determination," for unit 2 failed to correctly identify the limiting Fn(Z) transient value.
Although the error was nonconservative, no technical specification limits were exceeded. A recently established requirement for double verification of changes to core monitoring programs should prevent recurrence of this type error. u
[3 ABBREVIATIONS
.l.
ABI'
- Auxiliary' Building Isolation-2.
BAT
- Boric Acid Storage Tank Borop Injection Tank 3.
BIT 4.
' Component Cooling System 1
l5. CRI Control Room Isolation 6.
- Containment Ventilation Isolation
'7.
D/G(s)- Diesel Generator (s) 8.
- Design Change Request 9.
ECCS Emergency Core Cooling System Electromagnetic Interference
- 10. EMI 11.
ERCW Essential Raw Cooling Water 12.
ESF-Engineered Safety Feature j
i 13.
- Flow-Control Valve l
14.
IMI
- Instrument Maintenance Instruction.-
l
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15.
LCO
- Limiti'ng Condition for Operation
- 16. MCR
. Main Control Room
- 17. 'PORC - Plant Operation Review Committee l
18.
19.
- 20. RM
- Radiation Monitor (RAD Monitor) l
- 21. RWST - Refueling Water Storage' Tar.k i
22.
S/G(s)- Steam' Generator (s)
- 23. SI
- Surveillance Instruction /or Safety Injection
- 24. SR Surveillance Requirement 25.
SSPS -- Solid State Protection System 26.
TI
- Technical Instruction 27.
TS
- Technical Specification
- 28. WP
- Workplan
- 29. WR
- Work Request j
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4 0FFSITE DOSE CALCULATION MANUAL CHANGES i
No changes were made to the Sequoyah offsite dose calculation manual during l
the month.
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OPERATING STATISTICS (NRC REPORTS)
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DOCKET NO. 50-327 DATE JULY 8,1997 COMPLETED DY D.C.DUPREE TELEPHONE (615)B70-6722
+-
OPERATING STATUS l
- 1. J UNIT ' NAME: SEGUOYAH NUCLEAR' PLANT, UNIT 1
NOTES:
. 2.
REPORT PERIOD: JUNE 1987
' 3. ! LICENSED THERMAL POWER (MWT):
3411.0 4.
NAMEPLATE RATING (GROSS MWE):
1220.6-
-5.- DESIGN ELECTRICAL RATING (NET MWE):
1148.0
- 6.' MAXIMUM'DEPENDADLE CAPACITY (GROSS MWE):
1183.0 E7.1 MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1148.0
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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 720.00 4343.00 52584.~00 1
- 12. NUMDER OF HOURS REACTOR WAS CRITICAL 0.00 0.00 24444.91.
- 13. REACTOR RESERVE-t HUTDOWN HOURS 0.00 0.00 0.00 j
14. HOURS GENER ATOR ON-LINE 0.00 0.00
-23871.13
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- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 i
^16.
GROSS fHERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.'91' 1'7._ GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-4592.00
-23463.00 24879096.00 j
- 19. UNIT SERVICE FACTOR
- 20. UNIT AVAILABILITY FACTOR 0.00 0.00 45.40 i
^
0.00 0.00 45.40
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 41.21 l
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 41.21. )
- 23. UNIT FORCED OUTAGE RATE 100.00 100,00 43.58
'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. -
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NOTE THAT-THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED.
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-5 t
h SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL i
DCCKET NO.
50-327 UNIT. i, ONE DATE JULY 1, 1987 COMPLETED BY D.
C.
DUPREE TELEPHONE :(6153870-6594 MONTH: JUNE 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWe Net) l 01 0
16 0
t 02 0
17 0
i 03 0
18 0
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04 0
19 0
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20 O
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DOCKET NO. 50-328 DATE JULY: 7,1987 i
COMPLETED BY D.C.DUPREE I
TELEPHONE'(615)S70-6722' OPERATING STATUS 1.
UNIT " NAME: -SEGUDYAH NUCLEAR PLANT, UNIT 2
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. 2. ' REPORT. PERIOD: JUNE 1987 3.
LICENSED THERMAL POWER (MWT):
3411.0
- 4. 3 NAMEPLATE RATING. (GROSS MWE):
1220.6
- 15. L DESIGN ELECTRICAL R ATING (NET MWE):
1148.0 16.
MAXIMUM' DEPENDABLE CAPACITY (GROSS MWE):
1183.0 l
. 7, 4 MAXIMUM DEPENDADLE CAPACITY (NET MWE):
1148.0
-l 8.rIF CHANGES OCCUR =IN CAPACITY. RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE.LAST REPORT,. GIVE REASONS:
l 9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS IF ANY:
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THIS MONTH YR.-TO-DATE CUMULATIVE ils HOURS IN REPORTING PERIOD 72'O. 00 4343.00 44544.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS.
0.00 0.00 0.00
- 14. HDURS GENERATOR ON-LINE 0.00 0.00 21494.42'
- 15.. UNIT RESERVE SHUTDOWN HOURS 0.00
.O.00 0.00
- 16._ GROSS THERMAL ENERGY-GENERATED (MWH) 0.00' O.00 69127977.22
- 17. GROSS ELECTRICAL' ENERGY GEN. (MWH) 0.00 0.00 23536780.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-4761.00
-32081.00 22535442.60
- 19. UNIT SERVICE FACTOR O. OO O.00 48.25 1
- 20. UNIT AVAILABILITY -FACTOR O.00 0.00 48.25
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- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 44.07
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 44.07 j
- 23. UNIT' FORCED OUTAGE RATE 100.00 100.00 45.80 1
- 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:
THE STARTUP OF UNIT-2 HAS DEEN SCHEDULED FOR OCTOBER 1987.
J NOTE THAT. THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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SEQUOYAH NUCLEAR PLANT i
AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 l
UNIT : iTWO I
DATE : JULY 1,1987 i
CQMPLETED.BY D. C. DUPREE i
TELEPHONE :(6153870-6599 MONTH: JUNE 1987 i
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL j
DAY CHWe Net)
DAY CMWe Net)
I 01 0
16 0
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SEQUOYAH NUCLEAR Plant l.'
Period Hours 720 Month JUNE 19 87 Item No.
Unit No.
UNIT ONE UNIT TWO PLANT 1
Averace Hourly Gross Load, kW 0
0 0
2 Maximum Hour Net Generation, MWh 0
0 0
3 Core Ther mal Energy Gen, GWD (tl2 0
0 0
l 4
Steam Gen. Thermal Energy Gen., GWD (t)2 0
0 0
I E
5 Gross Electricat Gen., MWh 0
0 0
3 6
Station Use, MWh 4,592 4.761 9.353 E
7 Net Electrical Gen., MWh
-4.592
-4.761
-9.353 l
8 Station Use, Percent N/A N/A N/A 9
Accum. Core Avg. Exposure MWD / Ton!
0 0
0 6
10 CTEG This Month,10 BTU 0
0 0
11 SGTEG This Month,106 BTU 0
0 0
j 12 13 Hours Reactor Was Critical 0.0 0.0 0.0 1
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 g
t*
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 g
24 Gross Heat Rate, Btu /kWh N/A N/A N/A j
25 Net Heat Rate, Blu/kWh N/A N/A N/A M
26 Y
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature, F N/A N/A N/A y
30 Exhaust Pressure, InHg Abs.
N/A N/A N/A E
31 Intake Water Temp., F N/A N/A N/A F
32 J3_.
Main Feedwater, M lb/hr N/A N/A N/A
$ _ __34 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 j
39 Oil Fired for Generation, Gallons 2,310 22 40 Oil Heatin1 Value. Blu/ Gal.
138,000 41 Diegel Generation. MWh 35 O
Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
a 43 N/A N/A N/A N/A N/A N/A O
Remarks: IFor BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermat Energy.
3 m
4 Date Submitted. JUL 1 5 1987
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MAINTENANCE SUM"ARY (MECHANICAL)
I
MECHANICAL MAINTENANCE MONTHLY REPORT FOR JUNE 1987
)
s COMMON 1.
Continued hanger bolt tightening deficiency resolution.
2.
Completed A-train metrix valve changeout.
3.
Completed posting of warning signs at all interlock doors.
4.
Completed repairs on "A" auxiliary boiler.
5.
Continued repairs on control building roof.
6.
Submitted detailed schedule for retubing of "B" auxiliary boiler.
7.
Continued 51-233.1 penetration inspection.
UNIT 1 l
1.
Continued reassembly of turbine generator.
l UNIT 2 1,
Continued walkdown to identify missing mirror insulation in primary containment.
2.
Completed removal of all lower containment air cooler coils.
3.
Completed replacement of feedwater elbows.
4.
Completed review and approval of MI-6.15 for replacement of pressurizer code safeties.
5.
Continued replacement of Hoke valves for post-accident sample system, 6.
Started SI-106 - Ice Weighing.
7.
Started S1-162.1 - Snubber Visual Inspection.
8.
Started SI-191.2 - Fire Hose Station Inspection.
9.
Continued maintainence on equipment condition evaluation program.
- 10. Completed repairs on 2-FCV-74-3.
OTHER 1.
Completed suitability evaluations for old ASME Section XI work packages.
2.
Continued S1 and M1 review and revisions to support startup.
3.
Continued efforts to reduce WR backlog.
4.
Continued equipment condition evaluation report support for restart.
5.
Continued NMRG, INPO, and NRC action items for restart.
6.
Continued evaluation of employee concerns, 7.
Completed workplan and detailed schedule to retube "B" auxiliary boiler.
8.
Completed workplan and detailed schedule for replacement of lower containment air cooler coils..
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s MAINTENANCE
SUMMARY
4 (M00lflCATIONS) l l
l 1
---__---.__________u
k 9'O 1
4
SUMMARY
OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS JUNE 1987 i
e Major Capital Projects:
1 i
PN7101:
ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan 12223 in process pending safe access to current transformers.
PN7102:
ECNs 5938 - Replace Feedwatee Heaters 3 and 4 Preparation work is underway as time and manpower permit.
Installation of the monorail on unit 2 continues in preparation for the changeout of feedwater heaters 3 and 4.
Structural steel reinforcement continues on unit 1 heaters 3 and 4.
This work will be moved out possibly into FY 1988.
PN7105:
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel Th9 vorkplar for the replacement of unit 1 isolation valves is not scheduled to begin until later in the fiscal year.
Some insulation activities remain incomplete.
PN7106:
ECNs 5034 and 5743 - Various Platforms in Lower Containment j
Additional safety gates are to be installed on unit 2.
Upgrading of be,1 ting material in work by Warehouse Material Group.
PN7108: ECN 6720 - Crane Consistency Program Unit 2 polar crane modification is complete.
Postmodification testing (PMT) by Electrical Maintenance remains.
Unit 1 polar crane work. started July 6.
PN7115:
ECN 6719 - Volumetric Intrusion Detection System Installation complete.
Preoperational checkout by security to be scheduled.
1 PN7122:
DCR 1373-- Secondary Side I
Steam Generator Preservation ECN 5657 - Installation of MSR Drain Valves Work is essentially complete on all the ECNs.
Some minor insulation installation activities are in process. There may be some small changes to complete this project in FY 1987.
q PN7123:
ECNs 5938, 6305, 6571 - Replace Feedwater Heaters 1 and 2, Units 1 and 2 a:m Eroded Pipe Modifications Group B is supporting PMT on heaters 1 and 2 on both units as requested.
Insulation work on unit 1 continues.
f _._______ _____________- ____
a
i i
e l
Major Capital Projects (cont.):
PN7130: DCR 1156 - Post Accident Monitoring i
This work has slipped to allow work to continue on priority unit 2 restart efforts.
NRC commitment on NUREG 1.97 calls i
for unit 1 completion by Septem'ber 1987 and unit 2 by U2C4.
A request has been sent to the NRC to move the unit 1 completion date to U2C4.
PN7136: ECN 6259 - Moisture Separator Reheater (MSR) Tube Bundle Replacement Complete except for PMT, inservice leak test', and scaffold removal.
PN7152:
ECN 6808 - External Conduit Sealing Unit 2 work complete. Unit 1 workplan in approval cycle.
PN7159: Appendix R ECN 6300 - Additional Sprinklers and Draft Stops 4
All mechanical work complete. Waiting on Electrical Modifications to finish for composite testing of system, s
PN7161: ECN 5855 - Replacement of Doors A56 Installation of door A56 was completed. Work on door A57 has been deferred.
A57 project has yet to be authorized.
s ECN 6300 - Sensors and Detectors Installation of PC modules and functional test remains.
Modules duo July 8, 1987.
External c'aduit sealing in process.
PN7181:
DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste Buildin6 Interface potable water and fire protection in process.
Electrical interface in process.
JGC vendor representative due July 6, 1987 to start equipment installation.
PN7199: Miscellaneous Activities Under $100,000 This is for various work orders prepared for work under
$100,000 total site cost. This work is done as manpower s
resources are available that will not impact unit 2 restart effort. __
i P.
'Significant Itemc:
'The following major significant items are under Operation and' Maintenance Expense (0&M) and will continue to be until restart of unit 2.
1.
Fuse Program Work.
l ECN 5880 - Additional tagg' t identified by DNE in process.
ECN 6854 - Workplan complete.
Valve cycling test by Operations scheduled to complete July 10, 1987.
j 2.
Main Steam Valve Vault Cable and Insulation Work, All cables have been replaced. Functional tests are held for
)
delivery of resistors for surge networks.
Completion of functional tests is expected to be July 15, 1987.
)
^
ECN 6809 - MSVV Insulation The workplan for insulation continues in progress. Work is j
continuing on the resolutior, of interferences, i
3.
Cable Ampacity Program.
Unit 2 complete.
Unit 1 in progress.
l 4,
Raychem Cable Splicing Work.
l There have been 966 of 973 splices replaced.
Current l
1 completion is scheduled for July 15, 1987.
i NOTE:
Financial Planning is in process of transferring funds to cover items 3 and 4.
This will be an increase in O&M expense.
07/07/87 0120K/pam
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Other Items:
'l ECN 5095 - Modify Test Drain and Verify Connectors of Various 1
s Containment Isolation Valves i
A workplan was written', approved and worked for installation of nipples and caps on valves required for startup of unit 2.
Additional drawings
~
are to be, issued documenting current fi6ld. configurations.
]
ECN 5435~- Fire Doors i
The installation of weather stripping, continues as resources permit.
j
'ECN 5111 - Remove Power From Old Carpenter Shop at Dry Active Waste
-Building Modifications Group C is holding the completion of this ECN until the completion of the Dry Active Waste Building. Power is needed for construction power.
L-ECN 5111 - Provide permanent power to manholes 42-46..
Electrical conduit and wiring installation for manholes 44, 45, and 46 complete per Workplan 12262.
Manholes 42 and 43 held for information from DNE on power cable routing and terminations.
ECN 5503 - Fire Detection System O&PS Building Workplan.In process.
'ECN 5599 - Conduit Supports for Fifth Vitel Battery and Waste Disposal Area Workplan 12186 in hold for fifth vital battery area supports.
Information needed from DNE on flex conduits. Workplan for waste disposal area held for issue of ECN by DNE to' include FCR 4753.
i ECN 5609 -~ Air Compressors Makeup Water Treatment Plant Installation complete.
Kit being installed for oil sight glass to prevent' oil leakage.
ECN 5626 - Containment Ladders, Unit 1 Workplan being written to incorporate this ECN.
Need additional design information to complete.
ECN 5676 - Diesel Generator Air Tank Valves
)
Workplan in closure cycle.
ECN 5713 - Various Platforms in Lower Containment The remaining trollies have been shipped to the vendor for modification.
Work will continue'when the trollies are returned.
_u.
.'Othtr' Items-(cont.):
ECN 5726'- CAQR.SQP870478 - Rsroute Sense Line Piping for Train
. Separation to, Panels 2-L-58 and 2-L-68 A workplan was written,. approved, and work started.
ECN 5743'- Ladders In Containment
~A workplan to insta11' additional safety gates was approved.
Held for
' upgrading.of bolt material by Warehouse Materials Group'.
ECN 5779 - Upper Head Injection (UHI) Bypass Leak check completed, and the workplan is in the process of being closed.,
ECN 5841 - Hot Shop Fire Detectior, Workplan in process.
ECN 5935 - Correct Power Block Lighting Deficiencies
~Workplan approved'for partial work.
Not'all drawings have been i
received from DNE. All work held pending approval of work order expenditure by Financial Planning Section.
ECN 5977 - Steam Generator Blowdown Demineralized
' Installation of SGBD tank tie-ins was completed.
ECN 6005 - Replacement of AFW Air Ejector The workplan.is complete except for leak check to be done by SI-130.1 in mode 3.
ECN 6014 - Replacement of ERCW Pump Bearing Piping Work was completed. Maintenance requested MODS support in cutting out cooler coils and rewelding three of four pumps complete.
ECN 6057 - Cable Tray Covers-This work on hold pending evaluation of cable. tray efforts with respect l
'to cable ampacity.
1 ECN 6147 - Airlock Packing Nut l
Final testing of the airlocks on unit 2 remains incomplete'(prior to mode 4).
ECN 6185 - Offsite Paging Systdm Functional tests of the remote mobile units remain to be completed.,
... ~
e Other Items (contd.):
~*
ECN 6196 - Pressurizer Hangers and Valves PMT is-incomplete and scheduled for startup. 'Two supports identified by DNE EA Review. Require limited amount of work.
l ECN 6204 - Electrical Penetration Overcurrent Protection
-l Complete.
i ECN 6380 - Replacement of Barton P assure Transmitters Fieldwork complete.
Final closure awaiting instruction revision by Instrument Maintenance.
1 ECN 6357 - ERCW Roof Access and Rails for Security Equipment Workplan 12238 held for DNE approval of FCR showing installation i
details. No new date for release of approved FCRs or drawings by DNE j
has been established.
ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation In-service tests will be performed when the system is brought up to l
I temperature and pressure.
ECN 6437 - Replace FE-2-265, and 257 Work is field complete. Calibration is being done by Instrumentation Maintenance.
ECN 6455 - Upgrade CU-3 Box Battery Packs Workplan issued. Work in process by Electrical Maintenance.
ECNs 6491 and 6534 - ERCW Supports All hangers currently identified have been completed. A documentation workplan incorporating the final ECN 6534 drawings was. approved.
Changes submitted for affected plant instructions are in progress. A review is in progress to ensure all unit 2 restart work has been completed for both ECNs.
l ECN 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from DNE.
ECN 6601 - Removal of Unit 1 EGT9 Backdraft Dampers PMT remains to be completed by the Engineering Test Section.
Modifications fieldwork complete.
f - _ _ _ _ - _ _ _
i j
6.
Other Items (cont.):
(
ECN 6610 - Modify Air Return Fan Supports Unit 1 work is incomplete.
)
ECN 6631 - Modify Snubbers Work remains on three UHI supports which require the lines to be filled with water. Operations is continuing efforts to fill the line.
I ECN 6661 - Upgrade of ERCW Piping f
Fieldwork was completed. Workplan is being reviewed for closure.
ECN 6689 - Relocation of Main Steam PORV I
Initial fieldwork was completed. DNE evaluating design. More work may I
be required.
ECN 6698 - Repull 120-Volt Cables Unit 2 complete.
Unit 1 la 90% complete and held by ECN 6742.
ECN 6700 - Anchors Near Free Edge Fieldwork complete. Workplan in closure review.
ECN 6706 14 Support Enhancement A late addition to the unit 2 scope was received and repairs are in
{
progress.
Repairs continue on unit 1.
Initial inspections for unit 1 lack approximately three supports for completion.
Unit 1 evaluations
)
are continuing. DNE is evaluating contract proposals for unit I work.
1 Documentation review of unit 2 work is in progress.
ECN 6707 - Replace System 74 Flow Switches Switches will have a new setpoint based on another ECN. The installation will be complete after the flow transmitter is removed from the existing workplan.
ECN 6715 - D/C Random Loads Both trains complete.
Holding for PMT.
f ECN 6717 - Stub Bus Fuses Workplan is complete.
ECN 6739 - Alternate Analysis 4
All identified fieldwork is complete.
Documentation review is in progress. DNE is evaluating contract proposals for unit I work.
_n.
e' e
1 Other Items-(cont.):
I ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits Workplan is. complete for unit 2.
Unit'l is 50% complete.
Instrument Maltenance cannot support until early August.
ECN 6752 - Modification of P.D. (Anchor Problems)
Fieldwork is complete. Workplan being closed.
r ECN 6761 - East Valve Room (EVR) Blowout Panels Implementation of unit 1 work is progressing as resources are available. Additional work on a unit 2 EVR door is in progress.
ECN 6768 - Rework Cable Tray Hangers Workplan is complete.
ECN 6783 - Replace Motor on 2-MOV-70-87 This ECN is superseded by ECN 6858.
Regear is complete.
Second regear is complete. Waiting on leak test.
ECN 6784 - Documentation to Show Pipe Class Breaks l
Resolving QA comments from QA Review for approval cycle. Additional drawings were added during this period.
ECR 6790 - Medium Energy Pipe Break i
This work has been determined nonrestart and will be scheduled for later work periods.
ECN 6791 - Pipe Clamp Replacement The workplan continues in work.
ECN 6802 - Modify EGTS Filter Housing j
Fieldwork is complete. Completion is awaiting PMT by test group.
ECN 6808 - Conduit External Sealing l
The workplan for conduit sealing is complete for unit 2.
Unit 1 workplan in approval cycle.
ECN 6810 - Rework Category "C" Devices Complete.
ECN 6812 - Backup Control Room Cable Reroute Complete.
e Other Items (cont.):
i ECN 6848 - Thermal Expansion Problems With Platforms Fieldwork is complete.
Functional testing is in progress.
ECN 6851 - Thermal Expansion Problems With Hangers Additional work has been identified by DNE.
ECN 6866 - Modification of Valve Room Doors The mechanical workplan is in work.
ECN 6871 - External Conduit Sealing DGB/CB/ERCW Workplan in process.
ECN 6874 - CVCS Heat Trace Power Circuits Complete.
ECN 6878 - Replace PS and TS SYS 32 Compressor B complete; however, ECN 7194 for setpoint change needs to be issued in order for resetting pressure switches before Compressor B can be completed.
ECN 6893 - Install New Air Regulators Workplan was approved and work started.
l ECN 7000 - Addition of Support to Main Steam Dump Header Fieldwork is complete except final inspections during heatup.
ECN 7078 - Install Hangers - Main Steam Piping t
Complete except for final inspections during heatup.
ECN 7089 - ERCW Check Valve Replacement j
Fieldwork was completed.
SI-158 has to be performed.
ECN 7092 - Capping of Spare Sleeves in Unit 2 Shield Building Preliminary coordination with DNE was started.
Restart determination 1
has not been completed.
1 1
ECN 7095 - Sleeve Installation On Shield Building Preliminary coordination with DNE was started. Craft installers and inspectors certified by vendor.
Problem with pipe movements. May require rigorous analysis on I&C.
,.y i
6-rdther' Items (cont.):
t ECN 7102 - Control Air Line Plugging-1 l
Work'was completed.
j ECN 7110 - Relocate AFW Controllers Mechanical workplan was approved and work started.
Electrical work in process.
ECN 7134 - Raise Operator of RHR Valve 2-FCV-74-1 above Flood Level Preliminary coordination with DNE was started. New valve stem not expected to be delivered until late August.
l l
'ECN 7137 - Lost Calculation Hangers A workplan for 15 hangers is in progress.
ECN 7141 - Lost Calculation Hangers
'Workplan,for four hangers was approved and work started.
j ECN 7147 - Lost-Calculation Hangers Workplan for seven hangers written, approved and work started.
ECN 7228 - Lower Comp. Cooler Duct Supports A workplan was written and placed in the approval cycle.
DCN X00002A - Modify RCP Platform.(CAQR #SQP870177R1)
A workplan was written and placed in the approval cycle.
ADP Additional Lights to Parking Lot No. 2 (DCR 2260) l Workplan 12208 written, but held for design drawings.
Temporary lights installed.
i Procedure Revisions Many manhours were spent revising procedures (M&AI's),
i Control Room Bullet Resistivity - DCR 2268 - ECN 6860 i
Boundary redefined. Hold for issue of revised drawings.
l Startup Activities List SAL. Closure - Many manhours spent closing these items.
l
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i i
3 l
S
- Other Items (cont.):
l Appendix A - Internal Conduit Sealing Work in progress. Completion being rescheduled due to fire detector hehd sensitivity test requirements.
Instrumentation Verification program There have been 823 discrepancies identified to date with 397 not required for restart.
Remaining being worked on WR packages.
i DCN 4B - RHR rework of root valves in process.
Collection pot rework held for revision of USQD.
DCN 7A Miscellaneous slope adjustments held for DCN and USQD DCN 9A revision.
DCN 14A - Additional collection pots held for issue of DCN and USQD.
ECN 7171 - (Unit 2) Workplans approved. Work held for SI-26 completion.
ECN 7172 - (Unit 1) Workplans approved. Work held for SI-26 completion.
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j F - -' $ -
TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant
/
P. O. Box 2000 SodR -Daisy, Tennessee 37379 L
4 t.
July.15. 1987-Nuclear Regulatory Cornmission Office of Management Information and, Program Control Washington, DC 20555 Centlemen:
D SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - JUNE 1987 i
l Enclosed is the' June 1987 Monthly Operating Report to NRC for Sequoyah
- Nuclear Plant.
l 1
Very t'ruly yours, l
TENNESSEE VALLEY AUTHORITY j
Y AW L.
M.~ Nobles Plant Manager i
Enclosure cc (Enclosure):
l Director, Region II Nucicar Regulatory Commission
)
Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, Georgia 30323 (1 copy) l Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. T. Marston 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) i Ik Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant An Equal Opportunity Employer l}