ML20236W145
| ML20236W145 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/30/1987 |
| From: | Dupree D, Nobles T TENNESSEE VALLEY AUTHORITY |
| To: | NRC |
| References | |
| NUDOCS 8712070300 | |
| Download: ML20236W145 (49) | |
Text
.S TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 5
SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION
" SEPTEMBER 1987" l
l UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 l
UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l
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Submitted by:
L. M. Nobles, Plant Manager l
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8712070300 870930 ADOCK0500g7 DR i
s TABLE OF CONTENTS Page I.
Operational Summary Performance Summary 1
Significant Operational Events 1
Fuel Performance and Spent fuel Storage Capabilities 2
Spent Fuel Pit Inventory 2
PORVs and Safety Valves Summary 2
Special Reports 2-3 Licensee Events 4-9 Offsite Dose Calculation Manual Changes 10 II.
Operating Statistics A.
NRC Reports Unit One Statistics 11-13 Unit Two Statistics 14-16
/
B.
TVA Reports s
Nuclear Plant Operatin6 Statistics 17-18 Reactor Histogram 19
, Unit Outage and Availability 20-21 Ma$ntopteeSummary III.
Instrument Maintenance 22-25 Mechanical Maintenance 26 Modifications 27-39 I
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OPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
l September 1987 The following summary describes the significant operational activities for the month of September.
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 control review, configuration control updating, and resolution of significant employee concerns.
Outage related maintenance and modifications are being performed. Unit 1 has been off-line 769 days.
Unit 2 has been off-line 770 days.
Preparatations are underway for unit 2 alignment and mode 4 verification.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 09/01/87 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.
09/30/87 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.
Unit 2 Date Time Event 09/01/87 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.
09/20/87 2130E Condenser vacuum established in preparation of system alignment and heatup.
09/30/87 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 Preparations are underway for system alignment for mode 4 shakedown.
1
FUEL PERFORMANCE l
Unit 1
~The core average fuel exposure accumulated during September was 0 MWD /MTV with the total accumulated core average fuel exposure of 0 MWD /MTV.
Unit ?
The core average fuel exposure accumulated during September was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.
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.
SPENT FUEL PIT INVENTORY A complete inventory via cassette tape of all 348 spent bundles was performed by Reactor Engineering Section personnel on September 16, 1987.
This inventory was performed to meet a plant instruction (TI-1) requirement to perform an inventory of fuel at least every twelve months.
No discrepancies were observed.
NOTE: An inventory of new fuel in the new fuel storage vault was performed on August 6, 1987.
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PORVs AND SAFETY VALVES
SUMMARY
No PORVs or safety valves were challenged in September 1987.
SPECIAL REPORTS The following special reports were submitted to NRC in September 1987.
87-10 On August 14, 1907, fire breaches issued on August 7, 1987, for fire doors A77 (to air lock room, Auxiliary Building elevation 690) and A78 (to annulus, Reactor Building unit 2 elevation 690) exceeded the seven-day limit allowed by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.12.
The fire breaches were issued to keep the doors open to support leak rate testing on nonessential control air containment isolation check valve 2-CKV-32-387. This report is required in accordance with TS 3.7.12.
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SPECIAL REPORTS (continued)
I 87-11 On August 21,1987, at 1500 EST, the meteorological instrument for wind direction was declared inoperable.
The meteorological l
instrument was returned to service at 0930E on August 30, 1987.
This report is required in accordance with TS 3.3.3.4 as a result of the i
instrumentation being inoperable greater than seven days.
87-12 On September 11,1987, at 1530 EST, the meteorological displays in j
the main control room were declared inoperable.
The meteorological j
instrumentation was not returned to service.
The action statement j
for LC0 3.3.3.4 requires a special report to be submitted, as a j
result of the meteorological instrumentation being inoperable greater than seven days.
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a.
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in' September 1987.
Description of Event LER l-87041 On August 4 1987, at 2149 EST. with unit 1 in mode 5, a momentary
-loss of RHR flow occurred wnen valve 1-FCV-74-2 inadvertently-closed, isolating RHR pump 1A-A suction from the RCS loop 4 not leg..The control room operator was immediately. alerted to this condition by annunciation of the RHR high discharge miniflow alarm.
The operator assessed.the position of RHR suction valve 1-FCV-74-2 and manually stopped RHR pump 1A-A.
LCO 3.4.1.4 was entered and A01-14, " Loss Of RHR Shutdown Cooling," was.placed in effect for use in recovery operations.
RHR loop A flow was reestablished at 2153 EDT on August 4,1987, by reopening valve 1-FCV-74-2 and restarting RHR pump 1A-A, at which time LCO 3.4.1.4 was exited.
The RHR system isolation was caused by personnel error during initial plant. lineup for performance of IMI-99, " Response Time Testinh (RT) 699B".
A student AU0 was dispatched to 120V Vital Instrument Power Board 1-II with the initial alignment checklist (Attachment A to IMI-99 RT-6998) to verify the position of breaker 2 (the checklist called for the breaker to be closed). The AU0 trainee, for no explainable reason, opened the breaker and then, realizing his mistake, closed it back.
Opening the breaker deenergized separation relay PB403BX, whose function is to close isolation valve 1-FCV-74-2 on a high RHR system inlet pressure from the reactor coolant system.
1-87049 On December 1,1986, an SCR was initiated describing a condition in which the motor overloads were improperly sized on, motor-operated valves (MOVs) and other safety-related low-voltge. induction motors.
There was no assurance, during a condition in which the voltage was near the degraded voltage relay setpoint and the ambient temperature was at the upper limit of the design basis (104 degrees F), that the installed overloads would allow the motor starters to perform their safety-related action.
The overloads were installed without considering minimum voltage level and were sized to protect the valves in the event that they malfunctioned, rather than ensuring that the safety function was fulfilled.
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C Description of Event LER 1-87049 Additionally, the thermal overload protection devices have not yet (cont.)
been functionally tested at 104 degrees F.
The root cause of this condition was an inadequate procedure during construction.
The-construction engineers selected overloads from a procedure provided by Design that was not adequate to ensure that the overloads would allow tne motors to perform their safety-related action without uncertainties.
No operator action was required because both units-are in mode 5.
To provide'an adequate margin of safety that the overloads will not prevent the motors from performing their safety function, they have been replaced with either larger overloads or a copper strip. These loads from which the overload heaters have been removed (MOVs) will be periodically tested, utilizing the Motor-0perated Valve Analysis Test System (MOVATS). The modifications that were necessary to support unit 2 restart are now complete. Those needed for unit 1 will be completed before unit i restart.
To prevent recurrence, overload heaters are now controlled by design drawings, and procedures have been established that would require analyses or calculations to be performed to support aay design changes affecting overload heaters.
1-87051 On August 12, 1987, during an ERCW system inspection by NRC, it was determined that certain skid-mounted valves associated with safety-related equipment were not being checked for proper position on a 31-day interval as required by TS SR 4.7.4.a.
A subsequent walkdown of safety-related pumps and equipment associated with the component cooling water system identified additional skid-mounted valves that were not checked as required by TS SR 4.7.3.a.
The root cause of this problem was the original administrative position of considering skid-mounted valves as part of the equipment. As a result, the valves were not denoted on the drawings that were used when writing the 510, and were not considered within the scope of the TS SR.
Safety-related skid-mounted equipment is being reverified to ensure that skid-mounted valves requiring a 31-day surveillance to comply with TS 3.7.3 and 3.7.4 are identified.
sis will be revised to add these valves and the valves checked for proper posiiton. These corrective actions will be completed before restart of the respective unit.
1-87054 On August 10,1987, at 1100 EST, it was necessary to remove f rom service train B CRI RM-90-126 to perform SI-83, " Channel Calibration for Radiation Monitoring System," because the TS SR for channel calibration was due.
Train A CRI RM-90-125 was inoperable because of a high voltage special test performance on selected lE cables with potential for cable pullby damage. The cables being tested were in the output circuitry of the RM-90-125. With both trains inoperable, TS LCO 3.3.3.1, action b, required within one i
hour to initiate and maintain operation of CREVS in the recirculation mode of operation.
This c7uld not be accomplished because both trains of the CREVS were inoperable pending resolution of a design deficiency previously reported by LER SQRO-50-327/87039.
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Description of Event LER 1-87054 The root cause of this event was a combination of the SR being due J
(cont.) on RM-90-126, the required high voltage testing being performed on S
RM-90-125, and the design deficiency on the CREVs all existing concurrently.
RM-90-126 was returned to service at 1645 EST on August 10, 1987, and the high voltage testing was completed on RM-90-125 and it~was returned to service at 1138 EST on August 19, 1987.
Recurrence of this event is not expected.because j
the special testing on RM-90-126 was completed, and corrective l
actions are being taken to restore the CREVS to an operable status.
L l-87055 This report was submitted as a voluntary LER to identify a potential problem with the Sequoyah auxiliary feedwater (AFW) system.
On February 17, 1987, Sequoyah plant personnel were notified of SCR-SQNEEB8743, Revision 0, which identified that a loss of water supply to the AFW system may occur as the result of the inadequate routing of pressure switch sense lines.
The AFW system function is
'to supply feedwater flow to the steam generators so that reactor coolant' system stored heat and reactor decay heat can be dissipated through the main steam system steam relieving features.
The cause of this condition has been determined to be inadequate design output specifications for installation of instrument lines.
No immediate corrective action is required based on the AFW system not being required in the present mode of operation (mode 5) for both units.
ECNs are presently being implemented to resolve the installation deficiencies applicable to units 1 and 2 pressure switches sense lines for the motor-driven AFW pumps.
1-87056 With both units in mode 5, the listing of secondary containment
~ bypass leakage paths (Table 3.6-1) was determined'to be deficient on August 11, 1987, and was determined to be potentially reportable.
This table, which specifies the penetrations for consideration in determining the combined bypass leakage rate for LC0 3.6.1.2.c, was found to be incomplete because of its failure to include all of the potential bypass leakage paths to the auxiliary building for the current plant configuration.
By using the incomplete list in the past, the potential existed for exceeding the TS allowable limit for combined bypass leakage.
Both units contain this deficiency.
The errors in the TS bypass leakage table resulted from a lack of specific design criteria defining secondary containment bypass penetrations. When a design basis for the TS list'cedid not be found during a recent design review, a new basis was 'r/aloped that identified an additional 26 penetrations that met the definition of bypass leakage path to the auxiliary building.
TSs are being revised to add 26 additional penetrations to Table 3.6-1, and appropriate surveillance instructions will be revised to reflect the proposed technical specification change..
i Description of Event LER l-87059 On August 31,1987, at 1300 EST, an extensive review of past records, plant equipment, and storage locations, performed as a result of sealed source inventory deficiencies identified at TVA's Browns Ferry Nuclear Plant, revealed that Sealed Source No. 283N had been used by the Instrument Maintenance Section for a source
. check.
This source had not been tested for alpha contamination before use as required by TS SR 4.7.10.2.b.
On September 9,.1987,
.it was also discovered that Sealed Source No. 662N had not been tested for alpha contamination on the previous SI-56, " Byproduct Material Inventory and Sealed Source-Leak Test Units 1 and 2," as required by TS SR 4.7.10.2.a.
Further reviews indicated that other sealed sources had not been properly inventoried and controlled by 51-56.
This SI is controlled and documented by the Chemistry Section.
However, some byproduct material' sealed sources are accessible to other plant personnel.
In addition, Radiological Control performs the actual checks for leakage. Thus, while personnel error contributed to these deficiencies, the governing root cause for the Sequoyah events has been determined to be a less than adequate accountability for the TS SR.
Upon d'iscovery of each of t'hese conditions, each source was checked for alpha, beta, and gamma contamination.
SourcemNo. 283N was also added back to the inventory.
Other byproduct material sealed sources will be. inventoried and checked as necessary by October 30, 1987.
Accountability for byproduct material sealed sources and SI-56 is being transferred to Radiological Control, which is consistent with common industry practice.
1-87060 On August 27,1987, at 1140 EST, an inadvertent start of three of the four D/G units (1 A-A, 2A-A, and 28-B) occurred while cutting tie-wraps in the shutdown board IB-B auxiliary compartment during the performance of Special Maintenance Instruction (SMI) 1-202-4,
" Replacement of GE PK Block Study on 6.9 kV Shutdo'wn Board 188, Panel 17."
In performing the instruction, an electrician was using a knife to cut the tie-wraps when the knife blade came into contact with two bare energized studs.
The short-circuit across these studs jumpered dc power directly to the trip coil of the normal feeder breaker for the 18-8 shutdown board.
The resulting trip of the shutdown board supply breaker caused a blackout condition at the shutdown board, which in turn started all of the operable D/Gs.
All D/9s were shutdown; however, during shutdown of the lA-A D/G, a malfur,0 tion of the governor caused the diesel to trip on overspeed.
The 1A-A D/G was declared inoperable, and the applicable LCOs were entered.
At 1208 EST, the overspeed trip
)
mechanism for D/G 1A-A was reset and the related LCOs were exited.
The root cause of the 0/G start was an inadequate procedure.
The procedure did not require the energized studs to be deenergized or insulated from an inadvertent contact with tools and personnel, nor the shutdown boards to be isolated from the D/G's circuitry.
During the remainder of the performance all precautions were taken to prevent recurrence.
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a Description of Event LER 1-87061. On August 31, 1987, at 0730 EST, it was determined during a calculation review that, in several cases, a fault on Appendix R-associated circuits could cause a required circuit to be interrupted on the 125V dc vital battery boards.and 480V shutdown boards.
This was because of improper fuse / breaker selective-coordination of circuits with a common power supply.
The design cable length values were used when sizing fuses and breakers.
The actual conr.tructed cable lengths were not evaluated to determine the effects on fuse / breaker coordination used to protect required circuits in the event of a fault.
The actual constructed cable lengths were found to be nonconservative.
The identified circuits have been evaluated, and corrective actions to obtain proper selective coordination will be c'ompleted before restart.
To prevent recurrence, Procedure Method (PM) 87-26 (EEB),
" Cable length Values to be Used in Electrical Calculations," has been written to ensure design lengths are not improperly used, and Sequoyah Engineering Procedure (SQEP) 34, " Procedure for Implementation of the Electrical Fuse Tabulation," has been' written to prov,ide fuse coordination.
2-87007 On August 15, 1987, it was determined that a potential reportable event had occurred for unit 2.
The following conditions were identified for train A of the containment hydrogen analyzer system:
1.
The sample line to lower containment was partially plugged with a foreign material.
2.
The upper containment sample line was not installed as required by design drawing, preventing proper sampling.
3.
A low point in the field-routed line, resulting in a condensate trap, was discovered that could potentially cause the inlet pressure drop to exceed the vendor's recommended maximum limit.
These conditions were discovered as a result of recent efforts by TVA and the analyzer manufacturer to resolve calibrational problems.
The cause of the plugged sample line (which has been unplugged) has not been determined.
The excessive condensate trap was due to insufficient j
installation instructions.
The cause of the lack of an upper containment train A sample line is a construction installation deficiency.
Upper containment sample tubing has been installed, and the condensate trap has been removed by rerouting of the sample tubing.
Procedures will be performed before restart to ensure physical changes have not affected the hydrogen analyzers calibration or containment pressure boundary integrity, respectively. The unit 1 hydrogen analyzer system will be verified in detail for similar deficiencies. _ - _ _ _ _ -
ABBREVIATIONS g.
'l.
ABI
- Auxiliary Building Isolation 2.
- Auxiliary feedwater 3.
AOI
- Abnormal Operating Condition l
4.
BAT
- Boric Acid Storage Tank
{
5.
BIT
- Boron Injection Tank j
'6.
- Component Cooling System 7.
CRI
- Control Room Isolation 8.
CREV Control Room Emergency Ventilation System 9.
- Containment Spray System.
- 10. CVI Containment Ventilation Isolation 11.
D/G(s)- Diesel Generator (s)
- 12..DCR
- Design Change Request 13.
- Division of Nuclear Engineering 14.
ECCS Emergency Core Cooling System 15.
ECN Engineering Change Notice 16.
EGTS Etnergency Gas Treatment System 17.
- Electromagnetic Interference 18.
ERCW Essential Raw Cooling Water 19.
ESF Engineered Safety Feature
- 20. FCV
- Flow Control Valve 21.
FSAR - Final Safety Analysis Report 22.
IMI
- Instrument Maintenance Instruction 23.
LC0
- Limiting Condition for Operation 24.
LOCA - Loss Of Coolant Accident
- 25. MCR
- Main Control Room 26.
PORC Plant Operation Review Consnittee 27.
- Reactor Coolant System 28.
- Residual Heat Removal 29.
- Radiation Monitor (RAD Monitor / RAD MON) 30.
RWST - Refueling Water Storage Tank
' 31.
- Significant Condition Report 32.
S/G(s)- Steam Generator (s)
- 33. SI
- Surveillance Instruction /or Safety Injection
- 34. SQN
- Sequoyah Nuclear Plant
- 35. SR
- Surveillance Requirement
- 36. SSPS - Solid State Protection System 37.
TACF - Temporary Alteration Control form 38.
TI Technical Instruction
- 39. TS(s) - Technical Specification (s)
- 40. WP Workplan i
t OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the month.
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OPERATING STATISTICS (NRC REPORTS)
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c r.x r 4 l in Dain n tW L,n i DOCKET NO. 50-327 DATE OCTODER 09,1987 COMPLETED BY D.C.DUPREE TFLEPHONE (615)870-6722 CFERATING STATUS 1.
' UIT NAME: SEOW V AH NUCLEAP PLANT, UNIT 1
NOTES:
2.
S EP CR T PER IOD. c E P T Ei c r.;
1987 3.
'ICENSED THERruL FCWE~ nWT) 3411.O 4.
NAMEPLATE RATIN3 (GRO5: MWE '; :
1220.6 5.
DESIGN ELECTRICAL RATING (NET-MWE):
1149.0 6.
MAXIMUM DEPENDADLE CAPACITY (GROSS MWE):
1183.O 7.
MAXIMUM DEPENDADLE CAPACITY (NET MWE):
1148.0 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE. LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS.IF ANY-:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 6551.00 54792.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91
- 13. REACTOR RESERVE SHUTDOWN HOURS O.00 O.00 O.00 14 HCURS GENERATOR ON-LINE O.00 O.00 23871.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 O.00 O.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
- 17. GPOSS ELECTRICAL ENERGY GEN. (MWH)
O.00 O.00 25976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
-4562.00
-36738.00 24865821.00
- 19. UNIT SERVICE FACTOR O.00 0.00 43.57
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 43.57
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 39.53
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 39.53
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 46.38
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
25, 5F SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CCNFI GUR ATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT EPPLOYEE CCNCERNS.
NOTE 1 HAT THE THE YR.-TO-DATE AND CUMUL ATIVE VALUES HAVE DEEN UPDATED. ___
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-CiERATING DATA REPCRT DOCKET.NO. ~ 50-328 DATE OCTODER 09,1987-g COMPLETED'DY D.C.DUPREE L
TELEPHONE 1(615)S70-6722 OPERATING. STATUS l.
1.
"IT NAME.EEGUdYAH NUCLMN' LANT, UNIT 2
NOTES:
- 2. i b 70R T PER IOD. SEPTEM2EA PF~
- 3..
!CENEED THERMAL POWER (MUf>
3411.O a.
'eMEPLATE PATING ( GRCSS M'4 1220.6 5.
CESIGN ELECTRICAL RATING (NET MWE):
1148.0 6.
MAXIMUM DEPENDADLE CAPACITY (GROSS MWE):
1183.0 7.
MAXIMUM DEPENDABLE CAPACITY 1(NET MWE):
1148.0.
B.
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 6551.00 46752.00
-.12.
NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54
-13.
REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.001
- 14. HCURS GENERATOR ON-LINE O.00 0.00 21494.42 Iy, UNIT RESERVE SHUTDOWN HGURS 0.00 0.00 0.00
- 16. GPOSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00
- 18. NET-ELECTRICAL ENERGY GENERATED (MWH)
-4294.00
-46188.00 22521335.60
- 19. UNIT SERVICE FACTOR O.00 O. OO 45.98 L20. UNIT AVOILADILITY' FACTOR O.00 0.00 45.98
- 21. UNIT CAPACITY FACTOR (USING MDC-NET) 0.00 0.00 41.96 22.. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 41.96
- 23. UNIT FORCED OUTAGE RATE 100.00 100;O0 48.66' I
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
' 2 5.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
PREPARATIONS ARE NOW UNDERWAY FOR MODE #4 SHAKEDOWN AND SYSTEM i
ALIGNMENT. THE RESTART OF UNIT-2 IS UNDETERMINED AT THIS TIME.
I
)
- NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
1 14-
O I
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[-
~
f SEOUDYAH NUCLEAR FLANT AVEFAGE DAILY. POWER LEVEL LCCiE1 NO.
50-3_:F IJNIT : TWO E,~iTE : OCTOBER 09.,196-COMPLETED BY :
D.
C.
DUFREE
~'
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TELEPHONE :(615)870-6544
.. MONTH: SEPTEMBER.1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWe Net) 01 0
16 0
02-0 17 0
03 0
18 0
04 0
19 0
20 0
05 0
06 0
21 0
~07 0
22 O
~
08
.O 23 0
09 0
24 0
10 0
25 0
11 0
26 0
12 0
27 0
13 0
28 0
4 14 0
29 0
15 0
30 0 L________.__.
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FS 1
t OPERATING STATISTICS (TVA REPORTS)
rVA 7)S2 A (DNP4.au NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant Period Hours 720 Month Se t3t embe r 19 87 item Ne Unit No.
CCit 000 UCi" IW PlGS 1
Aaray Ho A Gross Load. kW 0
0 0
2 Maximum Hour Net Generation. MWh 0
0 0
3 Co a Tner rnm Enm, Gen, Gwo (t}2 0
0 0
4 Steam Gen Thermal Energy Gen, GWD (t)2 0
0 0
5 5
Gross Electrical Gen., MWh 0
0 0
5 6
Station Use, MWh 4,562 4,294 8,856 h
7 Net Electrical Gen., MWh
-4,562
-4,294
-8,856 5
8 Station Use. Percent N/A N/A N/A 9
Accum. Core Avg. Exposure. MWD / Ton!
0 0
0 10 CTEG This Month,10 BTU 0
0 0
6 11 SGTEG This Month,106 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 R
16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 D
17 Generator Avarl. Factor Percent 0.0 0.0 0.0 g
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
?3 y
24 Gross Heat Rate Blu/kWh N/A N/A N/A j
25 Net Heat Rate. Stu/kWh N/A N/A N/A
.E 26 C
27 l
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 32 33 Main Feedwater. M lb/hr N/A N/A N/A y
34 35 36 37 Full Power Capacity, E FPD 404.86 360.65 768.51 38 Accum, Cycle Full Power Days EFPD 0.0 210.8416 210.8416 d
39 Oil Fired for Generation, Gallons 5,280 138,000 5
40 Oil Heatina Value. Btu / Gal.
41 Dient Generation. MWh 80 a?
Max Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
3 43 N/A N/A N/A N/A N/A N/A 3
Remarks: IFor BFNP this value is HWD/STU and for SQNP and WBNP this value is MWD /MTU.
5 2(t) indicates Thermal Ene y.
v,
.f BEE I 4 100I Date Revised Date Submitted l
17 Plant Superintendent
l' rva para ice +sif NUCLEAR PLANT OPERATING STATISTICS -
Seouoyah Nuclear Plant l.
l l
Period Hours 8.760 Month Fiscal Year gg 87 l
~
t rem No Unit No.
Unit One Unit Two P1 ant
]
Average Hourly Gron Load, k W O
U V
2 Maximum Hour Net Generation, MWh 0
0 0
3 Core Thermai Energy Gen, GWD (t)2 0
0 0
4 Steam Gen Thermal Energy Gen., GWD (t)2 0
0 0
5 5
Gross Electrical Gen., MWh 0
0 0
-. ]
6 Station Use, MWh 48.453 63.842 112.295 8
7 Net Electrical Gen., MWh
-48.453
-63.842
-112.295 5
8 Station Use, Percent N/A N/A N/A 9
Accum. Core Avg. Exposure, MWD / Ton!
0 0
0 10 CTEG This Month,106 BTU-0 0
0 11 SGTEG This Month,106 BTU 0
0 0-12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours. Min.
0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 y
16-Turbine Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 g
0 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 19 Reactor Avail. Factor. Percent OO
~01O O O' C
20 Umt 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, Blu/kWh N/A N/A N/A j
25 Net Heat Rate, Btu /kWh N/A
'N/A N/A 5
26 5
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature. *F N/A N/A N/A j
-30 Exhaust Pressure, inHg Abs.
N/A N/A N/A g
31 Intake Water Temp., *F N/A N/A N/A H
32 33 Main Feedwater, M lb/hr N/A N/A N/A y
34 1
[
35 j
36 1
37 Full Power Capacity, EFPD N/A N/A N/A 38 Accum. Cycle Full Power Days, EFPD N/A N/A N/A j
39 Oil Fired for Generation, Gallons 61,116 2
40 Oil Heatina Value. Btu / Gal.
138.000 1
41 Diesa.1 Generation. MWh 926 -l d2 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 l
R emarks: A For BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermal Energy.
Em Date Submitted 914 M Date Revised
-I8
' Plant' Superintendent
e SEQUOYAH ONE REACTOR HISTOGRAM 110 100 -
90 -
80 -
2 70 -
t
.0 _
i 50 -
40 -
30 -
20 -
10 -
0
-10 i
i 0
4 5
12 16 20 24 28 32 AUGUST 1987 O
hMIE e5 SEQUOYAH TWO REACTOR HISTOGRAM 100 90 -
80 -
70 -
60 -
30 -
40 -
5 i
y 30 -
20 -
10 -
0
-10 i
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8 12 16 20 24 28 32 AUGUST 1987 O
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SUMMARY
OF MAINTENANCE ACTIVITIES e
1 I
I a
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l MAINTENANCE
SUMMARY
l (INSTRUMENTATION)
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1N b
N 2 n. <.~a ' wa. nam.t.i.,n ha r au:.6f. wd5 d-rnu.
CDt1P i'
\\
W2';. 3 U FUNE SYS ADDRESS. ' DATE.. DESCRIPTIDil...
. CDRECITUE ACTIDN.,.,......
l l
-;102648 2.LI 077-41105/13/87 2-LI-077-411, CHECK CALIIRATIDN (F.
SI-85.2 REPLACED Cc!!PUTER PDINT 25 i 2-LI-77-411 5 CDf'PUTER IEPUT PER SI RESIsrs, UERIFIED PRDPLR VDLTACE $
h 85.2. THIS INTD IS REGUI2ED TD ACER CALIB DF LEVEL IHDIC')TUR PRD 8 2-86-71 FDR TDIF. L30P INACCURACY '
/- d R 2135 7 ai-YM 273 05/01/27 2-RM 090-27h.3PEWE GEEN LI1E IS HDT DEFECTIVE 9203,02 % TRANSISTORS, F222 I S MB C M MDHITCR DDE: NB1 APPEM 13 RESISTUR AND A IRDKEN WIRE WAS FDUND.
IF.IhDICATIMG THEJRMS!!TDRS ADH RESISTER WAS REPLACED. THE WIRE WAS RFAIRED WR
,g 0202135.
- 1
'.206598 0 il 234 SFARE %/14/37 0-TC-234-SPiA.,SH 48-8 6-6113 REPAIR UNKhDWd. PERfDRMED f.I PER Ift1234.1 MD CDHTEDLV3 iS HEC. FOUC BAD TACCED C000 SPARE.
fgI'
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'f 0-TR-82-:;036/1 IN DIESEL GENERAT!R RODn SWITCH WHICH STDPPED ERRATIC MDLTMENT DN in-A, INK PEN fD IS MDVING ERRATIC PRINT EAD. EPLACED IHK WHEEL,-
r g
PERfDRED PH 0764-082 DN ECDRDER.
] ',.e
- j 1:210088 0 XX 099 SPARE 04/21/87 0-XX-099-SPARE, CARD HAS DAD LDCIC S/W UNKNOWN REMOYED FROM U-2 SSPS CARD i A 0445 404 PEN WR-B212102 REPLACED RICRD LCIRCUITS 21,23 AND DIDDE C14 MICRO.
,)
CIEtDIT 213 PERfDRMED PMT (STEP DF j'
SMI-0-H-1 APPENDIX A) bf N..
3114338 0 TC 234 14107/10/87 0-TC-234-141,CREEWIICHT IS SUT CLDE CAPACIIDR DBTAINED SPARE
! rl J w,
[t CONTRDLLER S/W 100932-05 FDR CKT 141.
ih C
REPAIRED DN B220184 FUNCTIMALY CHECKED 9/
8 CAL. INSTALLED IN CIRC 1 FIT 1418
',I FUNCT. CHECKED REMDUED CDNTRDLLER f/N 13337-100 REPAIRED ON ilfl$ WR 8 PLACED IN SPAiIS CABINET.
3214643 0 TC 234 297 07/06/87 0-TC-234-297-!,CREEN 8 RED LAMPS ItDWH LAMPS ! IIBTAINED ! PARE CONTROLLER BLINKING-S/N 13340-02 fra CKTQ175 KPAIRED l'220195 REMDVED 8 REPAIRED CDFTRDLLER 13339-04, FUNCT ff.CKED, PLACED IN
+
SPARES CABINET. '
i P215607 1 FIS 074 0024 09/21/871-FIS-074-001HCALICWE TLDW I@ICATDR i
1-fIS-74-24 fi/ flus IIR MINUS 2 Z FDR
.8"b SI-128 AND SI-128.3 i
n.
P215610 1 FIS 074 0012 09/23/871-FIS-07WC1H.CdLII. RATE FLDW H
P a
}, 3 [*
INDICATDR 1-fit-74-12 TD PLUS DR MINUS 22 FDR SI-128 AND SI-128.2.
REPLfD MYSOCKET 8 Y
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- 233351 1 LI 077 L10 09/21/871-LI-07T 410,INDICATDR RE ADS LDW MPLITIER BDARD BAD. REPLACED MPLIFIES BDARD AND ZIRD PDT. REtaLIBRATED XMTR AND RETURNED TD SERUICE 575 85887010976 MPLITIER BDARD, 5887011020 PDTENTIDMETER c236Ut 2 TR 068 0024P00108/17/87 2-TR-068-0024P001,fDUHD DUT DF INST.
SI 306 DN-1 ND 10RK PERfDRMED. 000 DNLY TOLERANCE PER SI 306 FDR SI 306 8236936 2 Ik' 068 002kP002 06/17/87 2-TR-068 0024P002,fDUHD DUT OF INST.
SI 306 DN-2 ND 10RK PERfDRMED. DDC.DHLY TDLERANCE PER SI 306 WDRK DONE DN SI 306 P23693? 2 ft 068 0069 08/17/57 2-PR-068-0069,fDUND DUT Dr INST.
SI 306 DN-3 ND WDRK PF.RfDRMED. DDC.
' TDLERANCE PER SI 306 DHLY W3K DONE ON SI 306 r239556 2 FT OM ON 07/16/87 2-fi-030-0242,fI-30-242 IS READIHC D FUNCTIONALLY CHECKED 1.DDP, FDUND Cfn WITH B TRAIM A 0GTS RUNNING FLDW DPC2ATING CURRECTLY VERITIED PRDPER SHDULD BE READING APPRDX 9000 Cfn DPERATIDH OF FLDW WITH DPERATIDMS.
RETURNED l0 SERUICES.
- '239563 2 PDIC 065 0082 W/13/87 2-PDIC-065-0N2-B.DEUIATIDH METER FDUND DUT DF REQUIRED TDLERAHCE CH SI-188.2.
S243953 2 FCV 0 N 0032 OV11/87 2-fCV Ci4-0032,EuMPRDN3,CM IS LORN IN THE UALVE HAD A 50RN CM IN THE PCSITIQ;iER 8 THE DUTPUT IS HDT LINEAR PDSITIDHER. THE CM WAS REPLACED IN THE ___ ____- _ ___________ _ -
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t' Major Capital Projects (cont.):
- Other Work (cont.):
DCN 14A - Fieldwork is complete.
DCN 36A - Fieldwork is complete.
- ECN 7171
. Unit 2 workplans have been approved. SI-298.2 must be run. Fieldwork is complete. Work is being held for SI-26 completion.
lLDAl Lost Hanger Calculations ECN 7270 - Complete.
ECN 7275 - Complete.
ECN 7279 - Complete.
ECN 7282 2 Two are incomplete.
ECN 7283 - One is incomplete--located in high radiation area.
ECN 7284 - Two are incomplete.
ECN 7290 - Four are incomplete.
ECN 7293 - Twenty-six are incomplete.
ECN 7276 - One is incomplete.
j i.
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j o
1 THIS PAGE INTENTIONALLY LEFT BLANK i
e.
Major Capital Projects (cont.):
ECN 5657 - Installation of Moisture Separator Reheater (MSR)
' Drain Valves Work is essentially complete on all the ECNs. Some minor insulation installation, activities are in progress. There may be some small' changes to complete this project in FY 1988, i
PN7123:
ECNs 5938, 6305, 6571 - Replace Feedwater Heaters 1 and 2.
J Units l'and 2 and Eroded Pipe Modifications Group B is supporting PMT on heaters 1 and 2 on both units as requested.
Insulation work on unit I continues.
PN7130: DCR 1156 - Post Accident Monitoring This work has slipped to allow work to continue on priority unit 2 restart efforts. NRC commitment on NUREG 1.97 calls l
_for unit I completion by September 1987 and unit 2 by U2C4.
A request has been sent to the NRC to move the unit 1-completion date to U2C4.
PN7132:
DCR 2324'- Sewage Treatment Facility and Civil Upgrade Preliminary drawings for mechanical and civil changes received.
Electrical preliminary drawings due October 31, 1987. Completion is scheduled for December 22, 1987.
PN7136:
ECN 6259 - MSR Tube Bundle Replacement Complete except for PMT, inservice leak test, and final cleanup.
PN7152:
ECN 6808 - External Conduit Sealing Unit 2 work is complete.
Unit I workplan is available to work.
PN7159: Appendit R ECN 6300 - Additional Sprinklers and Draft Stops All fieldwork and testing are complete. Procedures revisions are in progress. _ _ _ _ - _ - _ _ _ - _ _ _ _ _ - _ _ _ -
e,
-j
- Major Capital Projects (cont. ):
lELBl.
'ECN 6300 - Sensors and Detectors functional test is. complete.
Closure is held for SI-234' update.
PN7161:
ECN 5855 - Replacement of Doors A56 and A57
.lELBl
' Installation of door A56 was completed, security of'A56 to be worked later. Work on door A57 and interlocks will begin later.
PN7181: 'DCR 1898 - ECNs'6832 and 6596'- Dry Active Waste Building lELBl Electrical interface is in progress.
Remaining items are-resolved.
l?l 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 resources are available that will not-impact unit 2 restart effort.
VLH' Modifications 10/6/87 i-
I e
l-1 Major Capital Projects (cont.)
Significant Items:
The following major significant items are under Operation and Maintenance Expence (0&M) and will continue to be until restart of l
unit 2.
1.
Fuse Program Work ECN 5880 - Incomplete work restrained by hold orders and work requests.
ECN 6854 - The workplan is complete.
Valve cycling test by Operations has been rescheduled by hold orders and work requests.
2.
Main Steam Valve Vault (MSVV) Cable and Insulation Work Functional tests are being performed as system valves are available to be tested.
Two valves remain to be tested with an expected completion date of October 22, 1987.
3.
Cable Ampacity Program Unit 2 is complete.
Unit 1 is in progress.
4, Raychem Cable Splicing Wort Six splices remain, but are held pending receipt of new junction boxes for acoustic monitors to accomodate bend 1
radius problems.
NOTE:
Financial Planning is in the process of transferring funds to cover items 3 and 4.
This will be an increase in O&M expense.
Other Items:
ECN 5435 - Fire Doors The installation of weather stripping continues as resources permit.
ECN 5111 - Remove Power From Old Carpenter Shop at Dry Active Waste Building Complete.
i 4 l
I l
Major Capital Projects (cont.):
Other Items (cont.):
ECN 5713 - Various Platforms in Lower Containment The trollies have been received.
Work was completed.
ECN 5100 - Installation of Nitrogen Regulators Complete.
ECN 5726 - CAQR SQP870478 - Reroute Sense Line Piping for Train Separation to Panels 2-L-58 and 2-L-68 Fieldwork is complete.
In-service leak check will be performed during heatup.
ECN 5841 - Hot Shop Fire Detection Workplan 12360 is 95 percent complete.
ECN 5935 - Correct Power Block Lighting Deficiencies Vorkplan 12437 bas been approved and is in work. This is a nonrestart item. Variances need to be approved by DNE. Workplan 12275 is being written.
ECN 6005 - Replacement of AFW Air Ejector The workplan is complete except for the leak check to be done by SI-130.1 in mode 3.
ECN 6057 - Cable Tray Covers This activity is in progress tor the unit 2 restart.
ECN 6082 - Vent for Boric Acid Tank (BAT)
Workplan preparation was completed and placed in the approval cycle.
ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4).
ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed.
l 1 _ - _ - _
'l u
. Mejor Capitial: Projects (cont. ):
,Other Work (cont.):
ECN 6196 - Pressuri::er Hangers and Valves PMT is' incomplete and scheduled for-'startup.
Two-supports identified.
by.DNE EA review were modified. An NRC inspection team' identified
- some deficiencies which require correcting--corrections are in progress.; All identified work required for this work period has been con:pleted.
ECN 6205 - Replacement _of Instrument Loop Power Supply Fuses Unit 2. work is complete.
Unit I work and spares is incomplete.
ECN 6380 - Replacement of Barton Pressure Transmitters Fieldwork is complete. ' Final closure awaiting instruction revision by Instrument Maintenance.
ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment Workplan 12238 is being held for DNE approval of FCR showing
. Installation details. No new date for release of approved FCRs or drawings by DNE has been established.
-ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation j
Inservice tests will be performed when the system is brought up to temperature and~ pressure.
'ECN 6437 - Replace FE-2-256~, and 257 Fieldwork is complete. Some resistors must be replaced for calibration. This will be completed by Instrument Maintenance.
ECW 6455 - Upgrade CU-3 Box Battery Packs Workplan 12295 has been issued. Modifications are complete for 97 of 129 CU-3 boxes. Work is presently on hold until locks are replaced on some of the remaining boxes (WR 220403).
ECNs 6491 and 6534 - Essential Raw Cooling Water (ERCW) Supports All hangers currently identified have been completed. A review is in J
progress'to ensure all unit 2 restart work has been completed for both ECNs.
ECN 6543 - Install Public Safety Access Portals and Modify Entrance Road l
Work is being held pending the release of drawings from DNE.
J q _ - _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _
O Major Capital-Projects (cont.):
20ther Vork (cont.):
ECN 6557
_ Installation of CO2 Abort Switches.
Modifications is awaiting resolution of design problems.
ECN 6601 - Removal of Unit 1 Emergency Gas Treatment System (EGTS)
Backdraft Dampers PMT remains'to be completed by the Engineering Test Section.
Fieldwork is complete.
ECN 6610 - Modify Air Return Fan Supports Unic 1 work is incomplete.
ECN 6631 - Modify Snubbers Documentation review is in progress for unit 2.
ECN 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV)
Fieldwork.is complete (except performance of SI-166).
-ECN 6698 - Repull 120-Volt Cables Unit 2 is complete.
Unit 1 is 90 percent complete and hel'd by ECN 6742.
ECN 6706 14 Support Enhancement Repairs continue on unit I as resources allow.
Initial inspections for unit I lack approximately three supports for completion.
Unit 1 evaluations are continuing. DNE is evaluating contract proposals for unit'l work. Documentation review of unit 2 work is in progross.
ECN 6715 - D/C Random Loads Both trains are complete. A technical specification change has been requested to close this workplan.
ECN 6717 - Stub Bus Fuses The ECN is complete; tape is on order to insulato the busses.
ECN 6739 - Alternate Analysis All identified unit 2 fieldwork is complete.
Unit 2 documentation review is complete. DNE is evaluating contract proposals for unit I work. _-
s Major' Capital' Projects (cont.):
Other Work (cont.):
ECN 6742 - Install Fuses in Radiation Monitor Power Supply Circuits The workplan is complete for unit 2.
Unit 1 is.50 percent complete.
Instrument Maintenance cannot support until early August.
ECN 6761 - East Valve Room (EVR) Blowout Panels Implementation of unit I work is progressing as resources are available. Work on a unit 2 EVR door is complete.
ECN 6784 - Documentation to Show Pipe Class Breaks We are resolving QA comments from QA review for approval cycle.
~ Additional drawings were added during this period and have not been
. received.
ECN 6802 - Modify EGTS Filter Housing Fieldwork is complete. Completion is awaiting PMT by test group.
ECN 6808 - Conduit External Sealing Expect to PORC approve WP 12363 soon. Quality Control has eight questions to be resolved before approval.
ECN 6810 - Rework Category "C" Devices Complete except for functional ~ test.
ECN 6848 - Thermal Expansion Problems With Platforms Fieldwork is complete.
Functional testing is in progress (SI-158).
l ECN 6866 - Modification of Valve Room Doors Final inspections remain incomplete. Workplan is in work.
ECN 6871 - External Conduit Sea?.ing DGB/CB/ERCV Physical work is complete.
Data sheet paperwork is being coordinated for closure by October 31, 1987.
ECN 7000 - Addition of Support to Main Steam Dump Header l
Fleidwork is complete except for final inspections during heatup.
Major' Capital' Projects (cont.):
1 Other Work-(cont.)
{
lLDAl ECN 7078
' Install Hangers - Main Steam Piping Complete except for final inspec'tions during heatup.
I lLDAl ECN 7089 - ERCW Check Valve Replacement Relocation of the check valves has been completed. Hanger work is in progress.
A new design was received and work started.
lLDAl
'ECN 7092 - Capping of Spare Sleeves in Unit 2 Shield Building Unit 2 penetrations are welded but lack final inspections.
lELBl ECN 7110
- Relocate Auxiliary Feedwater Controllers Electrical work is complete. PMT remains.
lLDAl ECN 7A37 - Lost Calculation Hangers 4
All hanger work is complete.
lLDAl ECN 7147 - Lost Calculation Hangers Complete.
lLDAl ECN 7271 - Purge Air Supports A workplan was approved and work started.
lLDAl ECN 7272 - Auxiliary Feedwater Shields The workplan was approved and work started.
ECN 7281 - Grout ERCW hanger The workplan was written, approved, and work started.
ECN 7294 - ERCW Check Valves for Turbine Building Compressors The workplan was written and placed in the approval cycle.
ECN 7297 - Auxiliary Air Compressor ERCW Relief Valves I
Preliminary workplan preparation was started.
WR B226336 - Modify the maintenance portion of the Sandblast Shop.
l L_ _ __ _ _. __
l
)
e 1
Major Capital projects (cont. ):
Other Work (cont.):
DCN X00006A - Remove Hydrogen Analyzers Tubing The workplan was completed except PMTs (SI-219).
DCN 2000188 - Install Needle Valve for Hydrogen Analyzers The workplan was completed except PMTs (SI-219).
lLDAl DCN 49 - Computer Room Air Conditioner The workplan was written, approved, and work started.
DCN 58 - Penetration X94 and X95 Stiffeners The workplan was written, approved, and work started.
Procedure Revisions Many manhours were spent revising procedures (MLAIs).
lELBl Control Room Bullet Resistivity - DCR 2268 - ECN 6860 Workplans 12602, 12604, and 12605 are in work. Workplan 12603 is ready for approval cycle. Approval is needed from DNE for FCR 6053.
Startup Activities List (SAL)
SAL Closure - Many manhours were spent closing these items.
lELBl Appendix A - Internal Conduit Sealing Fieldwork is complete on WP 12272.
lELBl Instrumentation Verification Program There have been 953 discrepancies issued to MODS to date with 476 not required for restart. All discrepancies required for restart have been completed, 334 nonrestart discrepancies are open.
DCN 4B - Fieldwork is complete.
DCN 7A - Fieldwork is complete.
l DCN 9A - Fieldwork is complete.
I l
ECN 7297 - Auxiliary Air Comprensor - ERCW Relief Valves Preliminary workplan preparation was started. _ _ _ _ _ _ _ - _ _ _ _ _ -
1
.s
~-
. Major Capital Projects-(cont.):
'Other Items (cont.):
ECN 5111 - Provide' Permanent Power to Manholes 42-46 Electrical conduit and wiring installation for manholes 44-46 is complete according to WP 12262.
Manholes 42 and 43 are.being held for information from DNE on power cable-routing and terminations..FCR 4572R1 was sent to DNE and was logged in, but it was not sent to the-responsible' engineer. _ Manholes 42-46 will be worked by this FCR 4572RI. This item is not considered unit 2 startup by DNE and they will not authorize the engineer to do the necessary work to obtain pull cards _or drawings for manholes 42-46.
ECN 5503 - Fire Detection System O&PS Building Workplan 12482 is ave.ilable to work.
ECN 5599 i Conduit Supports for Fifth Vital Battery and Waste Disposal Area Workplan 12186 is being held for fifth vital battery area conduit supports..Information is needed from DNE on support variances.
Initial installation of the 60th cell to the battery is to be added to this workplan. The workplan for the waste disposal area is being held for issue of the ECN by DNE to include FCR 4753.
l ECN 5609 - Air Compressors Makeup Water Treatment Plant j
Installation and chectout is complete. Modifications is awaiting approval'from DNE to install water drain valve on rec'eiver tank. The' i
specified valve called for by DNE is not obtainable. Modifications 1
received. approval to install water drain valve located by field.
J Additiored isolation valves need to be added on the water drain valve
)
for insLnilation and an additional valve should be added on the downstreta side of air receiving tant for isolation of the air receiving tank which Design originally omitted.
ECN 5609 - Evacuation Alarm Workplan 12387 is in work and is 90 percent complete.
)
ECN 5626 - Containment Ladders, Unit 1 A workplan is being written to incorporate this ECN. Modifications needs additional Design information to complete.
DNE needs to issue all drawings listed on this ECN. Work has not begun because of this holdup.
1 U
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CDFiP 4.3...,11 f tM SYS ADDRESS. DATE.
DESCRIPilCH.
CDRRECTZUE ACTIDH.
VALVE PDSITIDHER. UERIFICATIDM DF THE CALIBRATIDH WAS DONE DH THE YALUE AND PUSITIONER ft!HCTIDHALLY TESTED FR05 2-HIC-074-0032A AND LEFT IN SERVICE.
- 97779 2 TI 070 005107/10/07 2-FI-0f0-0031,EvHFRDv],f LCW IHDICAICR THE I@ICATCR WAS DEFECTIVE. THE i
EEf DS A?P7DX. 25 DEC2El HIGH DURIHG LCCP INDICATCR WAS REPL ACED AMD CALII"Af fD TD CHECK PEEfDRMED FCR RP 12 M DESIRED TOLERANCE fDR PEEifST
- .) records listed.
1 I
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1 l
1 l
i I
i MAINTENANCE
SUMMARY
(MECHANICAL)
Jo**=
MECHANICAL MAINTENANCE MONTHLY ' REPORT FOR SEPTEMBER 1987
-q COMMON
~ 1.
Completed work on soll compaction issue.
L2. -Completed repairs on security building roof.
3.
Continued repair of traveling water screens.
4.
Completed sealing o'f' mechanical penetrations UNIT 2 11.
Completed repairs on CCS_ heat exchanger B.
2' Completed stroke test on System 65 (EGTS) valves.
3.
Completed coil. replacement on 2BB pipe' chase coolers.
4.
Completed tubing replacement on-2AA component cooling pump.
5.
Completed repairs on various ERCW valves during A-and B-train outages.
6.
Completed System 43 sampling and water quality hanger repair.
7.
Completed repairs on ERCW pump N-B.
8.
Started replacement'of ERCW piping due_to MIC damage.
-9.
Completed replacement of cavitating venturi on MDAFWP 2A.
- 10. Completed rebuilding of spare fire pump.
- 11. LCompleted replacement of stuffing box on ERCW pump Q-A.
12.
Completed. installation of.high point vents on ERCW system.
13.
Completed repairs on valves 74-3 and 74-21.
- 14.
Completed repairs on EGTS filter housing.
15.
Completed repairs-on' valve 72-40.
- 16. Completed repairs on valves 3-163 and 3-174.
OTHER
- 1.
Completed revision of Maintenance Instruction (MI) 6.22, " Control Of Heavy' Loads In Critical Lifting Zones - NUREG 0612."
2 Completed ' revision of SI-111. " Testing And Setting Of Main Steam Safety
-Valves."
3.
Completed workplans for installing ERCW high point vents.
4.
Completed workplan for repair of door C-14.
5.
Continued efforts to repair post local leak rate testing valve failures.
6.
Continued SI/MI review and revision to support startup.
7.
Continued efforts to reduce WR backlog.
8.
Continued equipment condition evaluation support.
9.
Completed workplan to repair CCS heat exchangers.
10.
Continued efforts to rebuild MDAFWP 2A.
11.
Continued revision of MI 6.21.
- 12. Completed revision of SI-181.3.
13.
Completed workplan to replace pipe chase cooler coils.
14.
Completed workplan for metrix valve replacement.
15.
Completed workplan for lower compartment cooler coil replacement.
16.
Continued closure of various CARS, DRs, Notification Of Indications, l
CAQRs, etc. w ____-__-_-
e o
SUMMARY
OF YORK COMPLETED MODIFICATIONS - CURRENT STATUS SEPTEMBER 1987 I
1
- ; is' Major Capital Projects
PN7101: ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan (WP) 12223 is in progress pending safe access to current transformers.
PN7102:
ECN 5938 - Replace Feedwater Heaters 3 and 4 Preparation work is underway as time and manpower permits.
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 I 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 The workplan for the replacement of unit 1 isolation valves is not scheduled to begin until later in the year. Some insulation activities remain incomplete and are being worked as resources permit.
PN7106:
ECNs 5034 and 5743 - Various Platforms in Lower Containment Additional safety gates are to be installed on unit 2.
Upgrading of bolting material by the Warehouse Material Group was completed and gates installed.
PN7108: ECN 6720 - Crane Consistency Program Unit 2 polar crane modification is complete.-
Postmodification testing (PMT) by Electrical Maintenance is not complete.
Unit 1 polar crane work started on July 6, 1987 and is approximately 90 percent complete. Auxiliary Building crane WP 12596 is in the approval cycle. Drawings have not been issued on the remaining cranes.
PN7115:
ECN 6719 - Volumetric Intrusion Detection System ECN 6719 is still on hold. Security is dissatisfied with system operation.
Security and Engineering Design have not concluded discussions on resolution. Design is working on j
making the system functional.
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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P,
O.
Box 2000 Soddy-Daisy, Tennessee 37374 QCT14%51 s c '
Nuclear Re6ulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - SEPTEMBER 1987 Enclosed is the September 1987 Monthly Operating Report to NRC for Sequoyah Nuclear Plant, Very truly yours, TENNESSEE VALLEY AUTHORITY L'. M. Nobles Plant Manager 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 Regulatory Commission Washington, DC 20555 (10 copies)
/
1 Mr. T. Marston g
Electric Power Research Institute i
P. O.
Box 10412 Palo Alto, California 94304 (1 copy)
DESIGN AT 'D ORIGI,/g/
f
/
INPO Records Center Suite 1500 Certified E' 1100 circle 75 Parkway Atlanta, Georgia 30339 (1 copy)
Mr. K. M.
Jenison, Resident NRC Inspector l
O&PS-2, Sequoyah Nuclear Plant i\\
- . e two om...
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