ML20205P560
| ML20205P560 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/30/1988 |
| From: | Shawn Smith TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8811080217 | |
| Download: ML20205P560 (51) | |
Text
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6 TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP (FORMERLY OFFICE OF NUCLEAR POWER)
SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT l
TO THE I
NUCLEAR REGULAT0kY COMMISSION SRPTRMBER 1988 l
UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77
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UNIT 2 i
M DOCKET NUMBER 50-328 g
LICENSE NUMBER DPR-79 V
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N Submitted by:
pi S. J. Smit /f, Plant Manager pr
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ADOCK 0%y7 DR
L!p TABLE OF CONTENTS Page I.
Operational Sunnary Performance Summary 1
Significant Operational Events 1-4 Fuel Performance and Spent Fuel Storage l
Capabilities 5
Miscellaneous 5
PORVs and Safety Valves Summary 5
i l
Special Reports 6
l Licensee Events 6-11 Systems of sequoyah Nuclear Plant 12 Radweste. Summary 13 Offsite Dose Calculation Minual Changes 13 II.
Operating Statistics A.
NRC Reports i
Unit One Statistics 14-16 Unit Two Statistics 17-19 B.
TVA Reports Nuclear Plant Operating Statistics 20-21 Unit Outage and Availability 22-23 Reactor Histogram 24-26 III. Maintenance Summary Electrical Maintenance 27 Instrument Maintenance 28 Mechanical Maintenance 29-32 Modifications 33-39 0288(/dir
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i GPERATIONAL SUPDtARY I
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PEfFORMANCE SUSDtARY
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September 1988 3
The following summary describes the significant operational activities for the month nf September.
In support of this summary, a chronological log of eignificant events is included in this report.
UNIT 1 Unit remained in an administrative shutdown the entire month because of design control review, configuration control updating, and resolution of
-g significant employee concerre. Outage-related maintenance and modifications continue for restart. Unit i has been off line 1,135 days.
Extensive testing and various system alignments as well as other restart activities are being performed fer restart.
At 1545E, September 27, 198S, unit one entered mode 4, the beginning of system heatup to power operation. This is a significant milestone since being shutdown on Augt t 22, 1985, three years ago.
UNIT 2 Unit 2 continues to operate very well since restart.
It was online the entire month with a capacity factir of 72.35 percent.
Since restart, unit 2 has r
genera:ed over 2.6 MWhs (2.628,600 MWh) of electrical power and has been in continuous operation f or over one hundred (100) days.
Unit 2 was reduced in power for core life extenaion.
There are 55.3 effective full power days remaining in the cere.
l SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 09/01/88 0001E Maintenance continues for power operation. Mode 5. RCS
@ 1300F, 30; psi.
09/17/88 1330E Depressurize RCs to 50 psi in preparation of venting and sweeping.
09/17/88 2336E
- @ 50 si.
L_
09/19/8s 0700E sgan R ing and venting at various pressure 3.
1335E ed.
RC @ 50 oci.
34 201CE s 325 psi, ii 1
E,
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 09/24/88 1127E Began RCS heatup to 1800F.
2226E Began pulling vacuum.
09/25/88 0530E Vacuum established.
0728E RCS @ 1800F.
1502E Received reactor trip due to maintenance being performed on Loop #2 which cause a lo-lo S/G 1evel.
09/27/88 1226E Began heatup to 1950F.
1511E Authorization for mode 4 is given.
1545E Unit entered mode 4.
1725E RCS @ 2080F, 340 psi.
2135E Continue heatup.
2347E RCS @ 2200F, 360 psi.
09/28/88 0132E Excessite RCS leakage via the RHR System.
0817E Began system cooldown for leakage repair.
1230E RCS @ 2050F.
I 1707E Repairs complete on RCS leakage.
Resume heatup.
09/30/88 2400E Mode 4, RCS @ 2480F, 370 psi. Activities continue
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for power operation.
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t Unit 2 Date Time Event 09/01/88 0001E Reactor @ 98 percent. 1108 MWe. High steam flow alarm initiates at power greater than 98 percent.
t 09/03/88 0926E Besan load decrease for core life extension. (C.L.E.)
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1209E Holding for operator trainit.g. Reactor @ 70 percent, 1026 MWe.
1226E Resume load reduction, C.L.E.
2315E
.Holdiag for operator training. Reactor @ 80 percent.
940 MWe.
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SIGNIFICANT OPERATIONAL EVENTS Unit 2 Event date Time 09/04/88 1820E Resume load reduction. C.L.E.
2300E React 6r @ 70 percent. 830 MWe.
09/0S/88 1627E Borated RCS to maintain T-avera8e.
1852E Reduction completed.
Reector @ 70 percent. 790 MWe.
Holding for C.L.E.
4 2154E Borated RCS to maintain T-average due to xenon oscillation.
2345E P.eactor 0 70 percent power 770 MWe.
09/13/88 1300E Began power increase to full load due to system load demand.
1538E Reactor @ 76 percent.
1812E Holding @ 88 percent. 983 MWe, foe power range adjustment (SI-78).
1845E Resume power increase.
2200E Reactor @ 97 percent. 1006 MWe.
09/14/88 0032E Reactor @ 98 percent, 1106 MWe.
0500E Reactor @ 98 percent. 1115 MWe.
09/19/88 0758E Dilute RCS to maintain T-average.
4 1740E Started load decrease to 55 percent for C.L.E.
2200E Reactor 88 percent. 1018 MWe. Holding for operator trafning.
SIGNIFICANT OPERATIONAL EVENTS Unit 2 Event Date Time 09/20/88 0019E Resume reduction.
0325E Rtactor G 70 percent, 844 MWe.
0856E Resume power reduction to 55 percent, C.L.E.
1300E Reactor @ 64 percent, 736 MWe, Holding for operator training.
1615E Resume power reduction to 55 percent.
1806E Unit stablized at 57 percent, 650 MWe, 09/21/88 0900E Reactor G 57 percent.
09/24/88 12?iE Began power increase to 60 percent to increase taxiliary steam header pressure.
1450E Reactor @ 60 percent, 650 MWe.
19%5E Began power increase to 65 percent to increase auxiliary steam header pressure.
2259E Reactor @ 65 percent, 720 MWe.
09/30/88 2400E Reactor @ 65 percent, 72n MWe.
4 FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during September 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 September was 877.39 MWD /MTU with the total accumulated core average fuel exposure of 11841.05 MWD /MTU.
i SPENT FUEL PIT STORACE CAPABILITIES The total storage capability in the SFP is 1.386.
However, there are five cell. locations which sre incapable of storing spent fuel (SFP).
Four locations (A10, All A24 and A25) are unavailable due to a suction strainer t
conflict, and one location (A16) is unavailable due to an instrumentation
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conflict.
Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,03?.
MISCELLANEOUd Spent Fuel Pool Inventory The annual physical inventory via cassette tape / underwater camera system of all spent fuel (348 fuel assemblies) was performed by Reactor Engineering Section personnel on September 14, 1988. No discrepancies were noted.
An audit was conducted on September 22-23, 1988, by Division of Nuclear Quality Assurance to verify that an adequate program has been established, is implemented, and is effective for Special Nuclear Material (SNM) at the plant that meets the applicable requirements of 10 CFR 50 Appendix 5 and 10 CFR 70.
No significant diserspancies were observed.
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P0bVs AND SAFETY VALVES SU M Pj' i
No PORVs or safety valves were challenged in September.
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4 SPECIAL REPORTS The following special report revision was submitted to the NRC for the month cf September.
1-88-13 On August 9, 1988, with unit 1 in mode 5. fire door A-68 (IB-B RHR and CS heat exchanger room on elevation 690 of the Auxiliary Building) exceeded the seven-day limit allowed by TS LCO 3.7.12.
The door w s breached on August 1, 1988 and was not closed until 0200E on o
August 9, 1988. The door was opened for ventilation during surveillance testing activities in the room because of undesirable fumes from painting in the room.
While the door was breached, work activities were also initiated for wet layup of the 1B heat exchanger which required a temporary water hose to be routed through the opened door. The surveillance testing work activities under SI-260.2.1, "BIT Cold Leg Injection Flow Balance, Pump Performance and Check Valve Test " were completed on August 1, 1988, but the heat exchanger wet layup work continued past the seven-day interval.
The door was returned to normal August 9, 1988.
LICENSEE EVENT REPORT (S)
The following 'icensee event reports (LERs) were transmitted to the Nuclea-Regulatory Commission in September 1988.
Description of Event LER 1-88031 On September 8, 1988 with unit 1 in mode 5 and enit 2 at 70 percent power, the hourly fire watch through the 669 elevation of the Auxiliary Buitding was suspended from 0522E to 0815E because of en unexpected increase in the airborne radioactivity in that area.
The patrol was required for LCO 3.7.12.a because of a treached fire barrier.
The breaching permit had been issued on September 6, 1988 to repair flush bolts on fire door A-26.
The immediate cause of this event was the increased level of airborne radioactivity in the Auxiliary Building.
This condition presented an overriding personn".1 safety concern and access to the area was restricted.
This event was caused by a venting of the unit i volume control tank followed by opening cf the waste gas system for rsintenance on the strainers to the waste gas compressor.
Recently installed Beta Max whole body friskers provided an early warning of an increased airborne activity level due ta their ine eased sensitivity.
The increase in airborne was noted when six Nuclear Security Of ficers set of f Beta Max alarms '< hen exiting the Auxiliary Building. Workers were allowed to retur. in the Auxiliary Building at OS15E whsn all air samples indicated levels less t:
'he minimum detect;
.c levels.
Fire Door A-26 was returned to ser on September 8 at 1330E.
No further action is required.
6-
LER 4
1-88032 At 1338E on September 3, 1988, with init 1 in mode 5 and unit 2 at 90 percent power, an ABI occurred.
Before this event, at 0804E, IM personnel were performing SI-83, "Channel Cala..ation For Radiation Monitoring System " for the "C" channel of the Auxiliary Building vent RM 0-RM-90-101.
This SI required handswitch 0-HS-90-136A3 to be placed in the position to prevent the output of the "C" channel from causing an ABI during calibration.
At 1154E, Chemistry personnel i
placed the auxiliary sampling equipment in service to satisfy TS for an inoperable RM.
After the calibratiois of the RM, $1-83 required that the charcoal filters be reinstalled.
TI.16. "Sampling Methods,"
which is used to accomplish installation of the charcoal filter, instructed Operations personnel that changing the filter eculd result
!n an ABI, and recommended hat the "B" channel of 0-RM-90-101 be blocked while changing filters. As a result, the "C" channel was unblocked to allow the "B" channel to be blocked.
The next.1ection of SI-83 was for verification of the radiation indicator and the radiation recorder by step increasing the trip reference voltage of the radiation monitor.
At 1338E, durinC the verification, the trip setpoint of the RM was exceeded, and with handswitch 0-HS-90-136A3 set to block the "B" channel, the actuation of the "C" channel was permitted to cause an ABI. The root cause of this event was that the steps necesse.ry to be completed co continue performance of SI-83 after installing the charcoal filters did not take into account the actions required by TI-16.
To prevent recurrence of this event, SI-83 will be revised to include a step to remove the control fuses when performing calibrations of 0-RM-90-101 which is referenced in TI-16.
1-88007 This revisfori provides (1) additional information regarding the Rev. 2 corrective aeticn TVA is taking to ensure that the ABGTS can perform i
its design function during various modes of two unit operation and i
(2) include a discassion of a recent event in which compensatory measures necessary for placing the unit 1 containment purge system in operation may not have been adequately documented or communicated to l
the appropriate personnel.
2-88034 On August '.5, 1988, with unit 1 in mode 5 and unit 2 at 98 percent power, four separate incidents affecting plant operations occurred as a result of an area thunderstorm (1) a loss of power and monitoring functions at the Meteorological (MET) Tower, common to both unital (2) a momentary trip of the unit 2 CCW pumps 2A and 2B resulting in a
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perturbation in the condanser vacuum; (3) an inadvertent trip of the intertie bank ber. ween the 161kV and 500kV switchyards; and (4) a loss of power f rom the common station service transformer (CSST)-A to the start buses IA, 2A, and the 6.9kV shutdown board (SDBD) 18-B, which resulted in an automatic start of all four D/Cs.
The 1 css of power to the 6.9kV SDBD and the result of the D/Ge i
starting is reportable under 10 CRF 50.73, paragraph a.2.iv.
The other three events are included for informational purposes.
Items 1 t
and 2 are attributed to separate local lightning strikes that caused i
a trip of the subject equipment.
The CCW pumps trip caused a condenser vacuum perturbation but the Operations personnel were able to restart the pumps and stablize the unit without tripping the turbine.
7 m
__LER 2-88034 The cause of the intertie bank trip sas the result of a fault (cont.) condition on an offsite 161kV power line and a suspected erroneous relay operation.
The CSST
'A' trip was caused by a phase-to-ground fault in the start bus 2A normal feeder breaker compartment resulting from an apparent moisture and dust collection in the compartment allowing a low impedance current path from the C-phase bus bar to the cabinet wall. The MET tower computer link to the plant was restored on the sa.ae day.
The CCW pumps were immediately restarted without incident.
The 161kV/500iv intertie bank was restored on August 16, 1988, and the associated protective relays will be tested to ensure future proper operation. The start buses 1A, 24 and 6.9kV SDBD have been reenergized via the spare CSST-B.
Repair of the damaged start bus 2A breaker compartment will be completed prior to placing this compartment into operation.
4 2-88035 On August 31, 1988 at 0920E, with unit 2 at 98 percent power, an "A" train CVI resulted from the performance of SI-82.2, "Functional Test for Radiation Monitoring System." The immediate cause was found to be that a current path was inadvertently created across 2-RM-90-106 high particulate radiation relay contacts during the performance.
The root cause of this event is attributed to an error made by IM personnel when steps in the SI were performed out of sequence.
For l
immediate corrective action. Operations personnel verified that there was no high radiation and reset the CVI in accordance with S01-30.2B, l
j "Containment Ventiletion System Isolation." Plant Management has met with IM personnel to discuss this event and other recent events in which they were directly involved. This meeting discussed lessons learned and r9 emphasized the need for adherence to procedures to ensure that the potential for future events is reduced.
2-88036 At 1630E on August 30, 1988, with unit 2 at 98 percent power, it was determined that TS 3.0.3 should have been entered at 1010E on the same day.
The actions of TS 3.0 3 were required because the action statements (6a) and (16) of TS LCO 3.3.1 and 3.3.2 respectively were not being complied with during the performance of SI-90.72, "Reactor Trip Instrumentation Functional Test of AT/Tavg Channel IV. Rack 13 (T-63-67)." These actions require the loop bistables to be placed in the tripped condition within six hours and one hour respectively, of when the channel is declared inoperable.
Contrary to this requirement, the bistables for the unit 2 RCS loop 4 AT/Tavg, channel IV were not in the tripped condition for a portion of the tire the instrument loop was out of service.
The root cause of this at was the incomplete implementation of AI-47, "Conduct of e
Testing," section 7.11.2, "Unplanned Test Stoppage, Exiting, Reentering," by the SI-90.72 test director.
SI-90.72 was not revised as required by AI-47 when the test was stopped and the bistables were reset. To prevent recurrence of an event of this type, training will
.be provided to appropriate maintenance personnel on an unplanned 1
stoppage of a test as outlined in AI-47.
Training will also be provided to tiese individuals on the potential affects of instrument testing on TS requirements. Training will also be provided to licensed Operations personnel on the understanding of the condition of a protection grade instrument loop during testing.
8-i
LER 2-88006 This revision provides updated _ details concerning corrective action Rev. 1 completion dates.
2-88030 This revision provides additional information regarding the Rev. I corrective action TVA is considering to prevent excessive post-trip RCS cooldowns.
These cooldowns could have caused noncompliance with shutdown margin requirements.
2-88036 This revision clarifies the corrective action TVA will be taking to Rev. 1 prevent recurrence of the event.
Correction: LER 1-88032 reported in the August 1988 monthly report is incorrect. The correct LER number is 2-88032.
9
ABBREVIATIONS Page 1 of 2 t
1.
ABGTS Auxiliary Building Gas Treatment System 2.
ABSCE Auxiliary Building Secondary Containment Enclosure 3.
ABI Auxiliary Building Isolation 4
A01 Abnormal Operating Instruction 6.
ASOS Assistant Shift Operation Supervisor 7.
AUO Assistant Unit Operator 8.
BAT Boric Acid 3torage Tank 9.
BIT Boron Injection Tank
- 10. CAQR Condition Adverse To Quality Report
- 11. CCP Centrifugal Charging Pump
- 12. CCW Component Cooling Water
- 13. CRI Control Room Isolation 14.
CREVS Control Room Emergency Ventilation System
Containment Spray System 16.
CVI Containment Ventilation Isolntion i
- 17. D/C(s)
Diesel Generator (s) 18.
DCN Design Change Notice 19.
DCR Design Change Request 20.
ECCS Emergency Core Cooling System 21.
ECN Engineering Change Notice 22.
ECTS Emergency Gas Treatment System 23.
EMI Electromagnetic Interference 24.
EQ Environmentally Qualified / Environmental Qualification l
25.
ERCW Essential Raw Cooling Water 26.
ESF(A)
Engineered Safety Feature (Actuation) 27.
FCV Flow Control Valve 28.
FSAR Final Safety Analysis Report 29.
FWI Tecdwater Isolation
- 30. GOI General Operating Instruction
- 31. CPM Gallons Per Minute
$2.
H0 Hold Order 33.
IM Instrument Mechanic 34.
IMI Instrument Maintenance Instruction 35.
LCV Level Control Valve 36.
LCO Limiting Condition for Operation 37.
LOCA Loss of Coolant Accident
- 38. MAST Maximum Allowable Stroke Time 39.
MFI Main Feedwater Isolation 40.
MOV Motor Operated Valve 42.
MS!
Main Steam Isolation I
43.
MSIV Main Steam Isolation Valve 44 MCR Main Control Room 45.
NE Nuclear Engineering (formerly Division of Nuclear Engineering) 46.
NSS.
Nuclear Security Service 47.
NSSS Nuclear Steam Supply Syste 48.
PORC Plant Operation Review Committee 49.
PRO Potential Reportable Uccurrence i
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P ABBREVIATIONS E
Page 2 of 2 49.
RCS/(P)
Reactur Coolant System /(Reactor. Coolant Pump) 50.
RHR Residual Heat Removal Radiation Monitor (RAD Monitor / RAD MON) 51.
Rn 52.
RWST Refueling Water Storage Tank
- 53. SCR Significant Condition Report t
$4 SFP Spent Fuel Pit 55.
S/G(s)
Steam Cenerator(s) 56.
SI Surveillance Instruction /or Safety Injection 57.
SMI Special Maintenance Instruction l
58.
S01 System Operating Instruction 59.
SQN Sequoyah Nuclear Plant 60.
SR Surveillance Requirement 61.
SSPS Solid State Protection System 62.
TACF Teepnrary Alteration Control Form 63.
TI Technical Instruction 64.
TS(s)
Technical Specification (s) 65.
UHI Upper Head Injection 66.
U9/(S)R0 - Unit Operator /(Senior) Reactor Operator 67.
VLV Valve 68.
WP
- Workplan g
69.
WR Work Request i
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VARIOUS SYSTEMS OF SEQUOYAH NUCLEAR PLANT l
SYSTEM CODE SYSTEM TITLE 1
Main Steam System (Turbine) (MSR) 2 Condensate System (FW Heaters) 3 Main and Auxiliary Feedwater System 5
Extraction Steam System 6
Heater Drains and Vents System 14 condensate Demineralizer i
15 Steam Generator Blowdown System 24 Raw Cooling Water System 27 Condenser Circulating Water System 35 Generator Cooling Systems 36 Feedwater/ Secondary Treatment System 17 Gland Seal Wates System 42 Main / Auxiliary Feedwater Control System 47 Turbogenerator Control System 54 Injection Water System i
58 Generator Bus cooling System 61 Ice Condenser Syttem 62 Chemical and Volume Control System 63 Safety injection System 64 Ice Condenser Containment Sy' tem 65 Emergency Cas Treatment Systew 67 Essential Raw Cooling Water System 58 Reactor Coolant System (Steam Geneiator) 70 Component Cooling System 74 Residual Heat Removal System 82 Standby Diesel Generator System 87 Upper Head Inject!on System 90 Radiation Monitoring System t
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RADWASTE
SUMMARY
September 1988 1.
Total volume of solid waste shipped offsite:
A.
Dry active waste:
2052 ft.3 Activity:
14.0386 curies B.
Spent ec41ns, sludges, bottoms:
158.5 Activity:
14.0386 curies Shipped:
September 2, 1988 Barnwell, Inc.
September 28, 1988 Barnwell, Inc.
2.
Radwaste onsite and awaiting snipment:
A.
Resin in storage 109 ft.3 B.
Estimate resin that will be generated: 0 ft.3 C.
Dry active waste awaiting shipment:
1101 ft.3 0FFSITE DOSE CALCULATION MANUAL CHANCES No changes were made to the SQN Of fsite Dose Calculation Manual (ODCM) in September 1983.
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OPERATING STATISTICS (NRC REPORTS) 1 l
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NG!Or4 ELECT 9 tCAL PATING (tET NE):
1143.0 6.
e'AXIMUM DEPENDA11LE CAPACITY aGitCSS MWE):
1103.0
'. *' X I MUM C.': Feil 0 AllL E C AP AC I TY (NET MWE):
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mlT FORCED OUTAGE RATE 100,00 100.00 56.47 i
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- UTDOWNS SCHEDULED OVER NO.T : MONTHS (TYPE, DATE, AND DURATION OT-EACH):
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F iHUTDOWN AT END OF REPOHT PERIOD. ESTIt14 RED DATE OF STARTUP.
' E RESTAR T OF UNIT-1 15 3CHEl:ULED FOR CCTOLER !??G.
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET No. : 50-327 UNIT : ONE DATE : OCTOBER 05,1988 COMPLETED BY : D.C.DUPRIlE TELEPHONE : (615)870-6722 MONTH: SEPTEMBER 1988 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Nat)
DAY (MWe Net) 01
-6 16
-6 02
-8 17
-5 03
-4 18
-5 04
-6 19
-4 05
-6 20
-5 06
-7 21
~5 67
-9 22
-6 08
-6 23
-5 09
-8 24
-5 10
-6 25
-6 11
-6 26
-18 12
-11 27
-7 13
-7 28
-9 14
-6 29
-9 15
-5 30
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UtitT Sl!UTDOWNS AND p0WER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah one DATE october 7, 1988 COMPLETED BY D. C. Dupree REPORT tlONTil september 1988 TELEPHONE (615) 870-6722 U
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gg oyy Licensee g-3, og Cause & Corrective c*,
gg ggg Event gg gg Action'to 13 0.
Date e
o y
3o g
gge Report i go gu Prevent Recurrence a:
eec v
- . m g o
n 1
880101 F
720 F
4 Design Control, Configuration Updating, and Employee Concerns.
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Forced 2
3 Reason:
11ethod:
4 Exhibit C-Instructions S: Scheduled A-E<guipment Failure (Explain) 1-!!anual for Preparation of Data l
B-!!aintenance or Test 2-!!anual Scram.
Entry Sheets for Licensee i
C-Refueling 3-Artomatic Scram.
Event Report (LER) File l
D-Regulatory Restriction 4-C at. of Existing (NUREG-0161)
A E-Operator Trainisin F. License Examinataan Outage f
F-A.iministrative 5-Reductiort 5 Exhibit I-Same Source i
C-Operational Error (Explain) 9-Other i
li-Other (Explain)
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l OPERATIN1 DATA REPORT l
DOCnGT NO.00-728 DATE i:CTOUDit 7, 1968 COMPLETED DY D.C.DUPRH-l TELEPHONE (610)G70-67PP
'7ERATING STATU:1
' NIT NAME: SEQUOYAH NUCLEAR.FLANT, UNIT 2
NOTES:
1.
2.
'G: PORT PERIOD: 3EPTEMBER 19GG 3.
- ! CENSED THERMAL POWER (MWT):
'3411.0 4
mt1EPLATE RATING"(OROSS NWE):
1220.6
- +
3.
DESIGN ELECTRICAL RATING (NET MWE):
1140.0 6.
MAXIMUM DEPENDAULE CAPACITY (CROSS NWE):
1103.0 1
70 iMXIMUM DEPENDABLE CAPACITY (NET MWES:
1140.0 J.
M CHANCES OCCUR IN CAPACITY RATINGS (ITEMS NUMDERS
", THROUCH 7)S!NCE LAST REPORT. O!VE REASONS' f
.- =
7 WWER LEV 5iL TO WHICH RESTRIC TED, IF ANY(NET (1WE):
LO.
eA.~ONS FOR PESTPTCTICNS,IF
,.NY-THIS MONTH YR.-TO-DATE
(:UMULATIVE 11.
R URS Ill 3dPORTING PERIOD 720.00 6373.00 55536.00
- 12. "t1UER OF 0URS REACTOR NAS CRITICAL 720.00 2993.10 24977.64-
- 13. 'EACTOR REtCRVE SHUTDOWN HC09G O.00 0.00 0.00 14
' CURS GENU 3ATO,1 ON-LINE 720.00 2000.75 24382.97 1.,.
M1T RESERvi? dHUTCOWN HOURC O.00 0.00 0.00 th.
U:OUS THE'IMAL ENERGY GENERATCO (MWn 1870207.44 7979613.00 T/107590. 30 17.
UCSS ELEC7RICAL ENERGY GEN.
<MWH-616260.00 2623600.00 24145330.00 ta.
- T ELECTRICAL ENERGY GENERATED (MVH) 508166.00 2440013.00 2494Bloo.00 l o.
> NIT SERVICE F%CTOR 100.00 43.94 43.90
- 00. UNIT AVAILADILITY FACTOR 100.00 43.94 43.90 21.
NIT CAPACITY FACTOR (USING MDf., NET) 71.16 3.
03 39.13
'2 2.
- NIT CAPACITY FACTOR (USING DER NET) 71.16 32.33 39.13
- 23. NIT FORCCD OUTAGE R ATE 0.00 56.06 51.05
- 74. fHJTDOWNS SCHEDULED OVER NENT o MONTHS (TYPE, DATE, AND DURATION Oi EACH):
CLE FOUR REFUELING OUTA",F IS ECHEDULED FOR JANUARY 1909, WITH A
- "RATION OF $5 CAYS.
SHUTCOWN AT END OF REFOAT PE.4100. ESTIl1ATED DATE OF STARTUP:
25.
t 7 e
- 0 T :
4 HAT THE THE <R.-FO-DaTE z.N ':
n ei '..r1VE VALUES hat'E DEEN Ur'DA TEC.
i i
9 SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET No. : 50-328 UNIT : TWO DATE : OCTOBER 05, 1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 MONTH: SEPTEMBER 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY PohER LEV"L DAY (MWo Not)
DAY (MWa Not) 01 1068 16 1075 02 1068 17 1076 03 881 18 1075 04 881 19 1054 05 782 20 721 06 742 21 619 07 751 22 593 1
08 765 23 565 09 750 24 594 10 762 25 603 11 763 26 651 12 744 27 686 13 844 28 686 14 1072 29 689 15 1077 30 690.
Z !
UNIT SHUTDOWNS AND POVER REDUCTIO!G
.,JCKET.NO. 50-328 UNIT NA!!E Sequoyah Two DATE October 7, 1988 COMPLETED BY D. C. Dupree REPORT !!0NTl! Septeimber 1988 TELEPl!ONE (615) 870-6722 n
U w
o gg oyg Licensee g-r, we, Cause & Corrective No.
Date c
j 8; yjg Event o
gg gg Action to y^
go jge Report i o
go gu Prevent Recurrence b~
$$5 R
12 880903 5
0 F
5 Reduced load for core life extension.
13 880919 S
D F
5 Reduced load for core life extension.
8F:
Forced 2p,33,,
3 'ethod:
- Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-itanual for Preparation of Data D-!!aintenance or Test 2-!!anual Scrae.
Entry Sheets for Licensee C-Refueling 3-Automatic Scras.
Event Report (LER) File D-Regulatory Restriction 4-Cont..of Existing (NUREG-0161)
E-Operator Training & License Examination Outage F-A.lainistrative 5-Reduction-C-Operational Error (Explain) 9-Other 5Exhibit I-Same S$urce ll-Other (Explain)
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eva naro tono.o.aal G4UCLEAR PLANT OPERATING STATISTICS SEQUOYAll NUC1. EAR Plant Period Hours 720 Month SEPTEMBER gg 88 item No.
Unit No.
UNIT ONE UNIT '1NO PLANT 1
Averace Hourly Gross LoJd. kW 0
855,917 855.917 2
Ma=6 mum Hour Net Generation. MWh 0
1,088 1,088 3
Core Thermal Energy Gen. GWD (tl2 0
77.9253 77.9253 4
Steam Gen Thermal Energy Gen.. GWD (t)2 0
78.3200 78.3200 j
5 Gross Electrecal Gen.. MWh 0
616,260
__ 6 stat 6on use. MWh 4,728 _
28,094
._ 616,260 7
Net Electrical Gen.. MWh
-4,728 _
32,822 l
588,166 583,438 6
a Station use. Percent N/A 4.56 5.33 9
Accum. Core Avg. Exposure. MWD / Ton!
0 11,841 11,841 10 CTEG This Month.106 BTU 0
6,383,018 6,383,018 6
11 SGTEG This Month,10 RTU 0
6,415,347 6,415,347 12 13 Hours Reactor Was Critical 0.0 720.0 720.0 14 Unit Use, sours.M n.
0 00.
720:00 720:00 15
_ capacity F actor. Percent 0.0 72.35 36.18 g Jr.,
Turbine Avail Factor, Percent 0.0 100.0
,40_
1?
Generator A,a,i racto. Percent 0.0 100.0 50.0 p
is Tordor:.n. Ava,i F actor. percent 0.0 100.0 50.0 5
19 Peactor Avail. Factor Percent 0.0 2
70 Unit Avail. Factor Percent 0.0 100.0 50.0 100.0 50.0 21 Tureine Startuos 0
0 0
22 Reactor Cold Startons 0
0 0
n 24 Gross Heat Rate, Utu kWh N/A 10,360 10,360 f
25 Net Heat Rate, Atu/hWh N/A 10,850 10,940 J
26 Cross Heat Rate Stu/kWh(w/o oil) 10,360 C
?? Net Heat Rate Bru/kWh(w/o oil) 10,9/ G g,.
28 Throttle Preuure. es 9 N/A 871.0 871.0 29 Throttle Temperature, F N/A 530.1 530.1
.,e 30 F u haust Pr enuee, InHe AtTs N/A
- 2. 9 2.9 g
31 intak e Water Temo.. *r N/A 77.40_
77.4 1?
13 Main F ecowater, M ib/nr N/A 11.1 11.1 y
. ~-
3f,
~
17 Full Power Capacity, f f PO 404.8t-Jb3.05 768.51 13 Accum Cycle Full Power Days, EFPO 0.0 308.3156 308. 31 $ t, p
n ogised Ine Generaten. Gano s 10,824 2 _,a.1.StLutatinq Value. Otu/ Gal 138,000
.41 Ogset Generation MWh 164 t'
Ma s. Hour Net Gen Man. Day Net Gen LoJd
'N MWh Time Date MW" OJte Factor. %
a 43 1.088 0400E 9-15-88 25.86[
9-15-88 74.48 R emai k s - A F or SF NP this value is M A D/ST U and for SONP atxt W BNP this value is MWOiMTU.
j 2(t) indicates Thermal Ersergy.
w I
nm semitico 00T 1 F 1988 cate om,ed
_sf L Piant MJnager
. tv4 ru A tom se8 NUCLEAR Pl. ANT OPER ATING STATISTICS SEOUOYAH NUCLEAR Plant i
Perro. Hours 8,700 Month FISCAL YEAR 88 g9 stem No.
Unet No.
UNIT ONE UNIT WO PLANT 1
Averace Hourly Gross Lead. kW 0
909.944 909.944 2
Ma=imum Hour Net Generation MWh 0
1.108 1.108 I
3 Cnre Thermal Energy Gen. GWO (t12 0
332.4839 332.4839 4
Steam Gen Thermal Encegy Gen, GWO (tl2 0
333.9458 333.9458
{
5 Gross Electrical Gen., MWh 0
2.628.600 2.628.600 6
station Use. MWh
$5.426 201.775 257,201 i
[
7 Net Electrical Gen.. MWh
-55.426 2.426.825 2,371,399 [
~
8 Station Use, Percent N/A 7.68 9.78 l
9 Accum. Core Avg. Esposure. MWb/ Ton) 0 11.841 11,841 10 CTEG This Month,106 BTU 0
27.324.419 27.371.j9J [
6 11 SGTEG This Month,10 BTU 0
22,154,167 27.354.167 12 13 Hours Reactor Was Critical 0.0 299s.10 2993.10 14 Unit use. Hour 5 Min.
Oi00 2888t45 2888t45 15 Capac3ty Factor, Percent 0.0 20.30 12.65 g
16 Turbine Avast Factor Perrent 0.0 38.18 19.09 17 Generator Avail. Factor. Percent 0.0 38.28 19.14_
4 IB Tof boqen. Avait, rattor. Percent 0.0 38.18 19.09 E
19 ocactor Avail _ ractor. Percent 0.0 3
38.11 19.06
_2L. un.t Ava,s. rector. Percent 0.0 32.89 16.44 21 Turb,ne startues 0
7 7
22 Reactor Cold Startuns 0
1 1
_93 24 Gross Heat Rate, HtuaWn N/A 10.360 10,360 l
?5 Net Heat Rate, ntuchWh N/A 11.220 11,480 y
26 Gross Heat Rate Btu /kWh(w/o oil) 10,630 Net Heat Rate Bru/1<Wh(w/o oil) 11.490 g
2s Throttie pressure. ps,9 N/A 859.02 859.02
& 2 inrnttie Temnerature, r N/A 528.04 528.04 d
30 r a haust av essure, inHg Abs N/A 2 9 7____
2.97
[
31 intak e Water Temo, *F N/A 76.03 76.03 12
, 33 Mam F eed*ater, M id/hr N/A 11.7 11.7 34 g
35 36 37 r..is Powe, capacit y, E rPo 404.86 363 e5 768.51 38 Accum. Cycle Full Power Days, ErPD 0.0 308.3150.
308.32 p
39 c.: F ned for Generation, Ga6 tons 2 _,yL_nen1Lnly alue. ntax,4 t 84,942 41 Dssel Generation MWn 138,000 1,281 3,
Ma s. Hour Net ben.
Man. Day Net Gen LoJd
~~
MWh T ime Date MWh Date Factor.'%
43 1,108 0300E 5-31-88 r26,288 5-31-88 24.81 R emas k s. A F or HF NP this value is MW D/ST U and for SONP and W BNP this value is MWO/M T U.
l 2(t) indicates Thermal Energy.
nat,submine._00T 151988
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REACTOR HISTOGRAM SEQUOYAH UNIT ONE 100 90 -
80 -
gz d
70 -
m E
60 -
E 5
50 -
i 3:o 40 -
n_
30 -
H W
20 -
m*
10 -
Unit In Mode #5, #4
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13 17 2i 25 29 SEPTEMBER 1988
REACTOR HISTOGRAM SEQUOYAH UNIT TWO 100 1
2 1
2 1
\\3 90 -
3 L 2 80 -
3q2 g
Z A
d 70 -
2
(,
x
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50 -
3:
O 40 -
30 -
s S$
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UNIT Tk'O REACTOR HISTOGRAM ANALYSIS 1.
Reactor @ 98 percent, high steam flow alarm initiates at power greater than 98 percent.
2.
Redut:ing load /(Load reduced) for core life extension.
3.
Holding for operator training.
4.
Increaso load to increase auxiliary steam hcader pressure.
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9 SWNARY OF MAINTENANCE ACTIVITIES (NPRDS MAINTENANCE ITEMS)
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.1R2.... U f %it ;Yt ANRE!! DATE.... DE!CRIPTI3.........
.......... (DQE CTIVE ACTION.........
. 82371401 W.iOP 063 0073 09/10/$11 nt]P-043-c073 B,ti10CFk$0.%1:3, VALVE INTERLOCK ZUht SWITCH (1-Z!-074-4021/2)
WILL 30T $i23E FRC3 (CMTP0t. 20 CPI TO RESIDUAL MAT KMOUAL PunP B4 INLET i
FLOW (DNTRE VALE WAt Oui C7 ADJUSTFINT PPEVENTING CONTACT! FROM MAKINC UP, THIS CanPUENT WGED llAVE fl0 DEG9AMD PdD THE ZLes SWITCH IRif HAVE lEEN ADJUSTED.
ADJUSTED ZWE SWITCH (1-23-07%-M21/2) l BY LODSEMING FOUR M0WTING BOLT! AMD SLIDING THE $MITCH UP WTIL IT MAK CONTACT. RETIGHTEED MOUNTING Bll! AND HAD OPENTOR TO $1ROKE THE VALVE
{
(1fp11P-043-0073). ALSO PERFDRf!ED A CONTINUITY TEST W RE31 DUAL MAT En0V%
PunP B-8 INLET FLN CONTRE VALK r
(1-nVnP-474-0021). (WR F237140).
I t:W1401 ICV Ci?
- 3R 12/21/8714CV 047 0047 8. cmp 28,MPPDn3,THIS THE TEFLON 3 EAT lh8 FOUND WITH A iMALL VALVC !! LERIM TF700H. PLEATE FLAT tJEA DUE TO NURMAL WCM OR AGING.
REPATR.
REntP/CD VALVE FRM LIE AND KPLACED TEFLDN SEAT. K I:t3TALLED VALVE AND ADJU3 FED MECNMICAL STLPS AND LinIT!.
(WR B2Mt0).
I:37'4% 1 :Ci? 030 0374 tt/30/881 tCIC-030-0074-A,CHMA3,lREAKG WILL iME FEMER'S (CLD$E) Test (UTTON HAS
)
NCf CLD;E IN TEST ?3!!!!:3.
H. 0,
$f0CK CLDtED REPLACED n!CRO-! WITCH MD CCNTACT3 CW TEST CL !E !VIICH WILL NOT R$O KPLACED BRREN IrDICATOR LICHT.
(
CFD. FEEDE! 10 C'7.?tt.TE FCNCITCRAL RACKED !.REMER INTO POSITICN AND CYCLED TE!T OF W?72!2-01.
[REMER FOR PROPER OPERATIDN.
r753351 1 !CID 047 M9 08/27/8814CID-0#-00994,CbH?8083,T.OTOR THE AUXILIARY CONTACTS WERE DIRif.
CC:,TACTUR DOE! NOT f/,rE-LP CACH T!nt INSPECTED AND CLEMED CC3 TACT A11[MitY.
l VALVE It stR3ED. CLtM (CaTACTOR PER (WR 8753531).
MI-10.M. FEED OFF M3V 0D 142-C-4C I
NmM 1 nelP 047 04910 (9/10/CB 1 ft.'UP-047-04910-A,rs.G0a3,iFE UhlVE f0 TOR CAJKET WAS TCO THIN Cau!IWG OIL TD RDitt :XIusDC It Lt;tI:$ 'jIL ;'!ED310 IE LEM TL1 TOUGH HDU!!MC AND CM10 FLEX.
IETii1Mit MD FL7A!!!D Al PLEtO FEMCVED MOTOR FMIt OPERATCR hab!ING AND i
REPLACED CA!KCf. REIN 1TALLED MOTOR.
EtPt ActD FLD: CC)IKIIT. KTN3fALLG CULE iPlu2nA AND EEtiaMED CrE'arCR ta
![V/IEE (Q! I'764303),
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iMhM631 MINTENANCE MdQU %.YtR1 y
?42.... U FUNC $Y$ ADOR($$. DAi[.... D ESCRIPTICN............................ CORECTIM ACTIC3...
. S7800% 1 f! 042 0137A 01/04/94141-442-4137A,CnNF2H3,f! It $ MING d THE MODITIER (1-FM-Cd2-0137) WAS FOlle
$ m WITH O FLDI OUT Of TOLERMCC HIGH WICH PROVIDED A FAlt( SIGHN. TO THE INCIC.11CR. THIS Mi MVC i.EIN CUC 10 A CHANf4 P4 OPERATING TCMPtWATURES. PIRfDRnED LEDP CALIffATION TO EX50RE COL'RLCT EMIXGS.
T.789338 1 TI 4M 0242 M/21/89141434 0242,CWRDs),$HIELD itD THE FLOW TRAN$RITTER (14T-030-0242) WAS EXHAUST FLOW MONITOR SHOWS ' 14M CFM FOUND WT Of TOLERMCC HICH WHICH FLOll WITH ALL FAN: Off AND NO FLW PROVIDED titt FALE SICML TO THE IMlWCW ITACK.
INDICATOR. PDOT CAU$t U'irJIDEN. THE TRAN1RITf[R DAS KCALIMAIED TO Dt!!MD TOttRMCC M9 REilRINED TO 5tRVICE.
(WHt?89388) t7811341 FL'J 07%
M14 M/20/8814&074-0014,ChMPlie3,fCV FAILID TH( YALW LINEA $C MR ADJU$1ENT NUT WAS
!!-112. ATTACN. i ACCEffMCC CRITERIA.
OB3tRWD GITN THEAS DAMCC lei!CM YALW !TRME !! 3 IN.i $4110 DE 31/2". PREWNTED 9tY ADJU3fMENT. NWTCAUSC INYril! Gait FOR DAM 6C TO PO!!TIWER OR INKNOlk. If MY HAvt BEEll DIE TO UN.E MD REPAIR TO Mtti ACC[PTANCC CRO!3 THEADIWC FROM PNVIOUS RPAIR O(
CRITIRIA. LI!TED A3 CMI), PAGC 4.
IN!iALLATION. KPAIES DAMCED THR[ ADS.
SI192.
VfRITIED KHCH SET ffA ACTUATOR.
tiRottD YALVF PER 311'!2 MD RETWED VALUE TO $ERVICE. 'INitW7Biild) 0 a
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MAINTENANCE SDNARY
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(MECHANICAL) a.
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MQ :L.t$1YKf.?:CI c31 Twt ? e.wY N
PR2... U T 9C SYS A004tst. Kit.... Dtit21PTIDX........
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............. CO Pft C TIVE cCilD,...............
. A1149?111'V CO 0112 (9/10/101-TCV-00-0112,tWRtGuPPDu 1 FCV 43 KUUC'i SPOT! ON plt $ M6 stai 112 LEMS Ptt $1164 D RD.'C.-NACHINED $KIM CUT ON YALVC PLllC MD 1H3TMLIO NO3 CA!KET3. ICIN!iMLED VALVI !$0Y. (utt A11ti71)
A52M031 !N 043 Coi? OV10/S81 eCV-00-0017,tw?0Gu?R0s
- MEL IN0! CATION Of $CRATCht! CN THE l
ADJuti/PEPAlt YLV M Ft0UIFID/VLV 5 TAT MD PLUC.-0I! ASSEMBLED VALW, IEDICATED LEMACE CUWDC PC7TCPM OF P.ACHIFtB M POLI!ED MVC MD ttAT.
l 31-145.10 trPLACED PACKING MD CASKti! WITH NEW M0 REA53CMMED MVE. (Wil A324200) fd212731 FCU 40 0174 CV10/tt 1-FCV-0$3-01T4,ta:Op0Gry?p0u QV sitM 3CRAICHtD MD PLUG hat A TLICMT i
LEMDC TFRU. PttTCin CF !! 1d4.10 Pt.fi Cui.-INtiALLED Nul PLUS ON ITEMi C
DRILLED M0 FING PLUC TD titM.
MCllINED IllN AND ICN3fALLED YALW.
(WRt h32827.0 A5:$27% 1 ICV 0 0 002% 09/10/391-FCV-0434029,*NPfDs 1 f CV-43 24 LEAg3 PLUG WA3 DARACfD.4CMbUC8 $ttR/$
TK7U FOUNO LIAKNC OL11PC KRf0Ilt OF MB PLUS, TOR TO MCNIE $NIF M TCDK
$1 134.10 PtAl C sta CUT ON $TER MD PtLISE9 $IAi, CEILLED M0 PluCED N01 VLV.
A32%741 FCV 00 0071 CV10/:01 FCV-004079,[v.Pf 0GakPren MopML WAt ist St30tf SAstti.-ftnOYt0 i
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$0Ju$i/9CPAIX L1V A3 REWitt0 VLV YALVE (tDINti IN!TALLID NEW CASK [i, CIAf IK0!CATED LEMDC 03DC PttfDEM OF RIFC AM VRVE PLUS. E!DITALLED l'CM(i.
SI-164.10 (wet AS2%74) l A32%751 lCV 043 ell? CV10/!81 FCV-004117,twfN,0.PRDs VALW $ FAT AND PLDC WA! CUT. RACHINt0
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ADJUff/REPAlt VLV +$ ff9'llMD. 41U PLUC, IN$fALLED EN SEAT MD CAltti INDICAftD LIMD:S COtut Ptif0fMMCC OF FEINSTEtt0 VALVC (4NMti. (Ef4 A32147 l
31 144.10 i21:237 1 M O2 0291 DV19/041-L1U-0324M74,Cn*PtGV."Ltt TAILED NOR1L WEAR CN Caitti!, DITC A33LE!LY t
11 153.1 Lt i RATE ![:1. SEPAIRAs MD $FADC.-DIsa;ttneLID VUT, i
Nitrt0. 7.tfA 2Afi 33.4H3 SCTH INSTALLED FtX CA3rit. 0!!C A!!LPRY the t
EtrtRENCE LEM CAft.12 !CTH 3PfDC RIA!stMRID URVE M0 LfPPED t[AT. TDR0ut0 BDMtf 10 400 FT t!1. Mt l
C2 W 37) 12 n 233 1 U O 2 C21? CS/23/C81@.V 032423? AetrXPt*GVALVE FAILED 1 MALL A."C'JNT OF TIA!N CM 31-1!3.1 LEAK FAft it!T. "IPAllA!
Itt '.4. IIA!!tM8 LID YAltt, CLEEID t'Altt i
MLti[0. LEf3 FATE 331:11 !CTN.
![TlitNCE LEM RAlt.12 :CIN ftIN!T& LED INitEAL3. ((A!!Init[D
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UALYt (WR0 F213231) i (2; % 1 fC'J 077 n:108/21/C31 TCV 01740014,tn?i:Gr! PLACE NQtML WEAR DN VRkt.-REPLAC(0 GIAPHLA6R l
DI.VtfM MD CE tt!UILD Vitti A! FtttfD IN VALW De OPEMf0t. f[lif{te O fDC3.
!!-151.1 WA! IIRFUERED C'i l'fi f7803M AND QALLI PAtttD LIAL PATE Itti, tWtt I
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J 022'#.4) 235412 2 i;J C43 0309 01/3)/33 2 f!V CLM::M.E4HCF250.49s nWRDa1,U ;UtPECT VALVE !! SINDIWC D3E 10 tuti ALLT WILL XDT C?EH WITH FMUAL I: t..
aCCOULATICM CW IFTERNALS AL!3 TFEtt us ME! CTE1, !J$PEC1 ALVE BINDDit ("E A LLIClli DEPRE!!I M C3 VALVE to AP t.C 0!! UAltt IMtts1IGAIE ND DISC.-DISA!$[rJLED YALVE MD CLEA%CD REPAI2 As.iECE!!ARY CAT.1 ITER ?IED FCI Vf Ltf. INTEENALS, Lt.PPED DISC ! EAT N PE6CEPMCE C.f $I-145.4 PA2f "B" 00DY ! EAT MD REA$$ErtLED VALVE. Gil 1:21N12)
[29 %S3 1 F3 053 0023 P49/t31-FCV CfM32H.C WCO,PACUPS LEM h0EML PACKING LIAA.-T[ckTD CLD PACEDG MD IN3fALLED NEM PACKIXC. Gtt I:1N3)
- 73 N 3 1 M 033 ON CV14/tt 1-RY 03HM,toPTCO,1-VLU-33-?40 Nm*t WEAR 04 UALVI. FEPLACED CI*J8PEAG3 FAILED !I 1
- !.1 LEAK [ ATE 44.4433 SLFH. MD PACKING O-kIls. EEILTNED UAltt 70
![MCE. (Uti $78N8) i:714215 0 ft' 047 040 09/14/88 0-PEP-047 0440,EnWPPDO. PULL $ttTIING NOFPAL LTAR. THE stuff!NC EDX EUtMDC IUX TD ALLCW DIPECTION CF !TuffD's IDX HAD nut.tD. REPL ACED stuff!MC BOX fuLMING.
lu!HING, $LEEVE MD O-IIIHC. Glitt!4215)
LTS'ill31 ICV 043 00?! CVid/St 1-TCV 04M078.E47PDOdEPAIR LIAKIMC NORML PACK!rG LEAA.-FEMDttD OLD FAC V Atti PECK!M LCfK PND D3fALLED NEW PACKIEG. Gil 1719113) 07394 4 1 T M C43 W9 C9/14/031 fCV-04 HOT 9.EaK7f DO,11En PACKINC
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I MECHANICAL MAINTENANCE I
MONTHLY REPORT FOR SEPTEMBER 1988 i
l UNIT 1 1.
Completed work on various snubbers.
i 2.
Completed repair on 1-FCV-72-39.
3.
Completed repair on 1-FCV-74-28.
f 4.
Completed repair on #3 and #7 heater drain pumps.
l 5.
Completed repair on feeedwater regulator valves.
6.
Rebuilt 2 glycol chillers.
7.
Completed inspection on D/C 18-B and 1A A.
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Installed #2, 3 and 4 RCP plug.'
I 9.
Installed hydrogen analyzer pumps.
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- 10. Completed repair on 1A-A boric acid transfer pump.
- 11. Rebuilt IB-B boric acid transfer pump.
12.
Completed repairs on condensate booster pumps.
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- 13. Repacked condenser vacuum pumps.
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- 14. Repacked AIV level control valves.
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Rebuilt rad monitor pump 1-RM-90-125 and 130.
16.
Installed new valve at 1-VLV-41-730.
L 17.
Repacked 1-FCV-3-67.
18.
Rebuilt 1-VLV-62-682.
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- 19. Completed repair on 1-VLV-68-697.
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20.
Reinstalled main turbine throttle valves.
I 21.
Completed repair on 1-LCV-62-118.
- 22. Completed various activities on the ice condenser.
- 23. Repacked S/G bicwdown valves.
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24.
Installed bus duct cooler coils.
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.o MONTHLY REPORT FOR SEPTEMBER 1988 UNIT 1 t
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- 25. Comp 1 eted repair on 1-VLV-67-940A.
26.
27.
Completed rapair on 1-FCV-74-32.
- 28. Replaced reactor coolant filter.
29.
Reinstalled reactor coolant filter plug.
- 30. Completed repair on lower airlock door DOR-SB-X2A.
- 31. Rebuilt 1-VLV-62-1061.
32.
Completed repair on 1-VLV-30-572.
33.
Installed bio-shield blocks.
i UNIT 2 1.
Replaced condenser vacuum pumps.
2.
Completed inspection on D/G 2A-A.
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Completed repair on lower airlock doors.
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Rebuilt chilled water primary pump "B."
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Continued closure of various CAQRs CARS DRs etc.
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SUMMARY
OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS SEPTEMBER 1988 l
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Major Capital Projects:
PN7102:
ECN 5938 - Replace Feedwater_ltesters 3 and 4 No work in progress at this time.
PN7105:
[CN 5009 - Essential Raw Cooling Water (ERCW) Piping Changeout From carbon Steel to Stainless Steel No additional pipe replacement is scheduled in the near future.
PN1108:
ECH 6720 - Crane Consistency ProRram Unit 1 polar crane limit switch weights remain to be painted.
l Unit 2 polar crane post nodification testing by Electrical Maintenance is complete; however. Electrical Maintenance needs a copy of the vendor's manual.
Auxiliary Building crane (WP 12569) has completed review cycle.
Turbine Building 200-ton cranes (Unit 1/6720-04, Unit 2/6720-03) WPs are approved.
Turbine Building 15-ton crane WPs (Unit 1/6720-06. Unit 2/6720-05) and 5-ton Service Building crane WP (6702-02) has been approved.
Modification of Turbine Building unit 2. 200-ton crane has begun.
TN7115:
FCN 6 719 - Voluretric Int rusion Det ection Syst em ECN 6719 is complete.
PN7122:
DCR 1373 Secondary side No work in progress at this tire.
FN' 130:
ECN 6180 - Poit Accident Monitoring This work is now scheduled by unit 1 cycle 4 (U1C4) and unit 2 by unit 2 cycle 4 (U2C4). _ _ _ _ _ - - _ _ _ _ _.
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Maior Capital Projects (cont.):
PN7132: DCN 0026 - Sewame Iggr.tment Facility and Civil Upgrade Work is nearing cospletion. Connections at the lift station sind electcical evpply to the pumps is in process now.
PN7136: RCN 625% - Mst pgke Dundle Replacement ECM is complete except fo'.' postmodification testing (PNT) and inservice leak tett on unit 1.
Leak checks will be performed during system heatup. Unit 2 leak checks are complete.
PN7161: ECW 5855 - Roolacement of Doors A56 and A57 WP 09679 remains on hold and is partially complete.
ENV ;at DCR 1898 - ECNs 6832 and 6596 - Dry Active Weste (DAW)
Dutidina tiectrical interface work is complete. Workplan closure held for Electrical Maintenance (WP 12418),
checks and update of 301s by Operations, and Operations (WP 12477) pending a revision for packing dry active waste.
SLEntficant items:
PW7199: Miscellaneou_s_Aetivities Under $100.000 This was for various work orders prepared for work under $100,000 total site cost.
This work was done as manpower resources were available.
Other Items:
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ECW 5111 - provide Permanent Power to Manholes 42-46 j
Work stopped for lack of funding.
ECW $503 - Evacuation Alatus 04PS/ Fire Detection 04PS Work stopped for lack of funding.
ECW 5552 - Condensate Dominera11:er Modifications and High Crvd Filter i
Upgrade to higher ranse insttvmentation for condensate dominera11 er f
system neutra11:ation and nonreclaimable waste pumps.
1 WP 5552 Fieldwork is conglete.
ECW 5609 - Evacuation Alam/ Fire Detection Valve 26-290 WP 12387 is 90 percent complete and has been held due to manpower problems.
j IcW 5609 - Alteration to the Makeup Water Treatment Plant l
WP 12576 - Work is approximately 75 percent complete and is on hold for Electrical Maintenance to perform breaker tests. Weed resolution
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of instrument tab description fron WE.
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WP 12633 - Work is approximately 80 percent complete. Hold for f
instrument tab (475601-928) setpoint revisions.
WP 12731 - WP is approximately 80 percent complete. Hold for instrument tab (475601-928) setpoints. Need connection diagrans revisions from NE.
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l WP 12684 - WP is approximately 80 percent complete. Hold for l
l instrument tab (478601-928) setpoints. Need connection diagram i
l revision from WE.
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l WP 12665 - WP is on hold for outage and is 95 percent complete.
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WP 12682 - WP is on hold for outage and is 80 percent complete.
ECW 5626 - Containment Ladders, Unit 1 i
Modifications needs additional design information to complete.
WE j
needs to issue all drawings listed on this ECW. Work has not begun l
because of this holdup.
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Other items (cont.):
ECW 5841 - Hot Shop Fire Protection / Evacuation Alarm -
WP 12360 is complete and in closure cycle.
Need drawing deviation completed.
WP 12637 - All fieldwork for evacuation alarm is complete.
Awaiting Work Request (WR) B240406 to be worktsd to restart fans to do functional test on fire protection.
ECW 5935 - Correct Power Block Lighting Deficiencies WP 12437 is complete and in final review. WP 12215 is in work for FCR 1106 to add approximately 40 more lights. WP 5935-01 is field couplete.
ECN 6196 - Pressurizer Hangers and Valves PMT is scheduled for unit i restart.
Remaining unit 2 work is scheduled for U2C3 refueling outage.
ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment Original design for WP 12238 was rejected by operations.
NE to rework design to comply with operations' needs and attempt to salvaga existing work.
ECN 6388 - Hydrogen Monitors in Switchyard WP 12223 - Work has been stopped due to a lack of funding.
ECN 6429 - Component Cooling Heat Exchanger B Replacement Plate head exchanger and frame is complete. Hangers and pipe which can be installed prior to outage is in work. WP to remove old heat l
exchanger is in review cycle. NE procuring the remaining needed piping material.
Estimated completion date for nonoutage work is during thc conth of November 1988.
ECN 6455 - Upgrade CU-3 Box Battery Packs WP 12295 is field complete.
I EcN 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from HE.
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t Other Items (cont.):
i ECW 6601 - Removal of Unit 1 Emergency Gas Treatment System (IGTS) l Backdraft Dampers I
i FMT remains to be completed by the Mechanical Test Section.
Fieldwork l
is complete.
ECW 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV) l t
All work is complete for unit 2.
Work is complete on unit 1.
PNT 90 l
and SI 166.6 still need to be done - WP 12172.
ECW 6706 14 Support Enhancement / Lost calculations Complete for Unit 1 & 2 Restart.
ECW 6739. Alternate Analysis l
Complete for Unit 1 & 2 Restart.
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ECW 6761 - East Valve Room (EVR) Blowout Panels j
i Unit I work is complete. Unit 2 work is complete.
j ECW 6784 - Documentation to Show Pipe Class Breaks l
t Final closure is awaiting a revision to the plant modification Procedure for deleting requirements to mark shif t supervisor drawings.
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ECW 6815 - 500-kV Switchyard Addition
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All work is complete in the 500 kV switchyard except for grounding of j
the northwest corner of fence, some gravel placement and testing of e
PCB 5010. Closure of WP 6815-05 will be delayed because of problems with the data logger that prevent software changes. A decision has been made to retire the 161 kV equipe.ent in the bay 20 by leaving it J
in place. This decision will require revision of design drawings by j
means of an FCR.
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r Other Items (cont.):
ECW 6860 - Control Room Bullet Resistivity - DCR 2268 - ECN 6860 All work is complete.
ECW 7078 - Install Hangers - Main Steam Piping Corplete.
DCW 1000966 - Remove Hydrogen Analyzers Tubing The workplan lacks pMT, ECW 7093 - Replacement of Feedwater Pipe Complete.
DCN 2000188 - Install Needle Valve for Hydrogen Analyzers The workplan lacks PMT.
DCN 10 - Hydrogen Analyzer Check Valves The workplan lacks PMT.
DCN 341 - Pressurizer Drain Pipe / Hangers Complete.
Instrumentation Verification Program For unit 2, there have been 953 discrepancies issued to MODS to date with 476 not required for restart. All discrepancies required for restart have bica coepletedt 69 nonrestart discrepancies are open.
For unit 1, there have been 532 discrepancies issued to M003 to date with 218 not required for restart. The 314 required for restart are complete.
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Other Itmas (cont.):
l DCW 224 - RHR Slope Rework Work is complete.
DCW 27 - Double Isolation Valves 1
Work is complete.
k RCW 7345 - Valve Shima Work is complete.
DCW 373 - Flex Hose Rework Work is complete.
DCW 214 - AFW Tap Rotation Complete. Systems Engineer to test.
DCW 242 - Sense Line Hangers Work is complete.
QGE M - Ice Condensate Expansion tellows Work is in process.
DCus 229 an M - H2 Analyser Modification Field work complete testing remaint.
DCW.300 - ERCW Modification for Microbiologically Induced Corrosion (MIC) A Train is Complete 5 Train in Work Unit I work is complete.
ECW.4594 - Dry Active Waste Piping Interface l
l 32 - Workplan is closed.
2 - Complete.
Closuro in process.
30!s are complete. The
.re for the fire detection system of the Dry Active Waste Dus.%tng is in the process of being updated by Electrical Maintenance. _
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