ML20206J704

Monthly Operating Repts for Oct 1988 for Sequoyah Nuclear Plant

ML20206J704
Person / Time
Site:	Sequoyah
Issue date:	10/31/1988
From:	Dupree D, Shawn Smith TENNESSEE VALLEY AUTHORITY
To:	NRC
References
NUDOCS 8811290082
Download: ML20206J704 (46)

Text

{{#Wiki_filter:' o 4 TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP (FORMERLY OFFICE OF NUCLEAR POWER) SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY C05DlISSION OCTOBER 1988 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l f' 2 - .=s Mfd / Submitted by: S. J. S dt'h, Plant Manager i .s / b, 8811290082 881031 h PDR ADOCK 05000327 l R FDC

y G s ? 4 i i OPERATIONAL SDDIARY 1 l 1 I i .--t

a s I 4 ( TABLE OF CONTKHTS Pago 1. Operational Summary Performanco Summary 1 Significant Operational Events 1-4 Fuel Performance and Spent Fuel Storago capabilities 5 PORVs and Safety Valves Summary 5 Special Reports 6 Licensco Events 7-10 Common Abbreviations and Systems of Sequoyah Nuclear Plant 11-14 Radwasto Summary 15 Offnito Dose Calculation Manual Changes 15 11. Operating Statistics A. NRC Reports Unit one Statistics 16-18 Unit Two Statistics 19-21 B. TVA Reports Nuclear Plant Operatint Statistics 22 1 Unit Outano and Availability 23-24 Reactor Mistogram 25-27 III. Maintenanco Summary I v.lectrical Maintenanco 28-29 Instrument Maintenance 30-31 l Mechanical Maintenance 32-35 Modifications 36-41 r 028Bf/baf

o i i t PERFORMANCE SUSNARY ge,tober 1988 The following summary describes the significant operational activities for the month of October. In support of this summary, a chronological log of significant events is included in this report. UNIT 1 Unit I remained in an administrative shutdown the entire month because of design control review, configuration control updating, and resolution of significant employee concerns. Unit I has been off line 1,166 days. Extensive testing and various system alignments es well as other restart activities are being performed for restart. On October 20, 1988, the unit entered mode 3 (hot standby), one step from going critical. This is another significant milestcne for TVA. Enthusiasm and anticipation are high as criticality and power operation get closer and final testing and system alignment near completion. UNIT 2 Unit 2 continues to operate exceptionally well since restart. It was online the entire month with a capacity factor of 61.0 percent. Since restart, unit 2 has generated over 3.1 million MKhs (3,166,290 MWh) of electrical power and has been in continuous operation for more than four months (131 days). Unit 2 was reduced in power for core life extension. There are 35.5 effective full power days remaining in the core. l l SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 10/01/08 0001E Mode 4 RCS 0 2480F, 270 psi. 10/04/SS 0209E Received an unanticipated reactor trip signal due to Over Power Delta T while performing maintenance on loop di tempetature instrumentation. 1640E Received an unanticipated reactor trip signal on loop #4 due to steam flow / feed flow mismatch while performing maintenance on #4 S/G steam flow and level instrumentation. 1

i I L l SIGNIFICANT OPERATIONAI, EVENTS (continued) Unit 1 Date Time Event 10/09/88 1218E Began temperature increase to 3250F. 1400E Began RCS cooldown to investigate secondary steam Icaks. 1734E S/G pressure operated relief valve Icaking through. 2040E Resitmed heatup. 10/10/88 0034E RCS @ 3340F, 400 psi. 10/14/88 0034E Remove #4 RCP from service to replace water seal leak off temperature indicator. 10/17/88 2209E

1. 4 RCP returned to service.

10/18/88 1113E Received an unanticipated reactor trip signal on loop

1. 3, lo-lo S/G 1esel.

Plant equipment oscillated due to use of portabic radios by maintenance personnel. 1513E Received an unanticipated reactor trip signal due to hi-hi S/G #1 level causing a feen.ater isolation. Maintenance was being performed on level indicating ins t rumen ta t ion. 10/20/88 0015E Entered mode #3. 0130E RCS @ 3700F, 675 psi and increasing. 1506E RCS A 5250F, 1500 psi. Maintaining current status. 10/21/SS 2020E Increasing RCS temperature to perform testing on the steam driven AW pump. 10/22/8S 0024E RCS 0 5350F, 1500 psi. 10/26/8S 0122E Testing and maintenance complete on the steam driven AFW pump. 1340E Began RCS cooldown for the cross calibration testing of the RCS temperature sensing devices (RTDs). IS52E Terminate cooldowu. 4 i 2335E RCS @ 4450F, 1200 psi. 1 1 i {,.

6 i t l SIGNIFICANT OPERATIONAL EVENTS (continued) Unit 1 Date Time Event 10/27/88 0424E Cross calibration test complete. 0515E Begin heatup to 5250F. 1027E RCS @ 5250F. 10/28/88 0130E Begar heatup to 5470F. 0437E RCS @ 5470F. 1745E Pressurizing to 1950 psi. 10/29/88 0639E Began cooldown to 5250F, maintenance on the pressurizer safety valves. Valves are leaking through. 0752E RCS @ 5450F, 2220 psi. 1140E RCS @ 5320F. 1210E Began heatup for rod drop testing. 1600E RCS @ 5450F, 2225 psi. 1900E Began rod drop testJng. 10/30/88 0130E Began RCS depressurization for maintenance on ruptured membrane on Ul!I. 0328E Rod drap test completed. 0415E RCS @ 1830 psi. 10/31/88 2400E RCS @ 546oF, 1760 psi. Extensive testing and maintenance continue for restart and power operat!on. Unit 2 Date Time Event 10/01/88 0001E Reactor @ 65 percent, 720 MWe. Holding for core life I extension (CLE). r 10/21/88 2100". Began load reduction for maintenance on #1 RCP DC volt l control power supply circuitry.

g t t SIGNIFICANT OPERATIONA1. EVENTS (continued) Unit 2 Date Time Event 10/22/88 0500E Reactor 0 30 percent, 310 MWe, 1930E Began power increase. Maintenance complete on #1 RCP. Temporary cabic installed per TACF 2-88-2018-202. 10/23/88 0217E Reactor 0 64 percent. 715 MWe. Holding for CLE. 2100E Reactor 0 65 percent, 745 MWe, 10/31/88 7400E Reactor 0 65 percent. 740 MWe. Holding for CLE. I

g i 4 FUEL PERFORMANCF. Unit 1 The core a'.; age fuel exposure accumulated during October was 0 MWD /MrU with the total accan.olated core average fuel exposure of 0 MWD /MTU. Unit 2 The core average fuel exposure accumulated during October was 762 MWD /MTU with the total accumulated core average fuel exposure of 12603 MWD /MTU. SPENT FUEL PIT (SFP) STOR ACE CAPABILITIES The total storage capability in the SFP is 1,386 bundles. However, there are five cell locations which are incapable of storing ; pent fuel. Four locations (A10, All, A24, and 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 bundles. PORVs AND S6FETY VA!.VES

SUMMARY

No PORVs or safety valves were challenged in October. \\ x 1 SPECIAL REPORTS The following special report and revision were submitted to the NRC for the month of October. 88-14 The following cables are not protected by a three-hour fire barrier as required by LC0 3.7.12 1. Cable 1PP750A (6.9kV feed to 480V shutdown board transformar 1A-A) and IPP759A (6.9kV feed to AS0V shutdown board transformer 1A2-A) were routed and protected through the vital battery V room. A fire in vital battery V room with vital battery V system in service to vital battery systems II or IV could cause loas of either of thene train 'B' associated DC power systems and loss of above spccified unit 1 train 'A' shutdown board transformer feeds. j 2. Cable B1641 is routed through vital battery board room II and provides power supply from vital battery V to the battery board I. Cable B16SIV is routed through vital battery board room III and provides power supply from vital battery V to the battery i board IV. With vital battery V in service a fire in either of these two rooms could cause the loss of two redundant channels of DC vital power systeus. 3. Cables IB2511 and IB301I were installed in the vital battery board room I, and cables 2B111II and 2B16III were installed in j the vital battery board room IV. These cables are the normal DC power supply cabics to 480V shutdown boards IB1-B, 1B2-B and 2Al-A, 2A2-A. A fire in these rooms could caur.e loss of DC power control bus of the boards plus loss of the applicabic channel of vital DC supply. a Roving fire watches have been established and will continue j until Appendix R requirements have been met. 1 83-14 This revision provides details concerning noncompliance with Rev. I requirements of unit 2 License Condition Section 2.C.13.c of the unit 2 Facility Operating License. The noncompliance conditions are applicable to both units 1 and 2. I D m e

y i s t i LICENSEE EVENT REPORT (S] The following licensee event reports (LERs) were transmitted to the Nuclear Regulatory Commission in October 1988. t Dese.-lption of Event LFR 1-88033 On October 4, 1988, at approximately 0208E, with unit 1 in mode 4 f d and unit 2 at 65 percent reactor power, an unplanned reactor trip signal was generated on unit I while IM personnel were performing a j 3 channel calibration on loop 2 RCS narrow range temperature i instrumentation and a loop 1 RCS temperature instrument failed. On October 3, 1988, at 2215E, IM personnel received permission from c the unit 1 MCR to resume calibrating RCS AT/Tavg loop 2 in accordance with SI-94.22. "Channel Calibration of AT/Tavg Channc1 II, Rack 6 (T-68-25)." The applicabic channel II bistables f for SSFS AT/Tavg functions had been placed in the tripped i condition and the IM personnel were dalibrating the lead-lag logic 1 associated with the loop. All unit 1 rod control cluster assemblics were fully inserted into the core and the reactor trip breakers were tagged open. At 0208E. October 4, 19SS, the reactor i trip first out annunciator alarmed fnr an Over Pressure } AT (OPAT) reactor trip. Operations personnel observed erratic readings on the RCS channel I narrow range temperature indicator and the annunciation of the channel I bistable lights for en OPAT i reactor trip. This condition occurred when the channel I OPAT j reactor trip setpoint was exceeded which tripped its associated f bistables and the SSPS reactor trip two out of four logic was met ( l with the previously tripped channel II RCS AT/Tavg bistables. l Corrective action was to reset the reactor trip signal annunciation l and initiate a WR to diagnose erratic behavior of the temperature Indicator. Troubleshooting concluded that there was a failure of [ 4 the loop dynamic compensator. A new compensator was calibrated and r i installed. An analysis is being performed on the failed module. l ) 1-8S034 At 1359E, on September 29, 1988, with unit 1 in mode 4 and unit 2 at 65 percent power, a train 'B' ABI occurred. Modifications personnel were performing work inside 0-M-12 (panel located in the MCR) under WP-11266 R1 which was implemented to install a seal-in I circuit for an ABI caused by a high radiation condition in the f L I Auxiliary Building. The cause of this ever.t was an electrician inadvertently bumping a time delay relay (TDR) for 0-RM-90-103 *the I l spent fuel pool area RM). The investigation of this event resulted i in two recommendations to prevent recurrences (1) the appropriate }l monitors would be blocked when work is performed inside a MCR panel i in 0-M-12, and (2) to install a protective cover for appropriate [ I i TDRs. TVA will evaluate both options and revise this report by December 31, 1983 to provide the course of action to be taken. i i l 1 l [ l I t

g 1 s t i 4 LER 1-88035 On September 27, 1988, at approximctely 1138E, with unit 1 in mode 5 and unit 2 at 65 percent power, an ABI occurred. Before this event, a UO had been alerted to a problem with cent.rol power when an annunciator alarmed. Additionally, the UO noted that a feedwater heater string had isolated. The UO refere'nced SOI-55-1M1-XA-55-1C, "/.nnunciator Response Control Power and Fire Protection," which directed him to check the circuit breaker panels. An inspection of the circuit breaker paneln revealed that breaker 24, which supplies power to several feodwater heater LCVs for unit 1 had tripped. At 1138E. the UO reset and reclosed the tripped breaker. In the process of reclosing the tripped breaker, his hand slipped off of breaker 24 and hit breaker 23 in the adjacent breaker column. Breaker 23 supplies power to several RMs including the Auxiliary Building vent RM. This RM is designed to fail in the operated mode on a loss of power and consequently, an ABI occurred when the breaker was inadvertently tripped. Breaker 23 was reclosed at approximately 1140E, and Operations initiated recovery procedures for the ABI which were completed at 1337E. To aid in the prevention of recurrence of this event, a training letter has been issued to all licensed operators detailing this event. 1-SS036 On October 4, 19S8, at 1640E, unit 1 in mode 4, a reactor trip signal occurre1 as a result of a steam flow to feedwater flow mismatch of greater that 40 percent coincident with a low signal being present. The flow mismatch signal was a result of SI-9S.1, "Channel Calibration for Engineered Safety Feature Instrumentation (Steam Flow and Pressure) Calibrational Work." On October 4, 1988, at 0940E, IM personne,1 notified Operations that testing would be performed in accordance with SI-98.1 to calibrate the S/G loop 4 steam pressure transmitter (Channel !!). At 1430E, IM personnel also began work in accordance with IMI-118. "Filling of Sealed Instrument Systems," to backfill the senseline for the loop 4 steam pressure transmitter which had been previously calibrated on October 3, 1988. System design logic is such that when the test signal for calibrating the steam pressure loop was injected concurrently with the backfilling of the flow transmitter, porturbationa induced from the backfilling allowed the histable to trip for steam flow /feedwater flow mismatch. The S/C low level signal was a result of the bistable being tripped for preexisting instrument failure until malat"sance could be performed. A combination of a breakdown i aagement systems and procedural inadequacy allowed for this f;ilure to identify the potential for logic interactions. To prevent recurrence, the Site Procedures Staff will complete a review and revise as necessary each reactor protection / engineered safety feature calibration procedure to ensure associated trip functions are identified and tripped before bsginning work. In addition, this event will be reviewed with the appropriate Operations and Instrument Maintenance personnel.

t LER 1-8S037 On September 25, 1988, at approximately 1502E, with unit 1 in mode 5, an inadvertent reactor trip signal was generated on unit 1 during a L performance of SI-94.4 "Reactor Trip / Engineered Safety Feature / Accident Monitoring Instrument Steam Generator Level Channel Calibrations." Before the occurrence of this event, a reactor trip breaker (RTB) "A" was in the closed position and RTB "B" was open. When the reactor trip signal was generated, the RTB "A" opened as. designed. All control rods were fully inserted and rod withdrawal system was incapable of rod withdrawal; therefore, an actual reactor trip did not occur. IM personnel started the performance of the SI t on June 17, 1988, and placed all S/G icyc1 loops bistables in the ( tripped position as required by the procedure. Subsequently, the SI t was interrupted to allow performance of other sis. During the performance of other sis, two out of three bistables of S/G IcVel loops were reset to normal position (nontrip position). The performance of SI-94.4 was reinftiaced on September 25, 1988, without reverification of plant conditions. The IMs assumed that S/G icyc1 loops bistables were in the tripped position, but in fact only one of i the three bistables was in the tripped position. While the IMs were p backfilling the transmitter sense line, a low-low S/G water level l condition was simulated and the associated bistable was tripped. As I a result, a reactor trip signal was generated and RTB "A" tripped, as two out of three logic required for low-low S/G water 1cvel was satisfied. The cause of the event is attributed to the fact that the test director failed to follow AI-47, "Conduct of Testing," requirements which require reverification of plant conditions upon reentry into a test after interruption. As a corrective action, IM test directors will be retrained on AI-47 requirements emphasizing i the need to verify plant conditions before reinitiating performance, f 2-88037 On September 19, 1988, at 1827E, with unit 2 at 97 percent power, a CVI occurred as a result of a spurious series of spikes on the containment upper compartment RM particulete channel 2-RM-90-112A. Operations personnel immediately verified that no actual high l radiation Icvels existed and then proceeded to perform steps for plant recovery. An immediate invcstigation into the actuation did not discover any conclusive cause that may bave attributed to the i spurious signal. On September 21, 1988, at 1909E another CVI occurred similar to the previous one on September 19, 19SS, as a result of spurious spiking on the output of 2-RM-90-112A. Operations personnel again verified that the signal was inadvertent and i proceeded with plant recovery. Subsequent to the second CV1 i recovery, the RM remained out of service for maintenance personnel to { perform additional troubleshooting. During this troubleshooting, a spurious AC ripple voltage was discovered on the 24VDC power supply output which coincided with the high radiation spikes. The power supply was replaced and the RM returned to service. The output of the RM was monitored closely, however; some reduced spurious spiking continued to be observed as the RM electronics warmed up. During ad.iitional testing, spurious electrical spikfng was observed on the particulate detector output to the main processing module in the MCR. -

\\ f f t LER o 2-88037 The detector preamplifier assembly was replaced and the RM returned (cont.) to service on September 23, 1983. TVA concluded that both CVIs had been caused by the particulate detector preamplifier degrading over a period of time. Since no actual high radiation levels existed during these events and all CVI equipment actuated as designed, this t conditinn is not considered to have had an adverse impact on nuclear safety. To prevent recurrence, the applicable RM function.il test sis will be revised to include testing for detection of AC ripple voltage on the 24VDC power supply. I 2-88038 On September 29, 1988, at approximately 0910E, with unit 1 in mode 4 and uait 2 at 65 percent power, L.C.O. 3.8.1.1 was entered after it had been discovered that the potential transformer (PT) fuses for the alternate feeders to 6.9kV unit boards 2A and 20 were not installed. This condition would have prevented the automatic transfer from unit j station service to common station service following a unit trip. As j a result, one circuit between offsite power and the Class 1E l l distribution system was considered inoperabic. At 0956E, LCO 3.8.1.1 was exited when the fuses were reinstalled. A review of work activities relative to the unit boards and start buses revealed the ). PT fuses were removed following a storm that occurred on August 15, l 19S8. This resulted in the loss of start bus 2A. The fuses were not i j reinstalled before placing the start bus back in service. The root cause of this event was determined to be that 501-202.1, "6900 V Start Buses," which was used to put start bus 2A back in service, did not contain steps to ensure that the PT fuses were installed. To prevent recurrence, 501-202.1 will be revised to include steps to verify PT fuses are reinstalled and a training letter will be issued to licensed operators who are responsible for closing out H0 j clearances to heighten their awareness level for the potential for ] this type of event. 1 i 2-8S032 This revision provides updated details concerning long-tes n Rev. I corrective actions. l 3 a i I I i J ) _10 d 1_. ~

( i f l l i ABBREVIATIONS i Page 1 of 3 i 1. ABCTS Auxiliary Building Gas Treatment System Auxiliary Building Secondary Containment Enclosure l 2. ABSCE 3. ABI Auxiliary Building Isolation Auxiliary Feedwater 4 AFW j 5. AOI Abnornal Operating Instruction Assistant Shift Operation Supervisor 6. ASOS 7. AUO Assistant Unit Operator Boric Acid Storage Tank 8. BAT Boron Injection Tank 9. BIT 10. CAQR Condition Adverse To Quality Report l 11. CCP - -Centrifugal Charging Pump Component Cooling Water 1 *J. CCW

13. CRI Control Room Isolation 14.

CREVS Control Room Emergency Ventilation System f Containment Spr'ay System l

15. CSS (CS)

J l 16. CVI Containment Ventilation Isolation i

17. D/G(s)

Diesel Generator (s) I l Design Change Notice 18. DC." Design Change Request 19. DCR Emergency Core Cooling System 20. ECCS Engineering Change Notice 21. ECN ) Emergency Cas Treatment System 22. ECTS Electromagnetic Interference 23. EMI Eniironmentally Qualified / Environmental Qualification 24 EQ i I 1 -1L~

o \\ a l l 1 o-t i ABBREVIATIONS Page 2 of 3 t 25. ERCW Essential Raw Cooling Water 26. ESF(A) Engineered Safety Feature (Actuation) l Flow Control Valve I 27. FCV i s

28. - FSAR Final Safety Analysis Report f

f 29. FWI Feedwater Isolation

30. COI General Operating Instruction 31.

GPM Gallons Per Minute i 32. H0 Hold Order t 33. IM Instrument Mechanic l 4 34. IMI Instrument Maintenance Instruction i 4 l 35. 1.CV Level Control Valve I j { j 36. LCO Limiting Condition for Operation l 37. LOCA Loss Of Coolant Accident i 38. MAST Maximum Allowable Stroke Time I r Main Feedwater' Isolation f ,j

39. MFI 40.

MFP Main Feedwater Pump 1 j 41. MOV Motor Operated Valve s 42. MSI i Main Steam Isolation I i 1 43. MSIV Main Steam Isolation Valve 44 MCR Main Control Room Nuclear Engineering (formerly Division of Noc1 car Engineering) 45. NE l 46. NSS Nuclear Security Service J I 47. NSSS Nuclear Steam Supply System i { 48. PORC Plant Operation Review Committee i 1 j i L i i I i i l ' ^ ,,ce,- er.-w ..-,~..%.-,m-m .rm,_ ,m,m-__.--m.-- .m.-- ,-e,--e-.-

RI. \\ a t 5 i ABBREVIATIONS i Page 3 of 3 Potential Reportabic Occurrence 49. PRO Reactor Coolant System /(Reactor Coolant Pump) 50. RCS/(P) Residual lieat Removal 51. RilR 4 Radiation Monitor (RAD Monitor / RAD MON)

52. RM Refueling Water Storage Tank

53. RWST Significant Condition Report 54.

SCR 55. SFP Spent Fuel Pit i Steam convrator(s)

56. S/G(s)

I Surveillance Instruction /or Safety injection 57. SI Special Maintenance Instruction SS. SMI System Operating Instruction 59. SOI i Sequoyah Nuclear Plant

60. SQN l

61. SR Surveillance Requirement i ? 62. SSPS Solid State Protection System i j 63. TACF Temporary Alteration Control Form Technical Instruction-64. TI Technical Specification (s) 65. Ts(s) Upper Head Injection 66. Ull! I 67. UO/(S)RO - Unit Operator /(Senior) Reactor Operator Valve i 68. V!N Workplan 69. WP Work Request

70. WR i

1 2 j i i i.

a \\ f I i VARIOUS SYSTEMS _0F SE_QUOYAH NUCLEAR PIANT SYSTEM J0DE SYSTEM TITLE [ 1 Main Steam System (Turbine) (MSr.) 2 Condensate System (FW Heaters) f 3 Main ar.d Auxiliary Feedwater System Fxtraction Steam System ~ 6 Hecter Drains and Vents System 14 Cononnsate Demineralizer 15 Steam Generator Blowdown System l 24 Raw Ctoling Water System l 27 Condenser Circulating Water System l 35 Generator cooling Systema j 36 Feedwater/ Secondary Treatment System 37 Clanes Seal Water System f 42 Mair/ Auxiliary Feedwater Control System 47 Turbogenerator Control System t 54 Inaection Water System t 58 Cencrator Bus Cooling System 61 Ice Condenser System j 62 Chemical and Volume Control System i 63 Safety injection System 64 Ice Condenser Containment System l 65 Emergency Cas Treatment System 67 Essential Raw Cooling Water System 68 Reactor Cool.mt System (Steam Cencrator) I 70 Component Cooling System ( 74 Residual Heat Removal System 82 Standby Diesel Cencrator System j 87 Upper llead* Injection System 90 Radiation Monitoring System f l t t i t s / I 1 ) RADWASTE SUFDtARY i October 1988 .j r 1. Total volume of solid waste shipped offsite: j A. Dry active wastet 1950 ft.3 Activity: 11.53168 curires B. Spent resins, sludges, bottoms: 1045 ft.3 Activaty 4.0739 curies October 4, 1988 ( Shipped: Barnwell, Inc. Octber 6, 1988 i October 12, 1988 [ 1 l October 18, 1988 i October 19, 1988 October 26, 1988 October 27, 1988 i 2. Radwaste onsite and awaiting shipments i A. Resin in storaget _147 ft.3 l B. Estimate resin that will be generated: 120 ft.3 + ) C. Dry active waste awaiting shipment: _835.5 ft.3 I a i ) l OffSITE DOSE CALCUI.ATION MANUA1._ CHANCES t No changes were made to the SQN Offsite Dose Calculation Manual (ODCM) in j October 19S8, i b ? t [ I i i i 4 a f I l l l i 4 ) +

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0 SEQUOYA!! NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE : NOVEMBER 07,1988 COMPLETED BY D.C.DUPREE l'ELEPl!ONE : (615)870-6722 MONTil: OCTOBER 1988 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MPs Not) DAY (MWe Not) 01 -12 17 -21 02 -11 18 -30 03 -13 19 -32 04 -11 20 -25 05 -10 21 -28 06 -14 22 -28 07 -16 23 -25 08 -23 24 -18 09 -30 25 -30 10 -30 26 -25 11 -23 27 -25 12 -28 28 -25 13 -28 29 -23 14 -25 30 -25 15 -23 31 -25 16 -28 ~ l UNIT SIRTTD0iJNS AND PO'.lER REDUCTIONS DOCKET NO. 50-327 f.' NIT NNIE Sequoyah One DATE noverher 7 19RR COMPLETED BY D. C. Dupree REPORT !!CNTl! OCTOBER 1988 TELEPIIONE (615) 870-6722 I I n E w o gg o y 'j Licensee g-s, go, Cause & Corrective c8c ygg Event gg o, g iction to No. Date c o y [pt y fgM Report # >U gu Prevent Recurrence 5~ $55 R 1 880101 F 745 F 4 Design Centrol, Configuratiot, Updating, and Employee Concerns, e D 8 A Ft Forced 2 3 8 Reason: tlethod:

• Exhibit C-Instructions 5: Scheduled A-E<guipment failure ' Explain) 1 -!!anua l f or Preparation of Data B-Itaintenance or Test 2-!!anual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-R<gulatory Restriction 4-Cont. of Existing (UtiREG-0161) E-Operator Training f. License Examination Outage F-A.!ministrative 5-Reduction C-Operational Error (Explain) 9-Other 5Exhibit I-Same Source !!-Other (Explain)

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k UNIT Sl!UIDOWS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT !Ml!E Sequoyah Two DATE NovemD.r 7 1988 COMPLETED BY D. C. Dupree REPO.!T !!ONTII October 1988 TELE EHONE (615) 870-6722 E ~ o cg oyg Licensee g s, g ^, Cause & Corrective rig gg ytg Event gg gg Action to No. Date o o y 3g g ggM Report # >. o gu Prevent Recurrence b~ $N5 R 13 680919 S 0 F 5 Reduced load for core life extension. 14 881021 F 0 B 5 Maintenance on No. I RCP DC Control Power Supply Circuitry. 11 \\ 2 3Hethod: 4 Exhibit C-Instructions 3F: Forced Reason: Scheduled A-Erzuipment Failure (Explain) 1-!!anua l for Preparation of Data' B-!!aintenance or Test 2-!!anual Scram. Entry Sheets' for Licensee - C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161) E-Operator Training & License Exaraination Outage F-A.!ministrative ' 5-Reduction G-Operational Error (Explain) 9-Other SExhibit I-Same Source 11-Other (Explain)

4 1' -4 -b OPERATING STATISTICS (TVA REPORTS) 4 h I i e

] Tva n42A (ONP-4-888 NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant 745 uo,,t h October 19 88 Period Hours item UNIT UNIT No. Unit No. ONE TWO PT. ANT 1 Average Hourly Gross Load. kW 0 721.732__ 721.732 2 Manmun. Hour Net Generation. MWh 0 716 716 3 Core Thermal Energy Gen, GWD (t}2 0 67.7150 4 Ste.im Gen Thermal Energy Gen., GWD (t)2 0 68.2092 67.7150 68.2092 8 5 Gross Electrical Gen., MWh 0 537,690__ 537,690 5 6 Station Use, MWh 16.659 29,332_ 45,991 E 7 Net Electrical Gen.. MWh -16,659 508,358 491,699 0 8 Station Use, Percent N/A 12,603 1 12,603 5.46 8.55 9 Accum. Core Avg. Exposure, MWD / Ton! 0 10 CTEG This Month,106 BTU 0 5,546,674 5,546.674 11 SGTEG This Month.106 BTU 0 5,587,154 5,587,154 I? 13 Hours neactor Was Criticai 0.0 745.0 745.0 14 Unit Use, Hours M n. 0:00 745:00 745:00 15 Capacity ractor, Percent 0.0 61.0 30.5 } 16 T,irbine avait. Factor, Perr ent 0.0 10.0 0 50.0 2 [ 17 Ggnstallor Avarl. I actor. Pe. cent 0.0 100.0 50.0 0 18. Turbnnan. Avaii Factor. Percent 0.0 100.0 50.0 100.0 50.0 19 Reactor AM Factor. Percent

0. 0_

100.0 2 PO Unit Ave. ractor. Percene 0.0 21 .Tuib.ne star tuns 0 0 -'50.0 s 0 22 r.le,ptor roid startuns o 0 0 9 3 24 Grou Heat Ra'e. stumWn yf3 [0,32_g_, 10,320 { ?S Net Heat Rate, ntu/kWh 2 26 Gross Heat Rate Etu/kWh(w/o oil). N/A 10.910 11.280 10.320 C- '7 Not Heat Rate Btu /kWhiv/o oil) 11.290 g ca Throttie Piessure, ou9 N/A 888.5 888.5 g 29 Tntottic Temperature. F N/A 532.4 532.4 ao 30 E n haust Pr essure, inHq Ain. N/A 2.1 2.1 31 intake Water Temo$,' r /A 67.1 67.1 4 32 33 Main F eedwater, M ib/nr N/A 9.2 9.2 j. Et (s __l'L 4 36 37 s un Power capacit y, c r Po 404.86 363.65 768.51 13 Accum. Cycle f ulf Power Day s. EFPD 0.0 328.1675 328.17 y 39 , ois r ued f or Generation, Ganons 1,320 E-40 _OdEntinq vaive. titu/ Gal 138,000 20 41 _Qsu.t.Grrer a tion. M Wh Ma n.11our Net Gen. MJa. Day Net Gen. l oad _MWh , Time Date M Wh Date F. t'r, % n 41 716 0800E 10-28-88! 16,976 10-29-88 92.18 3 H ema r k g. A F or HF NP this value is MWO/STU and for SONP and WHNP this vaiue is MWO/MT U. j 2(t) indicates T hermal f nergy.

• i i

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REACTOR HISTOGRAM SEQUOYAH UNIT ONE 100 90 - 80 - g ZW 70 - 1 E 60 - h$ 50 - 3: o 40 - o_ 30 - Q 20 - m* 10 - Unit In Mode #4, #3 4 i i i i I i i I i e I i e i 1 5 9 13 17 21 25 29 OCTOBER 1988

REACTOR HISTOGRAM SEQUOYAH UNIT TWO 100 90 - ~ 80 - Zw g 70 - 1 w a_ 60 - h 50 Eo 40 - o_ m 30 - o o 20 - 5 m 10 - 0 -10 i i i i i i i i i i i 1 5 9 13 17 21 25 29 OCTOBER 1988

UNIT L'O REACTOR HISTOGRAM ANALYSIS 1. Reactor @ 65 percent, holding for core life extension. 2. Load reduction for maintenance on #1 RCP DC voltage control supply circuitry. i i l l l t l l l l . L

..s _. 4 a m- ..~.s.~_, m____. m_ 2 ...m.

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.m..m._,_..mm._...._ --_mm.~mm._ 'g. 4 e J a I j' l 4 1 s I 4 4 .s SUSDIARY OF MAINTENANCE ACTIVITIES 1 I l (NPRDS MAINTENANCE ITEMS) I d d i 1 4 + r l l i I t I i i i l f I I I l l 4 i + l

(. _ _.. _..\\ e j e r. 4 E i 1 I I i 1, d d t l 1 4 a I i i - i 1 t } 1 l s 1 e l i l 1 I aj i P 1 l MAINTENANCE

SUMMARY

l (ELECTR IC.4L) i l l 4 t i c a t l I i E 6 t k t k l I I O ? P 9 ? I

ELECTRICAL MAINTENMCE r.CNTHLY SU::MRY CCnP P.R2.. U fi'HC SYS ADORE!!. DATE.... DESCRIiTICN... ............. CO ERE CTM ACTI LDI...................... I.124244 1 11Y ' 09'l K412 09/28/831-RLY-099-K612,En'POu3,$!PS Sl/AT Tl!E SP.qING INSIDE THE EEL AY L'iD GOTTEN RELAf K415 TrPIN B C0dG0L ill)G 665 AUX Olli Of THE SETTING SLOT. THE !? RING WAS INSTR Rd 1-R-51. PltoY 3: STICKING AND NOT AfLE 10 l'USN THE PELAY CPEN WIDE, WILL NOT DEEEERGIZE CDYLEIELY MRY CAUSIEC POINTS TO ARC HVER. REPLACED THE TIME RELAY IS CYCLE",. 7L50 VIIRATICH RELAY ^.HD ALSD REPLACED THE ADDER DECK. FROM HERRl;Y FEl.AYS IEIXG ACTUATED WILL (WR B124244). CMIE PARTIAL CONTACT 9.tEUP REPLACE THE SLAVE RELAY. CC3RIDINATE ALL WORK HITil INSTR MINT FAIUIEE EVALUATIDN SHOUID BE PLRFORMED 0130428 1 1GN 248 0113 10/03 /88 1-IGM-268-0113-A, EOP ED w, u P2 u3, REPLA CE LOW TEnPERATURE READING DH IGNITER OR REPAIR DETECTM Iu!TER CIRClf1T 7A ELEMENT DilE TO NORMAL UIAR MD CYCLIFS BREAKER 7 A233 EL 715 LCW TEP.P READING REPLACED IGNITER ELEMENT MD RAYCHEn 18 MON PER SI4)5.1 CCf2LEIION DLE CATE INSULATED SLEEVE. (WR i;130428). i 8-15 013C42911CN 268 011410/03/881-IGN-268-0114-A,ECU'Ecu nP2m3, REPLACE LOW TCPPERATURE READING ON IGNITER e OR REPAIR DETECTIVE IGNITER CIRCIIIT 7A ELEMENT MlE TO NGIMAL WEAR AND CYCLING. f REAKER 7 A264 EL 707 LCW TEMP READING REPLACED IGNITER ELEMEHi MD RAYCHEN 18 DON PR 31-303.1 CCFJLETION DUC DATE IN!!!LATTD SLEEVE. (WR !<130429). 8-15 l'2229701 *CN 268 0159 10/03 /88 1 -IGN-248-0159-A, esp 28, KXP RD n3, NO WNEN lREAKERS IN DISTRIESTION PMEL 1A CURRENT DN E.KR circuli 3A RWP E90! RED WEEE TURNED ON, liYORCGEN IGNITER 1159 DID HUT GET HOT DUE TO ACE MD CYCLIEG. RACKED I.REAKER 3A IN MD READ 4.1 Arfs. REPLACED llYDROGEN IGNITER 1159. IGNITER READING 14.0 Uhn!. (W8 !<222970). [.2?i!11 1 M HT. 082 ' 00013 09/23/081-GEkB-082-00018-A.ENWPRDn3,WHEN FOSSIltY, THE GOVERNDR ACit'AT3R PERFCRnING GCVERPCR POSITION STEP THE DIFFERENCE MMUNCI4T10N ALARM (PC1) Alf:RM FAILED TO CUf.E IN. INVESTICaiE RELAY CUNTACTS WERE ItPJ:ED CR PITTED AND REFAIR AS HECES!AR'I PREVENTING THE INITIATID:t 0F THE TIME DELAY RELAY. REPLACED THE COVERNCR ACTUA1:31 DIFFERENCE MNtmCIATION ALARM RELAY. (UR D2312'11). 0?d R44 2 CIND 092 0?00310/11/83 2 GENB 082-0002A-A,tuMPRD13, ADJUST THE LINEAR SYNCHRONIZING TRM551 TIER WAS GCVERNCR ACTL'ATOR POSITION SLARn (i MD CUT CF ADJU$inINT RESULTING IN EXCESSIVE GM GCVERNDR ACTUATCR P031TICH SENSINC) VOLTAGE DUTPUT ON COMPARATCR CARD. ADJJSTED THE LINEAR SYMCHRUNIZING TRM3nliTER TO C3 FAIN LESS Tl:AN FIVE VOLTS [TJTPUT Of TE! Cur #ARATCR CARD CLEAQIMC TI:E ALABl. (WR R2433dd). i;85135 2 t7ur 003 011tA 12/15/87 2-nVCP-003-011(A-A,CaSFFDu),iKE TDTOR POSSIItY, THE CA!KET WAS VORN CAUSING OPEPATC.'! C1 EPCW SU PLY CALVE TO NDAfW DIL TO LEAK THR0!!GH THE H0ll!ING. ALSD, PUNP 2A A HAS A DIL LLAK. THEFE 1443 A (REAKDCWN IN LU0RICATING CAPA:IIITY Of OP!RaiCR GUEASE C00 TO A MIXfuCE Of GREA!ES Of DITFIRENT CHEnICAL CASLS THE CCT.PlEINT CQllIMUED 10 FERf0BI If! CESICHED filNCTICH [ti WOULD L.C,fRICAL NAINTEMMCE MCNTHLY SUnMRY CCnP 'R2... U fi'M SYS ADDRE 3. DATE... 0*3CRIPTICM........................ CURRECTIVE ACTIDd............... HAYE f.EEN DECRADED HAD I!!E DITRATOR CREASE HDI IINK KEH REPLYED. DISCONTCTEL dAL'X ELECTRICALLY MD REPLACED CAIKET MD $EAL TET AND DPERaiCR CCEASE. RECONMECTED GALYE MD PERfDRED H310.1 [PERATER VALUE MALY!It. TEST. (WR B2V5185). 07491421 MA 248 1D 10/11/631-XfA-268-1B-B,ErHPRDNLWHILE EDRKIHC TPE FIRIWC CARD (A?S) MD THE CGNIRCL $I-305.1 EXCE!$IVE MOI!E A M VIITATI 3 CARD (AIP.) WLRE EAD POSSIKY DUE TO WA3 COMIHC FFDM 10 TRM3fDP!'ER f!R MORML GEAE OR (CE. REPLACED FIRIHC CARD PERRMENT HYP0 GEN MITICATICN SYS. A2B AND L2iR1L CPRD A18. ALSO REPLACED INVESTICATE MD PEPAIR PRattui. THE TRM!ISTE! IH file SOLID STATE CIRCUIT (i 0;l "B" PHASE. POERED UP TEM 3fDRMER MD RM FOR ONE MD OME HALT ~i HOURS. PERf0 PAD SI-305.1 FDR POST MINTDtANCE TEST. (WR B741162). k k 4 I I I e

2 +- -,. -- s 2 _,.A C_ c' e' I I l 6 L A + f J 5 r i 8 e MAINTENANCE SURu;Y (INSTRL' MENTATION ) I k 5 4 t f i ( f [ i 1 1 4 I s t f I l

n i T! $.WT MI.MTEM.itE MUNil'LY ICnP/,Wf I . CClP / 3 /d SYS M DFE!! DATE.... DESCRIP11DN....... ........ CD CE C TIVE ACTID 1..................... nR2., f:237;83 1 1C045 00J2 M/23/S$ 1 FDIC 043-(MM,NPfDALIHDICATER UN PDIC HAD [EEN "'?0 LIED" TO 92 POSIIJU:1. MM KETLE.'; I@ICaiOR TF10% POSITICH THE CLE !!C? PED.':CVING EVCi THCUGH ThE PU3ITIU?ER 'JHEEL CONTD!UF TO i:E RDTATIO. [2411731 JOIC 00 32 09/1d/681-PDIC-oe5-62,EnkPRDul.CO1 TROLLER u!LL IEMI-CON 0UCICR FAILURE DUE TO ME AND/CR NOT CUIPhi FULL SICKAL MEAT. PEHlF/ED "DIER H)ARD PCI:" P/M 1575Kd4702 FROH CONTROLLER IN PUWER STGRES AND PLACED IN CONilRLER IN FIELD. PErf0RRED CAlit'MTION AND PRT PER SUmILLANCE INSTRUCTION SI-108.18. (13!0H241173) 029 %52 1 LR C(8 033910/03/081 LR-048-0331,EnhPRDn],FCLD'D IlFUT RDOT CAUJE OF FAILURE UNKNNN. RESI$iCR 0:1 C1-24 USER TERM 1hALS 4 AND 5 IN!!ALLED EW RE!1STOR AND CRIftPED i CUT CF TCLER/.hCE. REPLACE !.S NEESSARY. TERllINAL LUCS REFERENCIHC M8AI-7. PERTilRMED PRT PER SI-94.11. (WR33299932) f:16993 1 11 043 0048$4d 09/24/881 LI 061 Cf 48844,CnNF7Dv],1HERE IS, CUT OF CALICRATICH LOW t.ND F.RROR IN KAD 2000 CfL DIffEEENCE i:EILEEN 1-LI-63-Y1 VALL'ES. BLED HIGH SIDE AND AND 1-LI-il-41. RECALIrARATED TRANSMITTER TO DESIRED TOLEMMCE. REitT.SIED 70 SE2YICE. i - (WR13749108) Ct39192 2 a.! 003 01:44 03/30/C3 2-LC'H)1-0164A-A,E8MPU5LihE VME ZERO SPRING CN POSITICRER WAS DRCPPED Sl&ED "MOTTLECf' ?OSITIDM WITH COUN DUE TO LHOSE LOCK FUT CN SHAff. SETFOIHT LO WRED TD ' 73 7/!I-2?d. THE CONTROLLER WAS ALSO OUT Cr TCLERANCE HICli. RDOT CAUSE Of FAILUli UNKMCWN. THE HCDITIER AND CCNiKILLER WERE i KECALIWATED TO D:! IRED TCLERANCE AhD PETL'RNED TO SERVICE. ( W B789292) 678 % 92 1 % 002 4121 10/0'J /33 1-PI-C 02-01 :1, E eNKD n J,1- ?I-2-12'1 13 PE%ED HIGH A 300 PSIC. THIS IS MfP l [HLif futS$1.TI. INVEif1 GATE MD PEFATR. l l l i n i i

r-

g I.'i ; nhI a's1%1EPME LtilI!i;.y i";ts.Ry CW TP7.. :) (G!r 37% AtD/E!!. (ATE.. L(tcglPTICN. CCEREC11UE ACTIGl....... Ch?37 1 '.i es) 017109/24/631-1.1-043-0179-G,Ex M9,sicCTE50.t 9s,4F2 CAU0E Of FAILU2E: D' RING MINTERANCE, i J . J4TECTED LA Y CI 2716 iP LPi%16 AIR 963 FOUND Il! THE TPAlS!!ITTER SEh!E F C.D C'li CT TELL? E "LRIFC LIHE. CI'..CTIt'E ACTIDI: THE FEriLWHCE EF P:t :W100 TReMinITTER WAS [:ACKTILLED AND RECAII:2ATED. POST MAINTEMNCE TEST TEDWiD f.ND TL' ANT'1IfTER RETUKHED TO SEWJ [C. \\ . r-

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SUMMARY

j (MECHANICAL) 4 4 1 t e i i l i t d - e i I 4 l I { 4 p I t i I l t f I i l i' i I I -I'- ,,n q

m; g I HECWVAL NAINTEWCE FEIT!1Y !"'.mRY f CCl3' i a M2... U fWC SYS AD:PE5!. C ATE.... OESCRIPIIDN. CODE CTIVE ACTIIIN...................... f.2152401 '.iY 047 05S?D F/21/C914'LY-057-050(F:-r,CWSD13, CHECK YALVE DIRIY INTEUAL! VALVE !!AT $UPIACE /AD FAILED 01-153.1 LO:AL LEAK FATE TEST. PLUG DISCOLORID 5 TIGHTLY.-REPLACE 0 REPATR A! HifLED. INTERHAL PARTS WTTH HG l' ARTS MD RETUDPID TO SERVICE. (!I218215240) ?221C3 0 704 070 0197 01/04/83 0-FCV 070-0197 4,CtP2x,rHPgn3,RIPAIR RUT UF MECHANICR t.DJUSfMENT.-ADJuttED VALVI; LEAKACE DETECTED PER KP 12W4; LIMIT AND M0VATED VALVE. AIR TESTED CC3 FLCW FAlf1CE VALVE AND ZERO LEAKAGE WAS IDNENTIFIED. (URt 022'L'73) 0230]S3 2 PCJ C01 0023 03/11/83 2 PCV 001-0023-A,Ca.VP20m),ULY ACTUATOR VALVE STEM, PISTON SEATIllG AMD SEl> LING YCEE I3 BINDDG TLCA!E REPA1R 33 $URFACE3 WERE SCRATCHED.-DISASSEMEtED HECES!ARY GPERATOR, CHECKED FOR BINDING, LIGHTLY GRudD ALL PDIHTS SiiOWING $IWS OF BINDIMC, REA!!EM*tED DPERATDR BUT 11 UAS STILL IST WORKINC PROPERLY. IN3fALLED NEW DIAlHRAGM. IMKING ITUPERLY RDW. (WR B2]0338 Sili.L NOT WORKING PRCPERLY. INSTALLED HEW DIAPHRAGN WURKING PRit'ERLY NDH. P/b139 2 U;V (03 0164A 10/30/37 2-LCV-c03-016A etiMPros3, win VALVE dip stem EAL HAD A lett IN IT, MD PACKING NOT REET STRCKE TIP.E PER 31-164 WAS HARD AND DRY.-IN$iALLED NEW STEM SEAL MD L'EPACKED VALVE. (WR4 B2J413i) 0237:741 "C' 001 002310/15/331-PCV 001-00?J-A,[xXPP0s), FAILED LACK CF STER LUIUCAi!CN.-LUBRICATEG 0I-344.d STRCKC TIP.E. IWESTIGATE AFD STEM, (0 JUSTED PACKING MD STRDKED REPAIR As NECETIAWY. VALVE. (llR) B237274) 02373781 iCJ 042 003510/03/331-FCV-062-0084-A,CitPF04),VRVE KILL CAD SDLENDID.-INSTALLD HEW AIR tiRCKE CPEN CK CUT W'iTH PLACED TO T!!E REGULATCR MD YALVE STILL WAS SL0V 10 Cl03ED POSITIG IT Il VERY ILCW TD CLCSE. I)(3TALLED FG 3CLENDID V3LVE. i SLO 3C. IWESTICATE A9 REFAllt (WRI 0237373) 0239773 3 4 1 001 0134 10/04 /03 1 -FCV-001-01 M, C@ @a, n P2 s], VM.VE FACKINC Full.CMER WAS LCUSE.-REPACKED THE PACKD; IS LEM!i'G. 7"P REGUIRED VALVE. M t B239773) i BN15'l 2."! 063 03:4 07/21/83 2 FCV-043-03M.CGGu),CRIGIFIL WR IOROM ACCUMLATICM.TN THE MAINDI5C DLET j i03i - REFL ACED 4/IV37 PERFCFJ11'S MD DISCAHRGE PC1T3 PRE 1KNTED THE VALVE 31-1(4.40 TME STECIL iltt WA! 12.14 FRC:1 STRO.':ING ADEQUniELY. AL10 THERE WAS 3ECCF ThI f.CCEPI.UCL C2ITERIA 13 ( 2 EVIOCNCE OF WEAR M 3LEEVE. DUE TO THE SECCFP. P31E: FPE;:IrJIIER PRE $!!KE 240 TEMPERATUPE OF Tit VALVE CDDY VAPING l l PSI. NF EECUIRED. DURING SHUTODWN.-REMOVED UALVE MD IHSTALLCD 1:EW VAL'/t. Mi P243151) l 1:01:07 1 P.V 042 0072 01/19/?% 1 ICV-044 0072-A.CiPDa.FRDs),(UCN HDRnAL UTC-REMOVG BCRCN AND IM3fRLED 1 i LErW AFCrkD OLVE 01En ADDITICAL RING Cf PACKING MD A FEU WIPER !!INC. M t 0251237) j (MD71 l M1 0192 01/30/C3 1-FCV C03-0192,C.f:4.4WFt13,RCP314 F02 KORMAL LE3R MD DIRTY. SEAIDG $U2 FACE I i i i i ^ t l i c-ls ,er,rw~ vrr y--- .,,--+en--.wew--,-- --,,.m -,_e ,__e.c---

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i i ) PEC,7l' AL NIMIENMCE RONil9.Y SunM/3Y CCM* f32.. U f?C SYS ACCRES$. DATE... DE!CRlPIICH.... .......... CO RRE CT7VE ACTI D't..................... LEAK Tiltu DID !!!!T rATCll WELL.-DISA!!EMBLED/REA31Mf3 LED VALVE TD CLEtJ! INTEENALS MD LaffED SEATINS SUPJACE. O.Rf F;2'i3537) B2 N 15 1 i(Y 062 009 09/23/031-FCV-062-0049-A.ErP25,#.P9Du], VIVE NORMAL WEAR-IR3ffLLED EEW DIAPHRAGM AND PACKIHC WA3 FUtND 10 FC LERING CCRIHC REPACKED VALVE. TIGHTEKD ITE COMTAINMEHi INSPECTION. NUT TG '!IGHT TENSION. (HRt 8244215) 0267c521 FCV 074 0028 10/07/83 1-FCV-074-0023, cup 2m,4FR D'41VKVE VALVE DISK WAS DUT OF ALIGdMENT.-TRIED WCJED IFCDRKECTLY. TO CORRECT PROBLEM BY RUTATING 90 DEGKEE! Fui ITROKE WA3 STILL VERY i CRRATIC. VN.VE WAS REPLACED WITH A VALVE FROM IMITS BAR CM WORK PLAN 00 794601. (WRt l<247052) 12712J1 1 '.'lV 062 0915 *,0/13/831 VLV-062-0915,[WRDs],THIS WR If0Rftil WEAR. Felt!ILT THE VALVE. REPLACES LO!i W D271301. !USPECT INSTALLED NEW DI6PERAGM AND 0-RINGS. VALVE LEAK 3 THRO:Gd WHEN 3 HUT. (WR4 !<271301) INVESTIGATE t.ND REPAIR As hECE!!rWY F271502 i f CV 043 0174 09/21/831-FCV-043 0174,EtNPRDu1CLLAN !4 ROM OFF HORMAL WEAR.-CLE/JfED CDRON OFF CT VAttt VALVE. REPAIR PACKING LEAK. MD KEPACKED UnLtT. (WR4 B271502) B2755741 T'.'u 042 007010/05/031 FCV-042-0070-A,E=NPRDw1ValtT IFERATOR PAD CItMRAGM AND TO HIGH OF AIR LE/. KING AIR. !!GHTEN/PIPLACE THE PRE!$URE.-INSTALLED NEW DIAPHRAGM AND OPERATCR DItMA&M ADJUSTED AIR HE33URE TD UAltt. (WR0 0275b?d)D P2752921 '.'N 403 143 OV27/831-LCV-003-143,[3P2n,hMPRDn3,THE VKtt FAD DIAPER M M. INSTALLED HEW DIAPHRA&M DIfnRM PAS A LEM. MD RETURNED VAlti TO SERVICE. (WRt B274292) CEPCRIED AGAINST 1-tr'UP-003-01h3 P.. 127 070 1 "1 CC1 01% <*/21/331-FCV-003-01%,Cr?DJ,1-F(V-3-1% LEAK 3 fl8200GH P27 H01 1 3 0 !d2 H33 01/14/831-FCU-062-0083,EERDd,vP2s114CV 62-8 STR0rt >57 IET FEDPERLY.-INSTALLED HEW 3 LEMS THiu. REPLACE CR REPAIR TD STCP GA!IETS ED FEAT RING. (WRI P274601) A LEA ACE. REP REDU1HD A PREVENTILT PEASURE, !?71:24 1 ?it' 263 ?!1410/13/031 VLV-Ol6-):14-3 CeNfmLVALtt (ENNET H3FML WEAR. DIRTY AFD CORROSIOh CCFCH FLtW3C AND PACKING MEA! 3H0VED SIGHS CT ERY3TAL3 BUILT IP. REMUVED 1.TL LEAKliGE (10PM CRYliALS). FEED TD COUPLICG ON VALVE LEAK OtT. REMOVED REPAIR DURING RCS OUTME. ALSO, IENNET iONNtf MD GATE, CLEMED f>LL paris, siUD3 ME LIWILI CCRTCCFD-IPOULD CLEAM CLEMED STUO3 AND LUIRICATED, AHt> LULRICATE At HUtsitif., VAltC HA3 FCINSTILLED 10HMri AMD TOEQUED. LILCED MI:RCR IH!ULAtti.H 0:t Ii-WILL FEED TO [E C0lPLING DA VALVE LIAK OFF A.kD RE REr0VED. WR 13 R?;ti L'r M 11 % 0-363 UALVE (50 LUIRICATED ifEM. (WI B2792td) W0LKDGW. e c

s HCC:.:1.' AL DIHIEF6 E r.UUhlY ft' RAW .Cfv a72., U M.C !?! A;02ES: 03TE. DESCR?PTICM. CURRECTIVE ACTION.... 0295379 1 S2 (W 10/13/031-VLV-N2-0915.EWr20*3, ll!PEC! URVE FORML UEAR.-PEEUILT VALVE BY FEPLACING LEAKS THROUCH UEri Shul. DirFH;AGM AND PACKING 0-RING. (uti B29437'D 1:29E151 1 K': H2 0484 0/20/031-VLV-042-0!!4-i,CC2CFEx,*MPRDs,rP2m3,V LE AKING IMMET GASKET.-IH!fALLED FEW ALVE IS LEAKIXG EDNMET CASKET, RLit1MED TO SERVICE (WRI 0293151) I.733401 1 T'.~J 061 0164 (9/20/831-FCV-Od3-0164,CMPRD13,URVE Ff(KING PACKIMG 1130 EEEN ADJUSTED UMTIL THERE LEt.K WS$ HO MORE ADJUSTMENT.-ADJUITED PACKING DUT DID Nui siDP LEAK, PACKING EDITDNED DUT. REPKKED VAVLE. (WRI B753651) 0763936 1 iCU 03) 0037 09/22/831-fCV-030-0037,EE:?9Dm3, VALVE FAILED CLD:ED STCP EDI PRUPERLY SET ARD $1-153.1 INTEk.vilS DIRIY.-CLEANIED AND Lut[0 VALUE SEAT. REnliEMBLED BACKED DUT CLD3[0 STOP BULT 10 ALLCW YALVE 10 ftLLY Ct01E. (EN P743' lid). B149795 1 U; 062 C073 10/06/03 1-Z!-062-0073-A,EmXPR:n],VlV It LIMIT SWITCH DUT OF add 37 MENT.-ADJU3 FED IF)ICATING IN illf TH20 file PO!!!IrH RED (IMIT ~,.:liCHES TO CSTAIN PKCPER LIGHT AFD GREEN LI2TS LUIEH VLV 13 TULL C?EN. IXDICATIQWS. VALVE STILL STAYS CPEW. COMCTED PRCFLEM AGIANST 1-MUDP-462-0073 A. (L23 B749795) 277:453 I 'M 047 053 D 10/15/891 '/'#047-0532C-8,EnWPf0m], RELIEF tty >0ffAL WEAR.-REn0VED VALVE AMD TCCC TD 67 *07D H33 ft!ND FLANsE TH4i It $HCP TO TEST. CLEAFED PCL13, REINSTr>LLED LE6 KING. REPAIR AS HEICID. VALVE AND FLAXCE WITH NEW CAIKET. (kRI B772454) IM29 1 0 <03 01719 09/29/831-LCV 503-01710,E*MFP053, AIR LE/ KING XORf.AL t' EAR-IN3f ALLED A NEW $ TEM SEAL APOUFD VLV STIM. REPAlk 02 EiPLfCE. AND APPLIED LUCTITE. (WRI 0789521) s ) t MECHANICAL MAINTENANCE MONTHLY REPORT FOR OCTOBER 1988 U_ NIT 1 1. Completed several WRs on heater sightglasses. 2. Completed repair on 1-FCV-3-136A. 3. Completed repair on 1-LCV-3-174. 4. Completed repair on 1-VLV-67-705B. 5. Completed repair on hot sample room chiller. 6. Completed repair on containment spray pump 1A. 7. Completed repair on UHI valve 1-FCV-87-21. 8. Completed workplan on terry turbine room exhaust fan. 9. Installed new valve at 1-VLV-63-612. 10. Test for "Door Play" on upper and lower airlock doors. 11. Completed repair on 1-FCV-72-39. 12. Comple?cd inspection on D/G 1B-B. 13. Replaced radiation monitor pump on 1-RM-90-126. 14. Completed several WRs on blind flanges. UNIT 2 1. Replaced valves on Amertap System 2-VLV-27-733, -736, & -737, 2. Test for "Door Play" on upper and lower airlock doors. 3. Completed inspection on D/c, 2A-A. UNIT 0 1. Completed repair on waste package cranc. 4 OTHER.S 1. Continued closure of various CAQPa, CARS, DRs, etc. a 4 9 e - ~

g _f ,a J"' [ s . e f i t i i 1 4 1 i 1 l i a t MAINTENANCE SUmtARY (MODIFICATIONS'. i t i t t 1 i i i i f i 4 1 1 ) f 9 1 4 ii d 1 x .N I 1 ) P e i J .)

f ) e i i e SUMMA 3Y OF KOHX COMPLETED HODIFICATIONS - CURRE?T STATUS OCTOBER 1988 9 4 a l

e y Major Capital Projects: PN7102: ECN 5938 - Replaco Feodwater Hentors 3 and 4 No kork in progress at this time. PN7105: ECN 5009 - Essential Raw Cooling Water (ERCW) Piping Changoout_From Carbon Steel to Stainless Stool No additional pipo replacement is scheduled in the near future. PN7108: ECN 6720 - Cranc Consistency Program Unit 1 polar crane limit switch weights remain to be painted. Unit 1 cycle 4 (U1CA) is schedulo for completion. Unit 2 polar crane post modification testing by Electrical Maintenance is completo; however, Electrical Maintenance noods a copy of the vendor's manual. Auxiliary Building crano (WP 12569) which hr.s completed the review cycle will be hold for window between unit 2 cyclo 3 (U2C3) and UIC4. Turbino Building 200-ton crano (unit 1/6720-04) workplan approved but not implomonted. Unit 2/6720-03 is Modifications complete, hold for postmodification (PMT) by System Engineering. Turbino Building 15-ton crano WPs (Unit 1/6720-06, Unit 2/6720-05) completo and ready for PMT by System Engineering. Servico Building 5-ton crano WP (6702-02) has been approved and scheduled for implementation the wock of November 14, 1988. PN7122: DCR 1373_- Secondary Sido No work in progress at this time. PN7130: ECU 6180 - Post Accident Monitoring This work is now scheduled by UIC4 and unit 2 by U2CA. PN1132: DCN 0026 - Sewago Treatment Facility and Civil Upgrade Work is 95 porcent complete. holding for Soddy Daisy to completv their lift station and then our tie-ins can be comptated. e -

e e Maior Capital Projects (cont.): PN7136, -ECN 6259 - MSR Tube Bundle Replacement ECN is complete except for PMT and inservice leak test on unit 1. Leak checks will be performed during system heatup. Unit 2 leak checks are complete. PN7161: ECN 5855 - Replacement of Doors A56 and A57 WP 09679 remains on hold and is partially complete. l PN7181: DCR 1898 - ECNs 6832 at:3 +596 - Dry Active Waste (DAW)_ Building l Electrical interface work is complete. Workplan j closure hold for Instrument Maintenance (WP 12478), checks and updato of SOIs by operations, and l Operations (WP 12417) pending a revision for packing I dry active wastoi Waute Management is considering i removal of equipment installed und0r WP 12477. Significant Items: PN7199: Fisenllaneous Activities Under $100.000 This was for various work orders prepared for work under $100,000 total sito cost. This work was done as

aanpower resources were available.

l l

\\ i Other Items: ECN 5111 - Provido Permanent Power to Manholco 42-46 Work stopped for lack of funding. ECU 5503 - Evacuation Alarms O&PS/Firo Do'.cction O&PS WP 12482 - Work stopped for lack of funding. ECN 5552 - Condensato Demineralizer Modifications and High Crud Filter Upgrade to higher range instrumentation for condensato domineralizor system neutralization and nonreclaimable warto pumps. WP 5552 Fieldwork is complete. ECN 5609 - Alteration to the Makeup Water Treatment Plant WP 12387 (evacuation alarm / fire detection valve 26-290) is 90 porcent completo and has been held due to other priorities. WP 12576 - Work is approximately 75 percent completo and is on hold for Electrical Maintenanco to perform breaker tests. Need resolution of it.ctrument tab description from NE. WP 12633 - Work is approximately 80 percent complete. Hold for instrument tab (4 7B601-928) sotpoint revisions. WP 12731 - WP is approximately 80 percent completo. Hold for instrument tab (4 7B601-928) sotpoints. Need connection diagram revisions from NE. WP 12684 - WP is approximately 80 percent complete. Hold for instrument tab (47B601-928) sotpoints. Neod connection diagram ravision from NE. WP 12665 - WP is on hold for outogo and is 95 percent completo. WP 12682 - WP is on hold for outago and is 80 porcent completo. ECN 5626 - Containment Ladders, Unit 1 Hodifications needs additional design information to ec-.pleto. NE needs to incuo all drawings licted on this ECN. Work has not bor,un because of this holdup. t e g 6 Other Items (cont.): ECN $841 - Hot Shop Firo Protection / Evacuation Alarm WP 12360 is closed. Need drawing deviation completed. WP 12637 - All fieldwork for ovacuation alarm is complete. Awaiting Work Roquest (WR) B240406 to be worked to restart fans to do functional test on fire protection. ECN 5911 - Wasto Disposal Piping Addition Work is in progress. l ECN 5935 - Correct Power B.'ock Lighting Deficiencies l WP 12437 is completo and in final review. WP 12275 is in work for FCR 7706 to add approximately 40 more lights. WP 5935-01 is field completo. ECM 5977 - Instal) Steam Generator Blowdown Domineralizer Work is in progress on WPS 5917-01. -02. -03, and -04. ECN 6116 - Pressurizer Hangers an6 Valves Unit 1 is complete. Remaining unit 2 work is scheduled for U2C3 refueling outago. ECN 6357 - Essential Raw Cooling Kater (ERCW) Roof Access and Rails for Securit/ Equipment Original desl n for WP 12238 was rejected by Operations. UE to rework 3 design to comply with Operations' needs and attempt to salvago 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 Exchangor B Replacement Plato head exchanger and framo is comploto. Hangers and pipo, which can be installed prior to outago, is in work. WP to remove old heat exchanger is in review cyclo. NE procuring the remaining needed piping material. Estimated completion dato for nonoutago work is during the month of December 1988. ECN 6455 - Upgrado CU-3 Box Dattery Packs WP 12295 is field complete.

0 \\ f o i Other Items (cont.): ECN 6543 - Install Public 9tfoty Acce:s Portals and Modify Entranco Road Work is being hold pending the release of drawings from NE. ECN 6596 - Dry Active Waste Piping Interface WP 12612 - Completo, ECU 6601 - Removal of Unit 1 Emergency Gas Treatment System (EGTS) Backdraft Dampers Completo. ECN 6689 - Rolocation of Main Steam Power Operated Relief Valvos (PORV) WP 12172 - All work is completo for unit 2. Work is cotuplete on unit 1. PMT 90 and SI 166.6 are completo. ECU 6706 14 Support Enhancement / Lost Calculations 1 [ Completo for units 1 ated 2 restart. Postrestart work is in progress. ECN 6739 - Alternato Analysis Complete for units 1 and 2 restart. f ECN 6761 - East Valve Room (EVR) blowout Panols Unit I work is completo. Unit 2 work is complete. ECN 6784 - Documentation to Show Pipo Class Dreaks Final closure is awaiting a etv8-lan to the plant modification proecoure for doloting requircaents to mark 1hif t supervisor drawings. ECH 6815 - 500-kV Switchyard Addit / All work is complete in the 100-kV sw.i ..) except for grounding of the northwest corner of fonco, some gravoi placement and testing of l PCB $018. Clocuro of WP 6815-05 will be delayud becaudu of problems i with the data loggor that prevent sof tware cht.gos. A decision has I been mado to retiro the 161-kV equipment in the bay 20 by leaving it in place. This decision will requiro revision of design drawingc by means of an FCR.

r 4 4 O 9ther Items (cont.): DCN X00006A - Removo Hydrogen Analyzero Tubing Complete. DCU 200018B - Install Ucedle Valvo for ;iydrogen Analyzors Complete. DCN TO - Hydrogen Analyzor Check Valves Complete. Instrumentation Verification Program For u. it 2, there have been 953 discrenancies issued to MODS to date 4 with 476 not required for restart. All discrepancies required for restart have been completed; 69 noncestart discrepancies are open. For unit 1, thoro have been 532 discrepancies issued to MODS to date with 1.3 not required for restatt. The 314 required for restart are compictc. pCN 204 - Modify steam Dump Headce Supports (Unit 1) Complete.

• N 214 - APW Tap Rotation

'omplete, systems engincor to test. DCN 198 - Ice Condensato Expansion Bellows Complete. DCNs 229 and 231 - Hy Analyzer Modification Completo. DCN 300 - ERCW Modificatien for nicrobiologically Induced Corrosion (MIC) Unit ' "* is complete on A and 11 Trains. 7 0 \\ e s THIS PAGE INTENTIONALLY LEFT BLASK f i I l a

i v e TENNESSEE VALLEY AUTHORITY Sequoyah Nuc1Sar Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 November 14, 1988 e huclear Regulatory Comission Office of Management Information and Program Control Washington, DC 20555 centlemen: Enclosed is the October 1988 Monthly Operating Report to NRC for Sequoyah Nuclear Plant. Very truly yours. TENNESSEE VALLEY AUTHORITY I'. It Plant Manager Enclosure cc (Enclosure): Director, Region II INPO Records Center Nue". ear Regulatory Comission Suite 1500 Office of Inspection and Enforcement 1100 Circle 15 Parkway Suite 3100 Atlanta, Georgia 30339 (1 copy) 101 Marietta Street Atlanta, Georgia 30323 (1 copy) Mr. K. M. Jenison Resident WRC Inspector Deputy Executive DLeector 04PS-2, Sequoyah Nuclear Plant for Regional Operations Nuclear Regulatory Comission Washington, DC 20555 (1 copy) J. C. Partlow, Director TVA Protects DLvision Office of Special Products Washington, DC 20555 (1 copy) Mr. T. Marriton Electric Power Research Institute P. O. Box 10412 / Palo Alto, California 94304 (1 copy) / [ / \\ (: An Eque Opportumty Employer .}}