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| | document report number = LER-82-070-01T, NUDOCS 8207090257 | | | document report number = LER-82-070-01T, NUDOCS 8207090257 |
| | package number = ML20042C744 | | | package number = ML20042C744 |
| | document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT | | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns 05000327/LER-1993-0211993-08-18018 August 1993 LER 93-021-00:on 930720,discovered That Boron Analysis of Refueling Canal Not Performed,As Required by TS 3.9.1 Due to Miscommunication.Lco 3.9.1 Entered.Chemistry Surveillance Instruction Will Be revised.W/930818 Ltr 05000327/LER-1993-0201993-08-17017 August 1993 LER 93-020-00:on 930719,Train B of Auxiliary Bldg Gas Treatment Sys Manually Initiated as Result of Fire in General Supply Fan Room.Sg Wet Layup Recirculation Pump Bearing & Motor replaced.W/930817 Ltr 05000327/LER-1993-0191993-08-11011 August 1993 LER 93-019-00:on 930713,containment Isolation Occurred Due to Inaccurate Drawing Used to Develop Clearance Boundary. Returned Valves to Normal Positions & Restored Sys Air pressure.W/930811 Ltr 05000327/LER-1983-122, Updated LER 83-122/03X-1:on 830927 & 28,diesel Generator 2A-A Declared Inoperable Due to Failure to Maintain Load of 4,400 Kw During Surveillance Testing.Caused by Faulty Exciter1983-11-0101 November 1983 Updated LER 83-122/03X-1:on 830927 & 28,diesel Generator 2A-A Declared Inoperable Due to Failure to Maintain Load of 4,400 Kw During Surveillance Testing.Caused by Faulty Exciter 05000327/LER-1982-126, Revised LER 82-126/01T-1:on 821105,check Valve Downstream of MSIV Failed.Caused by Valve Disc Separating from Stem & Lodging Downstream in Steam Dump Header.Disc Retrieved & Replaced1983-03-30030 March 1983 Revised LER 82-126/01T-1:on 821105,check Valve Downstream of MSIV Failed.Caused by Valve Disc Separating from Stem & Lodging Downstream in Steam Dump Header.Disc Retrieved & Replaced 05000327/LER-1982-0701982-07-0101 July 1982 LER 82-070/01T-0:on 820618,discovered Possible Inoperability of Containment Sump Level Instrument Loops in Event of Loca.Possibly Caused by Increased Temps Rupturing Sensor Bellows.Procedures Revised 1998-07-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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LER-2082-070, |
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LICENSEE EVENT REPORT (hAAlt . .I' p.
2 .
COfJTROL DLOCK: ) l l l l l l 6 (PLE ASE PRINT On TYPE ALL REQUIRED INFORMATION)
JPlo l1l8 9lT lNLICENSEE lS lNCODE !P'!1 I4!h__0 15 l O ! -l 0LIGEN5E l 0 l NUUSEH 0 l 0 l 0 l- l0 l025 l@! 26 4 LICENSE l 1 l 1TYPE l 1JOl 1 l@[ l l Q, 5 7 C a t go, I CON'T * *
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EVENT OATE 74 76
' REPORT DATE 30
' EVENT DESCRIPTION AND PD00ABLE CONSEQUENCES h IT'lT} l With units 1 & 2 in mode l'(100% power. 578 decrees F. 2235 nsid at 1425 CST on
[ 0131 l 06/18/82, the containment sump level instrument loops have the possibility of beint Io l4 l l inoperable in the event of a LOCA due to 1 icreased temperatures run'turine ti sense a..
lo Is] l bellows. This event is reportable under section 6.9.1.12.1 of the technical l o is I l~speci ficatiotis. There 'was no ef fect upon public heal th and safetv . Previous
..y. . . , .
~
l 0 l 7] l ~ occurrences - none. .
Io ia l l SYSTEM CAUSE_ C AUS E CODE COMP. VatyE CODE' SUSCODE COM'ONE N T CODE SUSCOOE SUSCOOE loI9l 2 3 lS lF lh Wh l A lh l1l Nl S { T IR lU lh Wh h h 9 to 13 12 13 .
18 19 20
'f 0UENTI AL OCCunnENCE ' REPORT R E VISION LER EVENT YE AR RE Pon T No. IODE TYPE NO.
@ ,ag/AO ar 1812I
~
,_ 21, 22 l_J 2J l 01 71 01 24 26 l/l 27 10 l t i ITI l-l 10I 28 29 33 3 32 ET A T r O rLaNT T U HOURS 5 8 lit o F Of 41 UB. SUPPL 1 MAN FACTUI.
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36 31 40 41 l42N l@ lL l@. lB l0l8 43 44 CAUSE DESCRIPTION AND CORGECTIVE ACTIONS h .
li lo l l It was determined, during evaluations made of the level transmitters, that the i l sealed water filled capillary could possibly. fl6sh to steam in the event of a LOCA .
t?..
4 l T'M I nd rupture the sensor bellows. This would cause a loss of automatic switchover sa..
3g , g 3 g [ from the RWST suction to containment sump suctlon for ECCS~ equi'pment. It could 'als-
?.ig.~ .
/[gl provide erroneous indication to the control room operators. Measures have been tak
. .-s. .s g to 17p~lement a manual switchover tollowing a LUGA.
~ ge - r At.tLI1Y 'y MEfleOO OF
- j. S T All t's "L POvvER OT84E n status DISCOvt n Y DISCOVEnv DESCRIPTION 32 lii$i L Ej@ l 1l 0 l 0 l@l NA l l C l@l Equipment evaluation e A TivlTV' CO TENT RELEASED Or nELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
' a 1t.yI, ,
- a 9 LzJ @ 10LzJOI 19 NA 44 l l 45 NA 4g. pen 50NNEL EXPO 5uREs
.'* NUMBER TYPE DESCRIPTf 0N
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\ 7, . 8 9 1010 LOJ@l z l@l 11 12 13 NA gj.., PE RSONNE L INJUnlES NOV8tR DESCRtPTION li 181 a o10101 o l@li2 si NA LOS$ OF OR D AM AGE TO FACillTY TYPE DESCRIPTION Il2 198I 9LzJ@lto NA essuf otsCRiPfiONO ""U 8207090257 820701 '
b7 8 9 hl 10 n (DRADOCK 05000327 PDR l
sa og lJlIIfIII1l N'ame of FrenRro,- 11. R. Rogers /M. R. Harding Phone (615) 751-0349 y -@
Sequoyah Nuclear Plant 1
e e
e LER SUPPLEMENTAL INFORMATION SQRO-50-327/82070 Technical Specification Involved: 3.3.2.1 6 3.3.3.7 Reported Under Technical Specification: 6.9.1.12.1 Date of Occurrence: 06/18/82 Time of Occurrence: 1425 CST Identification and Description of Occurrence:
Units 1 and 2 containment sump level transmitters LT-63-176, 177, 178 and 179 could have been inoperable in the event of a LOCA causing a loss of automatic switchover from the RWST to the containment sump. The sump level is also identified as accident monitoring instrumentation which under the postulated accident conditions could have been inoperable.
Conditions Prior to Occurrenc.c:
Units 1 and 2 in mode 1 at 100% reactor trip power.
Apparent Cause of Occurrence:
During evaluations made of the level transmitters, it was determined that the sealed water-filled capillary could possibly flash to steam in the event of increased temperatures during a LOCA. The rapid increase of temperature / pressure in the reference leg could possibly rupture the sensor bellows resulting in a failure of the transmitter.
Analysis of Occurrence:
A ruptured bellows would cause the fill fluid (water) to be forced out of the sence line due tc steam pressure at the top of the sense line. As a result, the sump level transmitter would see a dif ferential pressure of 0 psid. Since the transmitters are calibrated to indicate approximately 18 feet level in the sump, with 0 differential pressure across the transmitter, the channel indication could lead to inappropriate operator action. Also, if these events occurred, there would be a loss of the capability to automatically switchover from the RWST suction to containment sump suction for ECCS equipment following a LOCA.
Corrective Action:
The containment sump level transmitter bistables have been placed in the bypassed (test) condition. This removes the capability of automatic switchover and requires a manual switchover by operators. Applicable procedures have been revised to reflect this required operator action and appropriate Operations personnel informed of this change. Temporary technical specification revisions to LCOs 3.3.2.1 and 3.3.3.7 have also been made to delete the requirement for automatic switchover.
Plans are being made to refill the scaled legs with a silicone oil to prevent flashing at elevated temperatures during a LOCA. After completion, the capability of automatic switchover will be reinstated. This work is scheduled to be completed by July 18, 1982.
Failure Data:
None.
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05000328/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | 05000327/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | 05000328/LER-1982-015, Forwards LER 82-015/03L-0 | Forwards LER 82-015/03L-0 | | 05000328/LER-1982-030, Forwards LER 82-030/03L-0 | Forwards LER 82-030/03L-0 | | 05000328/LER-1982-031, Forwards LER 82-031/03L-0 | Forwards LER 82-031/03L-0 | | 05000327/LER-1982-033, Forwards LER 82-033/03L-0 | Forwards LER 82-033/03L-0 | | 05000327/LER-1982-034, Forwards LER 82-034/03L-0 | Forwards LER 82-034/03L-0 | | 05000327/LER-1982-035, Forwards LER 82-035/03L-0 | Forwards LER 82-035/03L-0 | | 05000327/LER-1982-036, Forwards LER 82-036/03L-0 | Forwards LER 82-036/03L-0 | | 05000328/LER-1982-038, Forwards LER 82-038/03L-0 | Forwards LER 82-038/03L-0 | | 05000327/LER-1982-040, Forwards LER 82-040/03L-0 | Forwards LER 82-040/03L-0 | | 05000327/LER-1982-041, Forwards LER 82-041/03L-0 | Forwards LER 82-041/03L-0 | | 05000328/LER-1982-052, Forwards LER 82-052/03L-0 | Forwards LER 82-052/03L-0 | | 05000327/LER-1982-054, Forwards LER 82-054/03L-0 | Forwards LER 82-054/03L-0 | | 05000327/LER-1982-055, Forwards LER 82-055/03L-0 | Forwards LER 82-055/03L-0 | | 05000327/LER-1982-056, Forwards LER 82-056/03L-0 | Forwards LER 82-056/03L-0 | | 05000328/LER-1982-057, Forwards LER 82-057/03L-0 | Forwards LER 82-057/03L-0 | | 05000328/LER-1982-058, Forwards LER 82-058/03L-0 | Forwards LER 82-058/03L-0 | | 05000327/LER-1982-059, Forwards LER 82-059/03L-0 | Forwards LER 82-059/03L-0 | | 05000328/LER-1982-060, Forwards LER 82-060/03L-0 | Forwards LER 82-060/03L-0 | | 05000328/LER-1982-061, Forwards LER 82-061/03L-0 | Forwards LER 82-061/03L-0 | | 05000328/LER-1982-062, Forwards LER 82-062/03L-0 | Forwards LER 82-062/03L-0 | | 05000328/LER-1982-063, Forwards LER 82-063/03L-0 | Forwards LER 82-063/03L-0 | | 05000328/LER-1982-064, Forwards LER 82-064/03L-0 | Forwards LER 82-064/03L-0 | | 05000327/LER-1982-065, Forwards LER 82-065/03L-0 | Forwards LER 82-065/03L-0 | | 05000327/LER-1982-066, Forwards LER 82-066/03L-0 | Forwards LER 82-066/03L-0 | | 05000327/LER-1982-067, Forwards LER 82-067/03L-0 | Forwards LER 82-067/03L-0 | | 05000327/LER-1982-068, Forwards LER 82-068/03L-0 | Forwards LER 82-068/03L-0 | | 05000328/LER-1982-069, Forwards LER 82-069/03L-0 | Forwards LER 82-069/03L-0 | | 05000327/LER-1982-070 | LER 82-070/01T-0:on 820618,discovered Possible Inoperability of Containment Sump Level Instrument Loops in Event of Loca.Possibly Caused by Increased Temps Rupturing Sensor Bellows.Procedures Revised | | 05000327/LER-1982-071, Forwards LER 82-071/03L-0 | Forwards LER 82-071/03L-0 | | 05000327/LER-1982-072, Forwards LER 82-072/03L-0 | Forwards LER 82-072/03L-0 | | 05000328/LER-1982-073, Forwards LER 82-073/03L-0 | Forwards LER 82-073/03L-0 | | 05000327/LER-1982-074, Forwards LER 82-074/03L-0 | Forwards LER 82-074/03L-0 | | 05000327/LER-1982-075, Forwards LER 82-075/03L-0 | Forwards LER 82-075/03L-0 | | 05000327/LER-1982-076, Forwards LER 82-076/03L-0 | Forwards LER 82-076/03L-0 | | 05000328/LER-1982-077, Forwards LER 82-077/03L-0 | Forwards LER 82-077/03L-0 | | 05000327/LER-1982-078, Forwards LER 82-078/03L-0 | Forwards LER 82-078/03L-0 | | 05000327/LER-1982-079, Forwards LER 82-079/03L-0 | Forwards LER 82-079/03L-0 | | 05000327/LER-1982-080, Forwards LER 82-080/01T-0 | Forwards LER 82-080/01T-0 | | 05000328/LER-1982-081, Forwards LER 82-081/03L-0 | Forwards LER 82-081/03L-0 | | 05000327/LER-1982-082, Forwards LER 82-082/03L-0 | Forwards LER 82-082/03L-0 | | 05000328/LER-1982-083, Forwards LER 82-083/03L-0 | Forwards LER 82-083/03L-0 | | 05000328/LER-1982-084, Forwards LER 82-084/03L-0 | Forwards LER 82-084/03L-0 | | 05000328/LER-1982-085, Forwards LER 82-085/03L-0 | Forwards LER 82-085/03L-0 | | 05000327/LER-1982-086, Forwards LER 82-086/03L-0 | Forwards LER 82-086/03L-0 | | 05000328/LER-1982-087, Forwards LER 82-087/03L-0 | Forwards LER 82-087/03L-0 | | 05000327/LER-1982-088, Forwards LER 82-088/03L-0 | Forwards LER 82-088/03L-0 | | 05000327/LER-1982-089, Forwards LER 82-089/03L-0 | Forwards LER 82-089/03L-0 | | 05000328/LER-1982-090, Forwards LER 82-090/03L-0 | Forwards LER 82-090/03L-0 | |
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