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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML18039A2371998-01-0707 January 1998 BFN Unit 2,Cycle 9 NIS-1 Owners Rept for Isi. ML18038B8971997-05-13013 May 1997 ASME Section XI ISI Summary Rept for BFN Unit 3 Cycle 7 Refueling Outage 970222-0313. ML18038B7291996-05-29029 May 1996 BFN Unit 2 Cycle 8 ISI NIS-1 Rept. ML18038B6291996-02-23023 February 1996 Bfnp Unit 3 ASME Section XI Owner'S Rept for Repairs & Replacements, Vols 1-4 ML18038B6281995-11-25025 November 1995 Bfnp Unit 3 ISI NIS-1 Rept 841128-951125. ML18038B1261995-01-12012 January 1995 Cycle 7 ISI NIS-1 Rept. ML20056F7651993-06-0303 June 1993 Cycle 6 Refueling Outage Owners Rept for Isi ML18036A3281991-08-20020 August 1991 Vols 1-5 of Browns Ferry Nuclear Plant Unit 2,Cycle 5 ISI Summary Rept.W/Nine Oversize Drawings ML19323F3181980-05-15015 May 1980 Add Revised Pages for Facility Inservice Insp Program, Incorporating Addl Pipe Weld Insp to Provide Protection Against Pipe Whip ML19290C9601980-02-11011 February 1980 Inservice Insp Rept for 790822-0921 & 1011-1031,one-third of First Interval.Describes Ultrasonic,Liquid Penetrant, Magnetic Particle & Visual Examination in Specific Welds & Bolts 1999-08-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30
[Table view] |
Text
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.t ENCLOSURE This enclosure consists of revised pages from the Browns Ferry Nuclear Plant unit 3 inservice inspection program. These pages are identified by the effective date of the revisions, July 3, 1979, in the upper righthand corner of each page. The location of the revised or additional
< information on each page is identified by a vertical bar in the righthand 1
4 margin. Table 1A is being added.
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- 2. Main Steam Piping
- There are some 139 (including the 4 pipe-to-vessel no::le safe-end welds) Class 1 circumferential and branch connection pressure boundary pipe joint velds in the main steam piping subject to inspection. All accessible welds will be inspected for the preservice baseline examination and 40 of the welds will be inspected in the inservice inspection interval. Four known welds are inaccessible because of being located under piping supports (25-3-1, 25-3-81, US-3-29, 25-3-56). See Table I for veld si:e and scheduled inspections. .
There are some 78 class 2 circumferential and branch connection pressure boundary pipe weld joints subject to examination. Approx-imately 15 of these welds will be examined during the first inservice inspection interval and 59 welds during the four intervals. See Table II for veld si:e and scheduled inspections.
The entire system is carbon st. eel and all'26-inch piping has longitudinal scam welds. ~
- 3. Feedvater Pining There are some 77 (including the 6 pipe-to-vessel no::le safe-end welds) Class 1 circumferential and branch connection pressure boundary pipe joint welds subject to examination.
The entire system piping is carbon steel. All accessible circumferencial welds will be inspected for the preservice baseline, and 27 of the welds will be inspected during the inservice inspection interval. Two known welds are inaccessible because of being located under piping supports (KFW-3-4, KFW-3-22). See Table I for weld size and scheduled inspections. -
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- 4. Core Spray Piping
- There are some 27 (including the 2 pipe-to-vessel nozzle safe-end welds) Class 1 circumferential pressure boundary pipe welds in the core spray piping subject to exanination. The entire system is stainless steel. All circumferential welds will be inspected for the preservice baseline, and 10 of the welds will be inspected during the 10-year inspection i interval. See Table I for veld size and scheduled inspections.
- 5. Residual Heat Re= oval System Piping There are 35 Class 1 stainless-steel pressure boundary circum-ferential and branch connection joint velds (excluding the two dissimilar welds covered in Section N) in this system, some of which have longitudinal welds intersecting. There are also 7 Class 1 carbon-steel circumferential welds. All circumferential welds will be inspected for the preservice baseline examination, and 19 welds will be examined during the 10-year inspection interval. One known weld is inaccessible .
inside a containment penetration (TRHR-3-193). Table I outlines the weld size and scheduled inspections.
There are some 367 Class 2 circusferential and branch connection pressuse bauadacy pipe weld joints subject to exasination.
Approximately 44 of these welds will be examined during the first inspection and 160 welds during the four intervals. See
, Table II for veld size and scheduled inspections. All Class 2 portions are carbon steel.
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- 6. Cener,1 nod Drive '.tvdraulie Return Thera are 15 Class 1 pressure boundary circumferencia,1 joint welds (including the pipe-to-vessel nozzle safe-end weld) in this entirely stainless-steel system. All these circum-
- ferential joint welds will be examined for the preservice baseline examination, and 4 welds will be inspected during the inspection interval. See Table 1 for outage inspection 8
schedule.
- 7. Reactor Cleanup System Piping There are 15 Class 1 circumferential joint welds in the stainicss-steel and 7 Class 1 circumferential joint welds in the carbon-steel portions of this system. All accessible circumferential welds will be inspected for the preservice baseline examina-tion, and 9 welds will be examined during the 10-year inspection interval. See Table I for outage schedules.
- 8. RCIC Piping There are come 4 Class 1 circumferential joint welds in this carbon-steel system cubject to examination. All 4 joints will be inspected for the preservice baseline examination and 1 joint during the 10-year inspection interval. See Table I for veld size and scheduled inspections.
- 9. HPCI Piping There are some 18 Class 1 pressure boundary circumferential joint welds in this carbon-steel system. All accessible circum-e 9
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7/3/79 ferential weld joints will be insp'ected for the preservice baseline examination, and 9 velds will be inspected during the inspection interval. See Table I for veld size and scheduled inspections.
I. Piping Pressure Retaining Bolting There-is no pressure retaining bolting in any of the Class 1 piping systems under consideration larger than 2 inches. The flange bolting for the head spray piping and the relief and safety valve-to-main steam flange bolting will be visually inspected by TVA during normal maintenance for signs of leakage and distress. Also, the blind flange bolting in the recirculation system will be visually inspected by TVA.
The Class 2 piping flange bolting is located at RER pump discharge orifices. Each connection includes 24 studs and 48 nuts (1-1/4 inches). Bolting of one connection shall be visually examined during each inspection interval, and'a total of 3 studs shall be ultra-sonically examined for the four inservice insoeetion intervals.
Flange ligaments between threaded stud holes and stud threads shall ,
be visually examined when the connection is disassembled. The studs and nuts are fabricated to A-193 GR.37 and A-194 GR.2H, respectively.
J. Piping Supports and Hangers (Includes Valve Suonorts)
! There are 80 integrally welded supports in the Class 1 piping systems which will be visually inspected for the preservice
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7/3/79 Table 1 (Coutin cJ)
B r ow,e s Fer ry %e t e e r Pt ..nt Ct..ss I s ommiyt s
'..timated Arca Tstal 5+vle Nt!*oJ of I samt mat tan N.c Rate Firmt C apencnt Mg TestcJ h e t t..n apettity it.;%vtcJ Cater.wy B. f u -I tar (er /Lr) Ritu rk s 40 . 8J 120 tht h %nt h %n t h J. FeeJwater 7 CH-M-2138-C Two welds inacces-C t a. samtesent ial w.:lJa mable (ETW-3-4 2." CS 23 6 UT 2 2 2 3-J Hv-3-22) Lo(atcJ unJer support 24" CS 2 1 UT. FT -
1 -
3-J E!W-3-7. MV-3-24 2J" CS 6 2 ti ! - I s-t 12" CS 32 a UT 2 3 3 B-J 12" CS 10 10 UT 3 3 4 8-J See Table 1A Br.ansh F8pe t'sunection WelJa 16" CS 1 I UT 1 - - B-J 6" CS 1 -
UT - - - 5-J 4 Care Spr e 75 Cu 't-2142-C Circicfervatial welJs 12" SS 19 5 UT 1 2 2 B-J 12" SS 4 4 UT I I 2 B-J See Table 1A 30" SS 4- 1 UT -
1 - B-J
- 5. Elik 8 Ot-?t-2141-C One ws!J inacces-Cis. saiorent tal wlds sable (IbiR-3-193) 2 " SS 20 5 UT 1 2 2 s-J LocateJ In Jrywell penetration
.4" SS 3 3 UT 1 1 I B-J See Table 1A
'a l" SS 7 2 UT I -
1 B-J 20" Jissimilar ! I UT. FT 1 - -
B-F 20" CS 2 1 UT - 1 - B-J b" SS 24 6 UT 2 2 2 8-J 0" Jasstellar 1 1 UT. FT - 1 - B-F 6" CS 4 1 UT - -
1 8-J Bransh pipe connection welds 6" SS 1 1 FT -
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o
,,c, Table 1 (Continued)
' 7/3/79 Browns Ferry Nuclear Plant Class 1 Components Estimated Area Total Sample Method of Esamination Dose Rate First Component Sample Tested Inspection 4 antity Inspected Category Refueling (ar/hr) Reearks 40 80 120 Honth Month ---Honth-
- 6. CRD hydraulic return 7 CH-M-2143-C Circumferential welds 4" SS 15 4 UT 1 1 2 B-J
- 7. RWCU. 5 CH-M-2144-C Circumferential welds 8" CS 2 1 UT 1 - - B-J 6" SS 11 3 UT 1 1 1 8-J '
6" SS 4 4 UT 1 1 2 B-J See Table 1A i 4" CS 5 1 UT -
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B-J
- 8. RCIC 5 CH-M-2144-C Circumferential welds i 6" CS 4 1 UT 1 - -
B-J -
7 CH-M-2145-C
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1 Table 1 (Continued) 713/9
- 3rowns Ferry Nuclear Plant Class l_ fomponents Estimated Area '
Total Sample Method of Examination Dose RJte First Component.. Sample Tested Inspection Qiantity igpe_cted Category. Itefueling (ar/ld Remarks i 40 80 120 Hon tle Mmtle tbu t ti --- -
- 9. HPCI' 7 CH-N-2145-C Circumferential welds
'16" CS 1 1 Irr 1 - -
B-J 14 CS 3 1 UT - 1 - B-J 10" CS 10 3 UT 1 1 1 B-J 10" CS i 4 4 UT 1 1 1 5-J See Table 1A i
- 10. Pressure Retaining Solting All VT B-C-2 e
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.6 TABLE 1A WELD INSPECTION l'Oi! PIPE 10. IIP PROTECTION SYSTDI !!EI.D IDENTIFICATION Main Steam GMS-32, G>lS-IS , CMS-24, CtlS-6, Dis-104, KHS-24 Feedwater KFW-39, CW-15, KW-38, CFW-9, CW-12, KW-13, CW-26, KFW-31 CFW-29 CW-3.'
RiiR ' DSRilR-6, DSR11R-7, DSI:liR-4 Core Spray DSCS-12, DSCS-4, DSCS-II, DSCS-5 RNCU DSRWC-4, DSRUC-6, DSRUC-3. DSRWC-5 liPCI Tl!PCI-72, TilPIC-70, TilPJC-70A, T11PCI-71 4
Note:
All the above welds will be inspected during each 10-year inspection interval for additional pipe vliip protection.
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7/3/79 DPP Assigned Sizes Weld No. Inches Material DRWC-3-1A 6 SS -
DRWC-3-1 6 SS DSRUC-3-1 6 SS DRWC-3-2 6 SS ,
DRWC-3-3 6 SS
. DSRWC-3-LA 6 SS DSRWC-3-2 6 SS DSRWC-3-3 6 SS DSRWC-3-4 6 SS .
DSRWC-3-5 6 SS DSRWC-3-6 6 SS 1
DSRWC-3-7 6 SS DRWC-3-4 6 SS .
DRWC-3-5A 6 SS DRWC-3-5B 6 SS DRWC- 3-60 8 CS DRWC 3-59 8 CS DSRWC-3-8 4 CS I#
DSRWC-3-9 4 CS DRWC-3-58 4 CS TRCIC-3-7 6 CS TRCIC-3-6 6 CS TRCIC-3-5 6 CS TRCIC-3-2 6 CS -
DRWC-3-59A 4 CS DRWC-3-59B 4 CS e
k es 9
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