|
---|
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
.- ....---. .
_
.
!
.
ENCLOSURE INSERVICE INSPECTION
SUMMARY
BROWNS FERRY NUCI. EAR PLANT UNIT 3 (DOCKET No. 50-296)
In accordance with paragraph IWA 6220 of Section XI of the ASME Boiler and Pressure Vessel Code (1974 Edition, Summer 1975 Addenda), the following information is provided:
c.1. Date: December 1979
, c.2. Name of owner and address of corporate offices:
Tennessee Valley Authority Chattanooga, Tennassee 37401 c.3. Name and address of nuclet generating plant in which the nuclear power unit is located:
Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35601 c.4. Name or nun.ber assigned to the nuclear power unit by the owner:
Browns Ferry Nuclear Plant unit 3 c.5. Commercial service date assigned to the nuclear power unit by the owner:
March 1,1977 d.1. The number assigned to the "bo ile r ," " pressure vessel," or component by the State, municipality, or province:
Does not apply.
d.2. National Board Number assigned by the manufacturer to the " boiler,"
" pressure vessel," or component:
Does not apply.
d.3. Names of the components or parts of the components for which this is a record, including such in fo rma tion regarding size, capacity, material, location, and drawings as. may aid accurate identification:
The components or parts examined as part of this inservice inspection are listed in the abstract.
d.4. Name of the manufacturer of the components or parts for which this is a record, including the manufacturer's component or part numbers and such information regarding the manufacturer's corporate office or manufacturing locations as may aid in gaining: access to the manuf ac tu re r's records regarding the components or parts that the n002150 E F6 ;
. .
.
'
manufacturer is maintaining in accordance with requirements of section III:
The majortty of the components examined was supplied by:
General Electric Company Atomic Power Equipment Department San Jose, California TVA Contract 66C60-90744 d.5. Date of completion of the inservice inspection:
November 1979 d.6. Name or names of the inspector (s), when required:
The Tennessee Valley Authority acted as ite. cvn inspector.
d.7. Name and mailing address of the employer (s) or the inspector (s):
Tennessee Valley Authority 505 Edney Building Chattanooga, Tennessee 37401 d.8. Abstract of examinations performed, conditions observed, and corrective measures recommended and taken:
During the periods of August 22 through September 21, 1979, and October 11 through October 31, 1979, Lambert-MacGill-Thomas, Inc. (LMT), under contract to Tennessee Valley Authority (TVA) performed either ultrasonic, liquid penetrant, magnetic particle, and visual examination on the following welds and bolting on unit 3:
Main Steam - GMS-3-5, GMS-3-32*, GMS-3-20, CMS-3-17, GMS-3-15*, GMS-3-25, KMS-3-53. KMS-3-32, KMS 103, KMS-3-36. KMS-3-59, KMS-3-3, IC1S-3-70 Feedwater - GFW-3-6, KFW-3-23, GFW-3-14, KFW-3-39*,
GFW-3-12*, GFW-3-26*, KFW-3-36, KFW-3-3 Core Spray - DCS-3-17, DCS-3-16, DSCS-3-12*, USCS-3-114, DSCS-3-10, DCS-3-8, DCS-3-7, DSC-3-15, DSC-3-9, DCS-3-6 Core Saray (Baseline of Replacement Carbon Steel Pipe Welds) -
TCS3410, TCS-3-409, TCS-3-403, TCS-3-407, TCS-3-406, TCS-3-405, TSCS-3-404, TCS-3-403, TSCS-3-402, TCS-3-401, TCS-3-417, TSCS-3-413, TCS-3-419, TSCS-3-420, TCS-3-421, TCS-3-422, TCS-3-424, iCS-3-423, TSCS-3-425X, TCS-3-425 Residual Heat Removal - DSRHR-3-6*, DRHR-3-7, DS Td[R 10, TRHR-3-191, DHS-3-1, DSHS-3-9
.
9
- _. . . . . ..... __ .
.
- -
. .
Reactor Water Clean-up - DRWC-3-59, DSRWCU-3-3*, DRWC-3-1A Reactor Core Isolation Cooling - TRCIC-3-2 High Pressure Coolant Injection - THPCI-3-66, THPCI-3-70*
Recirculation - GR-3-60, GR-3-53, KR-3-46, KR-3-37, GR-3-11, GR-3-46, KR-3-22, KR-3-42 Recirculation Inlet Thermal Sleeves - N2B, N2D, N2F, N2H, N2K Valve Bolting - FCV-68-1, FCV-68-33, FCV-1-14, FCV-1-27, PCV-1-4, PCV-1-18, PCV-1-34, PCV-1-42, 1-537, HCV-3-67, 3-572, HCV-75-27, FCV-75-54 Vessel Seams - C-4-5(1 ft), C-3-4(1 ft), V-4-c(0.5 ft),
V-5-A(1.5 ft)
Vessel Head - RCH-3-10(0.5 ft), RCH-3-1V(1 ft),
RCH-3-2V (2 ft)
Vessel to Flange - (23 ft)
Head to Flange - (22 f t)
Main Steam Nozzle N3B (Nozzle to Vessel, Inner Radius, and Safe End)
Core Spray Nozzle N5A (Nozzle to Vessel, Inner Radius, and Safe End)
Feedwater Nozzle N4C (Nozzle to Vessel, Inner Radius, and Safe End)
Feedwater Nozzle N4B (Nozzle to Vessel, Inner Radius, and Safe End)
Recirculation Nozzle NIA (Nozzle to Vessel, Inner Radius, and Safe End)
Recirculation Nozzle N2B (Nozzle to Vessel, Inner Radius, and Safe End)
Recirculation Nozzle N2D (Nozzle to Vessel, Inner Radius, and Safe End)
Recirculation Nozzle N2F (Nozzle to Vessel, Inner Fadius, and Safe End)
Jet Pump Instrumentation Nozzle N8A (Nozzle to Vessel, Inner Radius , and Safe End)
.
-
_ _ _ . . _ _ _ _ _ _.. . . ._, . . . . -
.
. . .
~
.
Vessel Head Nozzles - N6A, N6Al Vessel Stud Numbers 26, 63-71 Vessel Nut Numbers 30 Vessel Washer Numbers 30 Vessel Bushing Numbers 71 Vessel Ligament Numbers 30 ,
Skirt to Vessel Weld - 1 f t Clad Patches - 2 Recirculation Pipe and Valve Hangers - KR-3-S4, R-3-R1, R-3-H1, R-3-H2, R-3-SS1, R-3-SS3, R-3-R1, R-3-H12, R-3-89 Recirculation Pump Hangers - R-3B-H3, R-3A-H2 Main Steam Pipe and Valve Hangers - MS-3-HA1, MS-3-HC4, MS-3-SSA12, MS-3-HA4, MS-3-RD3, MS-3-GD-1, MS-3-SSB4, MS-3-SSB5, MS-3-HC1, MS-3-SSC2, MS-3-HC4
'
Feedwater Pipe and Valve Hangers - FW-3-H6, FW-3-H7, fW-3-H5, FW-3-3, FW-3-G1, FW-3-H10, FW-3-SSB1, FW-3-SSB3, FW-3-SSB7, FW-3-H7 Core Spray Pipe and Valve Hangers - CS-3-H6, CS-3-HS, CS-3-H1 Residual Heat Removal Pipe and Valve Hangers - HS-3-H15, RHR-3-H6, RHR-3-H3, RHR-3-H9, RHR-3-H2, HS-3-11, HS-3-H15, HS-3-R75 Reactor Water Clean-up Pipe and Valve Hangers - RWC-3-H1 High Pressure Coolant Injection Pipe and Valve Hangers -
HPCI-3-H1 Recirculation Pump Bolting - 10
.
.
._
,
. . . . _ .. . _ . _ . _ . . .._. . . m. .
.
.
Recirculation Pump Nuts - 10 Resideal Heat Removal Heat Exchanger Circumferential welds RHRG-10-A (3 f t), RHRG-11-A (0.5 f t)
Bolts - 12 on B Nuts - 112/ flange on B Main Steam (Class 2) - DMS-3-9, DMS-3-16, DMS-3-17, DMS-3-29, DSAS-3, DSAS-15 Residual Heat Removal (Class 2) - TRHR-3-281, TRHR-3-67, TRHR-3-39A, TRHR-3-197, TRHR-3-204, TRHR-3-239, TRHR-3-183C, TRHR-3-374, TRHR-3-320, TRHR-3-104, TRHR-3-253, TRHR-3-404, TRHR-3-448, TRHR-3-118C Residual Heat Removal Pipe Flange Bolts - A Pump Discharge (24)
Residual r eat! Removal Pipe Flange Nuts - A Pump Discharge (48)
Residual Hes' Removal Pump Bolts - A Pump (24)
Residual Heat Removal Pump Nuts - A Pump (24)
Main Steam Supports and Hangers - RG-1-ST, RG-1-MSR, MSH-3-12, MSH-3-7, MSH-3-10, MSH-3-13, MSGEH-1, MSH-3-17, HPASH-1, HPASH-3, HPASH-8, HPASH-10, RPASH-18 Residual Heat Removal Supports and Hangers - H-158, R-50, H-122, H-62, H-14, H-4, H-23, H-158, R-36, H-82, H-84, H-SS, R-35, H-73, R-35C, H-98, R-50, H-63,
- H-55, H-122, H-56, H-65, H-121, R-54, H-67, H-o2, R-o4, H-124, H-125, H-4, H-14, H-16, H-10, H-8, H-26, H-19, H-21, H-23, H-29, H-146, R-70, H-160, H-145B
- These welds are included in the plant technical. speci'fications as an augmented inspection to protect against damage caused by pipe whip. The remainder of the program is listed in "The
.
.
-
.
.
Preservice Baseline Inspection and Inservice Inspection Program for the Tennessee Valley Authority - Browns Ferry Nuclear Plant,"
which is Surveillance Instruction 4.6.g.
Most examinations performed by LMT and TVA showed nothing but geometric indications caused by mismatch or weld crown. A rejectable linear indication was found on weld DCS-3-18; however, this 10-inch stainless steel core spray weld was already scheduled to be replaced with carbon steel. Another indication was located on weld TilPCI-3-66, a 10-inch carbon steel seam weld. Further evaluation which included radiographic examination was performed. It was determined that this weld was acceptable but would be examined again during the next inservice inspection of this unit.
Records which give detailed information on this inspection will be filed at Browns Ferry Nuclear Plant.
1
.
I