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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARLD-97-031, Part 21 Rept Re Incorrect Nut & Washer Plate Matl for ECCS Suction Strainer Bolted Connections.Nut Plates & Washer Plates Fabricated from Incorrect Matl & Delivered to Peach Bottom Unit 3 Site.Nut & Washer Plates Never Installed1997-10-30030 October 1997 Part 21 Rept Re Incorrect Nut & Washer Plate Matl for ECCS Suction Strainer Bolted Connections.Nut Plates & Washer Plates Fabricated from Incorrect Matl & Delivered to Peach Bottom Unit 3 Site.Nut & Washer Plates Never Installed ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20116L5121992-10-0909 October 1992 Part 21 Rept Re safety-related RHR Pump Motor Fan Failure Due to Lack of Weld Penetration Between Fan Blades & Discs. New Duplicate GE Motors Mfg by GE Canada,Motors & Drive Dept.New Surplus Motors Have Double Fillet Welds ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20151M7371988-07-29029 July 1988 Part 21 Rept Re Discovery of Cooper Contamination in 125- Volt Station Batteries.Cooper Contamination Could Result in Lowering of Cell Voltage or Negative Plate Voltage W/ Reduction in Battery Capacity ML20236F4911987-10-19019 October 1987 Part 21 Rept on QA Controls Re NDE Records Utilized by Eastern Testing & Insp,Inc During Performance of NDE Svcs at Facility.Names of Individuals Informing NRC & Identification of Basic Svcs Containing Defect Provided ML20204B3621987-03-19019 March 1987 Part 21 & Deficiency Rept Re Reactor Protection Sys Power Supply Circuit Breaker Deficiencies.Initially Reported on 860616.Unit 3 Mods Complete.Unit 2 Mods,To Be Completed During Spring 1987 Outage,Currently in Progress ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20211P5111986-06-16016 June 1986 Part 21 Rept Re Failures of Shunt Trip Coils on Westinghouse Circuit Breakers in Reactor Protection Sys.Initially Reported on 860609.Breakers Replaced,Operation Aids (Labels) Added & Equipment Modified.Related Correspondence ML20203C5261986-04-14014 April 1986 Part 21 Rept Re Defect in Westinghouse Circuit Breakers Type Lbb,Catalog Number LBB22250 W/Factory Installed 125-volt Dc Shunt Trip.Defect Could Result in Burning Out Shunt Trip Coil ML20155F2381986-03-13013 March 1986 Part 21 & Deficiency Rept Re Failure of Clow Corp Containment Isolation & Vacuum Relief Valves in torus-to-vacuum Breaker Lines.Bearings Being Replaced W/ Different Matl.Related Correspondence ML20154A3741986-02-24024 February 1986 Part 21 Rept Re Failure of Diesel Engine E-2 Air Blower. Generator Disassembled for Removal of Aluminum Fragments & Replacement of Colt Industries,Inc Turbochargers,Roots Blower & Piston Rings ML20133N4691985-08-0505 August 1985 Part 21 Rept Re Raychem Wcsf Shrink Sleeving for Sensor/ Connecting Assembly of Safety Relief Valve Monitoring Sys. Testing & Retesting in Progress.Sensor Installation Utilizing Shrink Sleeving Recommended ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20129G4401985-05-29029 May 1985 Part 21 Rept Re Failure of Inner Polar Connector Between Damper Bar Circuit on Generator Main Field.Cause of Failure Not Defined.Further Investigation Necessary ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20112C6491985-03-14014 March 1985 Part 21 & Deficiency Rept Re Inadequate Designed Clamps. Initially Reported on 850314.Spring Disc Washers Required in Clamp Design Shipped to Site,Assembly Drawings Revised to Include Spring Disc & Installation Procedure Made ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20069H0651983-03-23023 March 1983 Part 21 Rept Re Discovery of Failed Switch Operator Cam 14 within Position Selector Switch 4,operating ECCS Pump Room Cooler.Initially Reported on 830104.Caused by Cam Matl Fracturing Into Small Pieces.Jumpers Installed ML20086F0691977-07-15015 July 1977 Interim Deficiency Rept Re Welding Deficiencies on Embeds. Initially Reported on 770616.Caused by Improper Weld Joint Preparation.Personnel Instructed in Proper Interpretation of Welding Symbols on Design Drawings ML20086F0731977-07-0101 July 1977 Interim Significant Deficiency Rept 2 Re Structural Steel Defects.Initially Reported on 770111.Final Rept Will Be Submitted on 770801 Rather than 770701 ML20086F1101977-04-0101 April 1977 Interim Significant Deficiency Rept 2 Re Structural Steel Defects.Initially Reported on 770111.Caused by Improper Flange Trimming Operations,Failure to Properly Prepare Cope for Repair Welding & Deficient Repair Welding ML20086F1611977-01-11011 January 1977 Forwards Significant Deficiency Rept 2 Re Discovery of Cracks in Plate Girders Located in Reactor Bldgs.Initially Reported on 761209.Hold Placed on Const Activities That May Impose Substantial Addl Loads.Final Rept by 770401 ML20085E7651976-08-0505 August 1976 Final Deficiency Rept Re Incorrect Installation of Reactor Pressure Vessel (RPV) Seismic Stabilizer Plates.Initially Reported on 760513.Formal QA Program Developed & Implemented Since Pvs Stabilizer Assembly Installed ML20090L5211974-10-0303 October 1974 Significant Deficiency Rept SDR5 Re High Pressure Svc Water Valve Weld Failure.Initially Reported on 730601.Vendor Weld Stress Analysis Calculations Reviewed & Table of Acceptable Weld Sizes Prepared ML20086L0301974-05-20020 May 1974 Final Deficiency Rept Re Main Steam Line piping-external Surface Indications.Caused by Hot Tears in High Strain Areas of Pipe Induced During,Bending Process.Program for Exam of High Strain Areas Implemented ML20086Q5241974-05-15015 May 1974 Final Significant Deficiency Rept SDR 4 Re Core Spray Sparger.Core Spray Sparger Removed & Shipped to Reactor Controls,Inc for Rework to Meet NSSS Supplier Requirements & Reinstalled in Vessel ML20086L0391974-02-0606 February 1974 Interim Significant Deficiency Rept Re Main Steam Line piping-external Surface Indications.Caused by Hot Tears in High Strain Area of Pipe Induced During Bending Process. Program for Exam of Piping Being Implemented ML20086Q1951973-10-25025 October 1973 Final Significant Deficiency Rept SDR-1 Re Reactor Pressure Vessel Top Fuel Guide.Nicks & Scratches on Beam B Were Ground Flush to Surface.Beam a Replaced ML20084A0271973-10-0101 October 1973 Significant Deficiency Rept SDR-5 Re Weld Failure on High Pressure Svc Water Valve.Initially Reported on 730601.Eight Failed Valves Identified.All Valves Returned to Vendor for Rework to Eliminate Shims ML20085M3901973-10-0101 October 1973 Significant Deficiency Rept Re Weld Failure on High Pressure Svc Water Valve in Unit 2.Initially Reported on 730601. Vendor Weld Stress Analysis Calculations Reviewed.Table of Acceptable Weld Sizes Prepared ML20086Q4061973-07-19019 July 1973 Significant Deficiency Rept SDR 6 Re Blistering of Coating on Torus.Caused by Unavoidable Overlapping of Phenolic Sys During Application.All Loose,Phenolic Finish Coat Removed & Care Taken Not to Disturb Condition of Primer ML20086Q5001973-06-28028 June 1973 Interim Significant Deficiency Rept SDR 5 Re High Pressure Svc Water Valve Weld Failure.Caused by Insufficient Fillet Weld Throat Dimension.Valves Reworked to Eliminate Shims & Mounting Plates Rewelded ML20086Q5281973-06-13013 June 1973 Supplementary Interim Significant Deficiency Rept SDR 4 Re Core Spray Sparger.Rept Will Be Submitted on 730901 Instead of 730701 ML20086Q5431973-05-0202 May 1973 Interim Significant Deficiency Rept SDR 4 Re Core Spray Sparger.Core Spray Sparger Removed & Shipped to Reactor Controls,Inc for Rework to Meet GE Ape Design Requirements ML20086Q5981973-03-23023 March 1973 Final Significant Deficiency Rept SDR 3 Re Main Steam Line Restraints.Caused by Design Error.Affected Restraints Will Be Abandoned & Replaced W/Restraints Designed to Original Criteria & Allowable Stresses ML20086Q6031973-02-0101 February 1973 Supplementary Interim Significant Deficiency Rept SDR 3 Re Main Steam Line Restraints.Restraints Will Be Replaced.Rept Discussing Replacement & New Design Will Be Submitted by 730306 ML20086Q9691972-12-22022 December 1972 Supplementary Interim Deficiency Rept Re Damage to Vessel Top Fuel Guide.Results of Evaluation Being Evaluated & Corrective Action Being Determined.Rept Wil Be Submitted in Feb 1973 1997-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
[Table view] |
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9 9 PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET PHILADELPHI A. PA.19101 V.S.BOYER vica rnssioant July 19, 1973 x
Dr. D.F. Knuth, Director Directorate of Regulatory Operations United States Atomic Energy Commission Washington, D.C. 20545
Subject:
Significant Deficiency Report - Blistering of Coating on Unit #2 Torus Peach Bottom Atomic Power Station - Units 2 and 3 AEC Construction Permit Nos. CPPR-37 and CFPRe-38 File: QUAL 2-10-2 SDR No. 6 Dear Dr. Knuth In compliance with 100FR50 55, paragraph (e) attached is the Significant Deficiency Report concerning subject Blistering of Coating on Unit No. 2 Torus. This item was reported to AEC DRO I by telecon on June 8,1973 We trust that this satisfactorily resolves this item.
If further information is required, please do not hesitate to contact us.
We appreciate yc,ur extending the time for our response to July 23, 1973 as agreed by telecon of July 9, 1973 between our Mr. H. B. Winitsky and Mr. J. Allentuck, USAEC DRO I.
Sincerely, ff./1 y%
Attachment Copy to: J. P. O'Reilly, USAEC V
\ p h 8402270537 790813 gDRADOCK 05000277 D PDR 3 0670
- '. ATTACHMENT 1
- Significant Deficiency Report - SDR No. 6 Torus Coating Failure in Unit No. 2
; Peach Bottom Atomic Power Station - Units 2 and 3 AEC Construction Permit Nos. CPPR-37 and CPPR-38 i
INTRODUCTION AND BACKGROUND The Torus is located below and encircles the Drywell (see attached sketch) with a centerline diameter of approximately 111 feet and a cross-
; sectional diameter of 31 feet.
To provide protection against corrosion, the internal surfaces of the structural steel plates for the Torus were shop coated with inorganic zine over a pickled steel surface preparation.
l During 1969 and 1970 a phenolic finish coat was. applied over all
. interior surfaces of the #2 Torus. The decision to apply a top coat i over inorganic zine stemmed from a concern within the industry of hydrogen evolution from inorganic zine exposed to deionized water and steam atmos-phere. It was subsequently determined by independent testin contribution of hydrogen would be minimal (about 0.28 vol.).%gHowever, that the all hydrogen content will be kept below the lower explosive limit of 4%
j via the Containment Atmospheric Dilution System.
The selection of a phenolic topcoat was based on test results of various combinations of coating systems for the Peach Bottom Design Basis Accident Criteria.
In March, 1971, during a routine inspection of the #2 Torus, failure of the phenolic coating was found below the waterline. On February 10,
- 1972 it was decided to repair the Torus interior coating.as follows
1 4 1. Below water line: Cand blast to white metal and apply inorganic zine (one coat) only.
I
- 2. Water line level: Sand blast to white metal in 2 ft. band
! and apply one coat of inorganic zine and one top coat of phenolic.
4 3 Vapor Zone (above water line): Repair defective areas only.
The rationale for retention of the top coating in the vapor zone was that the condition of coating was essentially good. Coating adhesion tests performed during the re-coating investigation substantiated this rationale.
At the present time the Torus is costed with one coat of inorganic zine in the immersion zone with a-two foot wide phenolic band at the water line and the original coating system in the vapor zone.
On May 31, 1973 after the Torus underwent a relatively severe dynamic ,,
steam test (demineralized water heated to 1800F, held at this temperature for
~
i approximately 48 hours or more and then subjected to a " fast" cool down)
, ~ blister formation was observed in the vapor zone area of the Torus.
1 PB-SDR-6
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l DESCRIPTION OF DEFICIENCY A thorough inspection revealed that the phenolic finish coat blistered in localized areas. The blistering or delamination occurred at the phenolic 1 waterline band and in 16calized areas in the vapor zone as large as six feet in diameter, but mainly in smller areas of concentrated blisters no more than approximately one foot in diameter. Also, clusters of individual blisters one ,
half inch or less in diameter were found at scattered locations. These blister clusters averaged about one foot in diameter. -
It is estimated the total phenolic failure amounted to less than 1% of the surface area. The inorganic zine base coat, in failure areas, was found to be
; in excellent condition.
Preliminary analysis of the blistered areas indicated that in general the blistering or delamination occurred in the areas where a two-coat phenolic system existed because of unavoidable overlapping during application. This determination was made by measuring tha paint chips and visual examination of
, exposed areas where phenolic still exists. The examination also showed that the bonding between inorganic zine and the metal surface is still intact.
ANALYS~S OF SAFMPY IMPLICATIONS l Blistering and subsequent delamination of the phenolic top coat may occur l during a " loss of coolant" accident. However, this material is of the thermo setting type and has a melting point of about 1100 F, therefore the material i
will harden, become more brittle and not react with the deionized water. Also, since the phenolic is heavier than water, it will settle to the bottom of the Torus. Plu
' the Torus.(gging of strainers segmented is notring by structural likely, considering girders) the configuration and realizing of that typical Core
- Spray and HPCI strainers are connected to 16-inch pipe and the RHR strainer to
, 24-inch pipe, and the strainers are truncated cones with areasiof 4 7 and 7 i square feet respectively. They are mounted one foot above the Torus invert and .
have 1/8" holes. Further, the strainer flow area is conservatively designed-
~
with twice the area requred to pass the design flow at design pressure drop.
CORRECTIVE ACTION On June 1, 1973 all loose, phenolic finish coat was removed and care was taken not to disturb the condition of inorganic zine primer.
After removal of loose material, a testing program was initiated on June 1 and completed on June 14,-1973 to determine the integrity of the remaining phenolic top coat, including steam dynamic testa simulating the conditions
- experienced on May 31, 1973 The results of inspections made after conclusion of these tests clearly indicated that the inorganic zine primer was performing its corrosion resistance function and that the vast majority of the remaining phenolic finish coat was firmly adherred and is satisfactory from'a performance standpoint. .
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CORRECTIVE ACTION - Continued The cafety analysis design basis includes suppression pool cooling to preclude operation outside of the containment design temperature and pressure for all modes of planned operation, abnormal operational transients and accidents, with the exception of the monthly surveillance testing of the High Pressure Coolant Injection System and Reactor Core Isolation Cooling System turbines. Steps are being taken to incorporate operation of a Residual Heat Removal heat exchanger (with high pressure service water) to cool and circulate the water during monthly surveillance testing of the High Pressure Coolant Injection System and Reactor Core Isolation Cooling System turbines. This procedure will preclude localized high temperature on the vessel wall and eliminate thermal stress on the coating (such as was experienced on the May 31, 1973 l coating failure) during normal plant operation.
ADDITIONAL INFORMATION In view of the foregoing, we have initiated the necessary procedure to recoat. thit #3 Torus as follows:
- a. Below water line: Sand blast to white metal and apply one coat of inorganic zine only.
- b. Vapor Zone: Repair defective areas in present inorganic zine coating.
This procedure will provide an inorganic zine coating on the entire internal surfaces of the Torus.
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