Site Problem Rept 125,Revision 1,re Failure of Matl in Makeup Pump Stretched Studs to Meet Requirements of Certificate of Conformance.Ke Moore 790712 Memo to RP Williamson Re Necked Makeup Pump Case Stud EnclML20136C096 |
Person / Time |
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Site: |
Three Mile Island |
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Issue date: |
09/29/1977 |
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From: |
Pletke L, Rise D, Rogers L BABCOCK & WILCOX CO. |
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To: |
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References |
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TASK-TF, TASK-TMR 125-01, 125-1, PROB-770929, NUDOCS 7909140390 |
Download: ML20136C096 (3) |
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Category:PROBLEM/MAINTENANCE REPORT
MONTHYEARML20136C2051979-03-23023 March 1979 Summary Work List Re Various Instruments & Sys. Radiological Ref 130 ML20125D8921979-02-20020 February 1979 on 780329,reactor Tripped on Pump Power Trip,Followed by Rapid Depressurization of Rcs.Caused by De Energizing of Vital Power Supply 2-4.Review Underway Re Isolation, Surveillance & Operating Procedures ML20136C0651979-02-20020 February 1979 Site Problem Rept 198 Re Inability to Adjust Delta Flux Difference Amplifiers to Obtain K Factors Greater than Five Per Results of Tp 800/18,power Imbalance Detector Correlation Test.Old & New Wiring Diagrams Encl ML20136C0871978-10-15015 October 1978 Site Problem Rept 191 Re a & B Makeup Pump Gear Lube Oil Sys.Bearing Pressure Not Obtainable Due to Installed Pressure Gauge Located Downstream of Spray Throttle Valve. Addl Gauges Installed Per Attached Diagram ML20136C0381978-07-12012 July 1978 Site Problem Rept 174 Re Zero Ground Condition Discovered in 2A Reactor Coolant Pump Motor Between Upper & Lower Bearing Housings & Motor Casing.Caused by Positioning of Burns & Roe Oil Spill Retainer Housing ML20136C6991978-05-16016 May 1978 Work Request Approval for Calibr & Installation of Probes for Reactor Coolant Pump ML20136C6671978-05-10010 May 1978 Application to Remove Auxiliary Bldg Sump Pump WDL-T-5 from Svc for Replacement of Ruptured Disc ML20125B4531978-04-28028 April 1978 Startup Problem Rept 2690:on 780222,WDL-C-1A/B Tube Side Did Not Have Proper Overpressure Protection.Burns & Roe Proposed Solution on 780405.Action Completed Satisfactorily on 780428 ML19212A4761978-03-16016 March 1978 Chronological Summary of safety-related Maint & Operating Experience for 12-month Period Ending 771231 ML20125B4581978-03-15015 March 1978 Startup Problem Rept 5314:on 780314,radwaste Gas Release Rate of 90 Scfm Could Not Be Obtained.On 780317,flow Rate of 65 Scfm Determined Acceptable by Burns & Roe ML19252A2921978-01-20020 January 1978 Responds to NRC 780105 Questionnaire Re Standby Diesel Generator Unit Reliability ML20136C0611978-01-0606 January 1978 Site Problem Rept 152,Revision 1,re Failure of Makeup Pump Gear Oil Cooler to Meet Spec CS3-113 Paragraph 3.5 of Tubular Exchanger Manufacturers Association Stds.Spec Incomplete & Will Be Revised.Supporting Matl Encl ML20136C0421977-12-21021 December 1977 Site Problem Rept 161:during Ultrasonic Insp of 1A Flywheel, Insp Cover Bolt Was Trapped Between Flywheel & Shroud Covering Flywheel,Preventing Shaft Rotation.Bolt Removed & Flywheel Inspected ML20136C0461977-12-13013 December 1977 Site Problem Rept 157 Re Bump on Stuffing Box Seating Surface Formed by Depression of Lower Gasket Seating Surface During Disassembly of 1A Reactor Coolant Pump.Caused by Pressure Used to Break 1B & 2B Pumps Free ML20125B4781977-11-17017 November 1977 Startup Problem Rept Re Condensate ML20136C0481977-11-0808 November 1977 Site Problem Rept 149 Re Difference in Actual Range Between Hot & Cold Marks in Constant Load Supports of Reactor Coolant Pumps & Specified Range.Startup Problem Repts 2299 & 2436 Re Reactor Coolant Sys Encl ML20136C6771977-10-26026 October 1977 Surveillance Rept of RCS Valve RC-RV-2 from Mechanical Maint Dept.Work Requests Encl ML20136C0961977-09-29029 September 1977 Site Problem Rept 125,Revision 1,re Failure of Matl in Makeup Pump Stretched Studs to Meet Requirements of Certificate of Conformance.Ke Moore 790712 Memo to RP Williamson Re Necked Makeup Pump Case Stud Encl ML20136C0921977-09-0101 September 1977 Site Problem Rept 135 Re Malfunctioning of Tektro Pressure Control Valve for High Pressure Lube Oil Sys on Reactor Coolant Pump Motor 1A.Valve Disassembled & Cleaned,But Will Not Hold Pressure & Will Not Relieve ML20136C7331977-08-30030 August 1977 TMI Startup Problem Rept on 770830:valve RC-V2 Cracked Off Seat & RC-R2 Started Relieving Pressure.Solenoid Plunger Realigned & New Springs Installed.Work Requests & Notes Encl ML20136C0781977-08-11011 August 1977 Site Problem Rept 111 Re Corrections to Computer Point Listing.Bailey 855 Startup Problem Rept 2084 Encl ML20136C0841977-06-24024 June 1977 Site Problem Rept 109 Re Reactor Protection Sys & Resistance Temp Detector Re Test Data.Resistance Temp Detector Retested & Reworked W/Design Improvement Retested.Results Encl ML20136C0571977-06-20020 June 1977 Site Problem Rept 127 Re Standpipe Gasket Interference W/ Shaft in 2B Reactor Coolant Pump Motor.Pan Was Dropped,New Gaskets & New O-ring Installed.Motor Subsequently Was Successfully no-load Run.No Further Action Required ML20136C0351977-06-20020 June 1977 Site Problem Rept 127 Re Standpipe Gasket Interfering w/2B Reactor Coolant Pump Shaft on 770516.Pan Dropped & New Gaskets & New O-ring Installed.Motor Subsequently Successful During no-load Run.No Further Action Required ML20136C0671977-02-28028 February 1977 Site Problem Rept 113 Re Reactor Protection Sys Inputs. Startup Problem Rept 2089 & Response Encl ML20136C0751977-02-0707 February 1977 Site Problem Rept 112 Re Safety Features Actuation Sys & Reactor Protection Sys Errors.Startup Problem Repts 2087 & 2088 Encl ML19249F1751975-08-13013 August 1975 Energy Absorption in Size 24 Figure 607 Valve Seat & Disk. ML19276H2131973-09-0606 September 1973 Rept on Containment Bldg Vertical Tendon Upper Bearing Plates. ML19276H2111972-06-30030 June 1972 Containment Bldg Ring Girder Const & Repair,Addendum 2. ML19276H1091969-05-0909 May 1969 Summary of Factory Tests,Reactor Bldg Fan Assemblies, Prepared by American Air Filter Co 1979-03-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
Text
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O o SITE PROBLEM
~
REPORT TPJJ13MITTAL
FILE: 13- g- /25.of TO: Change Control For Distribution CONTRACT NO: 620-00 o'6 S . II. Klein -
Quality Ascuranee SPR / 7 r-o /
Central Engineerine Files TIEC meAn L. s cHz emyn- Tnc.k Enginect 4 ,, ,
/ ./P. 6 7 rx E - Project Mancrer DATE: 9-no -7 )
STATUS CODE C L. C. Rogers - MET. ED. 6/. /~uNd Foo '> f 4 F. R. Taist - TOLEDO .
J. R. Bohart - Intl. Support .
. J. L. Donnell - 0FR B. A. Karrasch - Plant Integration Attached is one copy of Site Probic:n Report No. /; c-a / which was processed on Contract 620-00 c4 . Future contracts have been reviewed for the potential of a similar probicm. This probics isdis not considered applicabic to other contracts .
PIMARKS:
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- Jersey Central 13 - 620-0006 125 ci P.A. NO. PAR 1 MO./lA5h NO. Grove no. M Q. h0.
YENDOR Bingha: 021-861LV 35 h0 1,2,3 111LE (HAI .30 CHAkACTEp5) PROBLEH COM1ACT .
IUP-lC Stretched Casing Studs E. G. Schaedel [/
, DESCRIPil0N Of PROBLEH:
As analysis of one of the stretched studs, by GPU, revealed that the caterial was not A-193-GR 16 as specified on the Certificate of Conformance. Tnis has raised questions concerning the validity of the Bingha: Q.A. data package.
See attached copies of CFU's analysis and MUP-1A,3,C Certificates of Confer =ance E
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. 5
5, y STA195-AC110h TO DATE, IKCLUDING PERSONS CONTACTED:
R. Willia = son L. Pletke ,
FURTHER AC110N RECOHHEHOED BY Lill PERSONNEL:
- 1. GPU has requested the test results of B&W's analysis and any conclucions regarding the stud elongation.
- 2. Advise if the Certificates of Confor=ance are valid for IUP-1A and 1B and IC.
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cc: H. F. Dobel THE BABC0CK & WILCOX COMPANY S. Funkhauser POWER GENERATION GROUP R. A. Fearing - Mt.
Vernon To l/
V R. P. WILLIAMSON, NUCLEAR SERVICE From K. E. MOORE, MC&C, TECHNICAL STAFF (7 Coh ses m .s Cust. File No.
THI-2 or Ref..
" NECKED" MU PUMP CASE STUD i
1 lm.i....,......,.........,..............,.
The Materials, Chemistry and Codes Unit was requested to coordinate !
the testing of an "overtorqued" makeup pump case stud from TMI-2. The l j
stud'given to MC&C was approxicately 6 in. in length x 1 in. diameter marked B-6. Evidence of necking was apparent over about a 3 in. length.
l l
The stud was subjected to hardness testing and emission spectroscopic analysis at Mr. Vernon Works - QA Metallurgy Lab. The verbal report from i Mt. Vernon indicates the following:
- 1. Hardness values equivalent to an ultimate tensile strength of
-110 ksi.
- 2. The chemical composition of 416 S.S. ,
Mr. R. A. Fearing - Mt. Vernon, will transmit his test report confirming these results at a later date.
While the measured hardness values were slightly lower than the MTR, ',
for this stud, certified by ESCO, there is no reason to bla=e cither the '
composition or the strength properties of this stud for the observed necking. '
8 geq K. E. Moore KEM/od ,
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. trk- ~.1 1 SPECIFICATION FOR ALLOY-STEEL BOLTING MATERIALS FOR dc55 d HIGH ';EMPERATURE SERVICE
,e is j l 3
- l. .O e
(D S S A-193 .
djW
% (Identical with ASTM Specificacion A 193-66) l
- . 3
? Scope for Lo..Temperaturt sc.Wce ( ASTM Designa-Li* A (b) The austenitic steel shall receive a
- 1. (c) This speci$ cation covers alloy. carbide solution treatment. This sha!!
d steel bolting material for pressure vesseis, Process
' ^ E * "
- d. uhes, 6anges, and 5ttings for high. ately af ter rdiirg or forpng to cwl at a coo ],, temperature service (Note 1). The term 2. The steel shall be made by one or rate su5ciently rapid to prevent injury l
3
$ W j *boltirg material" as used in this specifi. both of the following processes: open. to the material. It shah be reheated and cation covers ro' led, forged, or strain hearth cr electric. furnace. held a su5cient time at a ten perature at W
N harder.ed bars, and bolts, screws, studs, and stud bolts.
which the chromium carbide wiH go into Discard solution and shall then be co:!cd in air l i.' $ (b) Eight grades are covered, includ.
- or in a liquid medium at a rate su5cient
'M tag four ferritic steels and four austenitic 3. A su5cient discard shall be made to prevent the reprecipitation of the
)
O steels designated E5, DS, etc. Selec. frcm each ingot to secure freedom from ca rbide.
tion wGl hoend upon desirn, service con. injurious pipmg and undue segregation. (c) When increased mechanicd prr p.
.N'N ditions, mechanical proper' ties, and high.
temperature characteristics (Note 2). Heat Treatment erties are desirable, the austenitic boiting materials may be strain hardened.
g{ (c) Nuts for use with this bciting ma. 4. (c) Ferritic steels shall be properly l
d terial are covered in Section 13. heat treated as best suits the charat.
'" M*
l
$ ' 'y$ (() Supplementary requirements (Par. teristics of each grade. Immediately sf ter 5. Each alloy shall ccnform to the N !
ch, ag raphs Si and S2) of an optional rolling or forging, the boiting maierial requ:rements as to chemical composition l 4 c.ature are provided. These shall apply shall be aHoued to cool to a temrerature prewribed in Table I.
aly aben speci6ed in the inquiry, con. below the cooling critical targe. The ma.
.M tract, and order, terials uhich are to be furnished in the a Ana sis Non L-It ordering material under this liquid-quenched condition shall then be 6. An analysis of each heat of steel e inecihatmn. or ir. orperatie: it as a reference umformly reheated to the proper tem. shall be made by the rnanufacturer to in iny irMdaal snecdcatien. .purcbeers must perature to refme the grain (a group thus determine the percentages of the ele.
. 4
- 6 ;:2te the steel by ide::ti5 cation symbol and reheated being known as a "cuenching ments speci6ed in Section 5. Th swys4. or ataps atone. ned de5citely specify char;:c") and quenched in some liquid shall be made from a test inrot ta' ken f$m T for aNi i$um1 rnper' medium under subst antially uniform during the pouring of the heat. The d Ira ierperaure that at least conforms to the conditions for each quenching charge. chenucal compos; tion thus determined fQT repre:,erts of Secnoa 4 (c) or (t). i The mater:als whkh are to be furnished shall be reported to the purchaser or his l
.TM . Nm 2.-The comrnittee formutatiog this in the normalized or air quenched condi. representative, and shall conform to the be rat c cs e u$eIfor tIp es t ti n shaU be rcheated to lhe prcper requirements speci5ed in Section 5.
d'J J poo.e. Othe ec,peutions siti be considered t emperat ure to re6ne the grain and
.:9 krindusier, by the comittee from time to time cooled uniformly in air to a temperature Check Analysis W u the n-d becces a;mucci. below the conhng critical rance. The Nm 3 -For grades of ahoy. steel bdnec 7. An analysis may be made by the material, whether liquid quenched or purchafer froIn samples representing the h eNr$ere a$pIatNas refe eIe s5c] n rmalized, shall then be uniform!y re. bolting material. The chemical compo31
' '7S b eide to the Sreci:stions for Querated acd heated for tempering. The minimum tion thus determined shall conform to J ,* Ternered AUoy Steel Bedts aad Studs with tempering temperature shaU he at speci. the requirements speci6ed in Section 5.
g 5mtat;e huts ( ASTM Des pat ec: A 354).
hm 4 -For grades of ancy-steel bo!tieg Sed in Table II. The max!=um operat.
. w.q <i., Medal suitat:e ic? use in Imotemperature a;>- ing temE>erature should be at least 100 F Tmue Proputies grf,* pano,3, r.rerene, shwd he marie to the (56 C) lower than the minimum temper- 8. (c) The material shall conform to A .{ $(cchauons for ADoy6 teel Bolting Materials ing temperature.
- [.,h,.;3.E the requirements as to tensiie properties N M. 101 M.;gP(.
a ...
.J.GA :)n 1 %.u . _ . . _