ML20126B901
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{{#Wiki_filter:. ./ ./ UNITED STATES y '..vCLEAR REGULATORY COMMISSION WASHINoTON, D. C. 20555 /z3 March 28,1983 g4 h Docket No. 50-289 FACILITY Three Mile Island Nuclear Station, Unit 1 (TMI-1) LICENSEE: GPU Nuclear Corporation (GPUN)
SUBJECT:
SUMMARY
OF MEETING WITH GPUN ON MARCH 10, 1983 CONCERNING THE TMI-l STEAM GENERATOR RECOVERY PROGRAM
===. Background=== The purpose of the March 10, 1983 meeting was to brief the staff and staff consultants on the GPUN Reactor Coolant System Cleanup Program. The brief addressed the results and present status of various supporting tests, as well as the reactor coolant system (RCS) conditions for cleaning, chemistry parameters, cleaning effects, etc., The recovery program schedule and licensing considerations were also. discussed. The meeting attendees are listed in Enclosure 1. The GPUN presentation material is included as Enclosure 2. Reactor Coolant System Cleanup Program ~ GPUN described the purpose of the program as reducing the levels of ~ sulfur in the RCS. This would be done by adding H 0 to the ^ 79 coolant to convert the sulfur to sulfate. The sulfate would then be removed from the system by fon exchange. The process would be performed under protective (alkaline) conditions. GPUN characterized the potential risk of resumed or continuing steam generator corrosion as a result of the H 0 cleaning process as 2.7 being small. As evidence, GPUN observed tnat no H 0 related corrosion problems have been identified at PWRs which routin$lh add H 0, to and/or routinely form H,0, in the coolant. GPUN also cited shecific 2 e . test results and or.-gothg' confirmatory tests as additional evidence. GPUN presented a synaposis of its February 10, 1983 meeting of industry. experts on this issue; an NRC observer did attend that meeting. GPUN also presented the results of sulfur measurements on L a THI-l steam generator tube sample, a graph of polypropylene-like film
- thickness on a tube sample versus H,0, cleaning time, and other l-test results and measur~ements. GPUh conctuaed that it needs a better understanding of polypropylene film behavior during cleaning, better
{ comprehension of total sulfur data, and a better understanding of i atmospheric sulfur contributions. GPUN further concluded that the only ( l remaining major question is how much cleaning time is required to effectively j clean polypropylene-coated tubes. "The kinetic expansion process has deposited a thin polypropylene coating on the inner surface of the tubes. 3 [y [ Ad 8506140243 850125 9 PDR FOIA e DETJEN64-897 PDR g 7 2
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'L_Y V RE3 T3Ry 11F]R4ATION 31ST<ISJ) Jv SYSTE4 (RIJS) ACCESSION NBR:3304370379 )]:.3 ATE: 33/04/04 N3fA.41ZE): N3 JOCKET s FACIL:50-289 Tiree Mile Islano Mu: lear Station, Jiit 1, Metrocolit 35000289 AJTH.NAME AJTiJR 47Fd.IAT!3N MJKILL,1.3. 3eners.1 2Joli: J t i l i t i e s - 3 3'J S e r v i c e Coro. RECID.NAME R EC12.IE 4 Ti A:FILJ A TI 3 N STOLZ,J.F. Joerstiig Reactors 3 ranch 4 SJBJECT: Forwards " Rest o.f.Thiro Party Review o.f T41-1 Steam
- eneretor Reoair." Rest inclades discussions from S21209 meetino.
DISTRIBJTION 03)E: A001S COPIES RECEIVED: L.TR __[ ENCL;l_! SIZE:_].I~____ TITLE: 3R S am n i t t ail : 3 e ne rs.li Di s t ri out i on NOTES:R. Conte:1:v. NRR/)HF6/LQ3:1cv. AEOD/ORNSTEIN:1:v. 05000289 R EC I 3'I ENT
- DPIES RECIDIENT8 C3 PIES ID 03)E/NAME.
.lTTR E.N C L 13 003E/MA4E LTTR ENCL-VRR 3Rd4 30; 31 7 7 I 9 T E R.v A L: ELO[i)Su 1 0 NRR/DE/MTES 1 1 NR R /D 314-1 1 NRR/DL/ ORA 3 1 0 1RR/031/4EiTB 1 I NR I/4A3 1 1 R E G F.I'. E. 34 1 1 Q. WT 1 1 EXTERNAL: ACRS 39 6 6 LP)R 03 1 1 NRC 334 02 1 1 VSIO. 05 1 1 NTIS 1 1 NOTES': 3 3 gy /*'
s.. ~ r~ APPENDfX D (.. o. TPR Bibilography e 1. Date: April 12, 1982 Subj ect: Third Party Reviev To: TPR Members Material -Transmitted: .l OTSG CHARTER 42 Membership List and Resumes of TPR J Map to.GPEN 4 OTSG Repair Task Organization J Preliminary Report Failure Analysis 4 Preliminary Report - Eddy Current Exam Program .7 Agenda - April 23 - TMI-l OTSG Review Outline J Randout from April 7 Status meeting with NRC 9 Handout from January 25, TMI-l OTSG Status Review (NRC) e 2. Date: April 16, 1982
Subject:
TPR To: TPR Members Material Transmitted: .1, Part I, Haudouts from April 7th Status Meeting with NRC- / 4! Two Additional Resumes of Members of TPR Team e 3. Date: April 23, 1982 (No Cover Letter)
Subject:
TPR To: TPR Members Material Transmitted: .1 EdI-1 Steam Generator Recovery Program Task 7 .2 Reactor Coolant System Inspection and Requalification (April 16, 1982) B&W .3 Handout from NRC April 23, 1982 from N. Kazanas .4 Reactor Coolant System Review *ask 7 4/23/82 5 THI-l OTSG Tube Failure Probability from D. Slear 4/23 .6 OTSG-B E/C Absolute (4 x 1) Results Summary from D..Slear 4/23 .7 TMI-l GTSG Tube Making Process 4/23 1
.r- ,a ',s. S." 4. Date: May 13, 1982 Subj ect: Draft Minutes of First Meeting To: TPR Members _MaterialTransmitte[i: .1 OTSG Charter (Revised) .2 Preliminary Specification for the Repair .3 TMI-l Tube Preliminary Stress Report .4 (4/21/82) MPR Associates - draft Residual Stress Report .5 EPRI Reference Material (April 27, 1982) Memorandum Report April 1982EPRI Activities,in Support of T a. 'b. APPENDIX 1 Status Report 2/24/82 APPENDIX VI Laboratory Experience of Cracking of Mat c. (Other than IN600) in Solutions Containing Sulf erials ur Species e 5. Date:. June 1, 1982 Subj ect: Draft Minutes of May 20, 21 TPR Heeting To: TPR Members Material Transmitted: .1 Telecon M. Graham w/R. Jacobs (NRC) 5/24 re: .2 Memo: OTSG Testing Program 4/1/82 TMI-E3914 from D. SlearNRC Participatio e 6. Date: June 21, 1982 ~ Subj ect: TPR To: Prof. Arturs Kalnins _ Material Transmitted: .1 EPRI Letter: Status of Tasks Assigned to EPRI by GPUN Failure Analysis Task Group on 2/11/82 e 7. Date: July 2, 1982 Subj ect : TPR To: Prof. Arturs Kalnins Material-Transmitted: .1 Stress report Work by Jim Moore (Updated Copy) e 8. Dato: July 26, 1982 Subj ect: TPR To: Prof. Arturs Kalnins _ Material Transmitted: ,1 BAW - 10146 (October, 1980), " Determination of Minimum Required Tube Wall Thicknes's for 177 FA Once Through Steam Generators" 6 0 ll _ woup. o
P .suv,n.
- a.. - ~
e 9.' Date: August 10, 1982
Subject:
TPR 1 To: TPR Members Material Transmitted: 1 THI-1 OTSG Failure Analysis Report, 7/82 2 TMI-l CISG As-Built Tube Stress Analysis .3 THI-l OTSG Recovery I .4 B&W Evaluation of Tube Samples from EdI-l .5 Battelle final report on Failure Analysis of Inconel 600 Tubes from OTSG A and B of TMI-1 e 10. Date: August 20, 1982 l ' Subj ect : TMI-l UrSG Repair Safety Evaluation To: TPR Members idaterialTransmitted .1 TMI-l OTSG Repair Safety Evaluation e 11. Date: September, 1982 Subj ect: Minutes of Meeting l To: TPR Members Material Transmitted .1 Sulfur Cleanup Handout o .2 OTSG~ Logic Diagram .3 B&W Memo of July 30, 1982 from J. F. Pearson: Report on s Prequalification Charge Sizing.for TMI-l Steam Generator Tube Expansion .4 Kazanas Handout: August 9, 1982 TMI-l GTSG Task 4 Eddy Current Presentation to the NRC. e 12. Date: September 17, 1982 Subj ect: TMI-l OTSG Repair Process Description and Qualification To: TPR/CORB Members Material Transmitted: 1 Handout from September 15, meet -c '.in conjunction with i Foster Wheeler and Babcock 6 is',e x) with NRC. l e 13. Date: September 24, 1982
Subject:
TPR To: TPR Members O 6 O / ~/. - R /$asw" 4 's O 4
V s' ~ d -a..4.s..~d~:.._.., -w-c.m. c.w... ~ <s -~~,~~,e.c...., s s,- Inter-Office Memorandum 's MC-17so Dare March 29, 1983' Subject INSPECTION OF LEAKING PLUGS AND CORRECTIVE MEASURES To M. J. Graham Location The following is a summary of inspections and correctiv actions for the leaking Westinghouse-plugs which will answer e the NRC inspectors question regarding the subject matters: 1. The leaking plugs will be diatested prior to their re moval to obtain the actual wall-thinning in order to determine if any under-roll conditions existed iately after plug removal, the tube end and the I D Immed-if there are any cracks, surface of the tubes will be visually inspected t flaws, deposits or surface im-perfections. Engineering will evaluate the inspection with Westinghouse rolled plugs.results to determine if they can be If there.is no evidence. of surface imperfection or cracks in the rolled area of the tube end, the tube will be honed, cleaned and replugged with a new Westinghouse plug. the intentionally " Defective Tube Test"It has been justified by forential crack at 3/8" that a circum-the leak sealing capability of the rolled plug designedfrom the for TMI-I. These results were documented in }i WCAP Report - 10084. 2. It has been proven by the qualification test that when the tube was replugged after honing, resulted. Therefore, a leak tight -joint it is concluded that the leaking ~ . plug will be,. repaired by replugging;as_ described.above.j. .. ~ 4 sc. 7x'r OWp.Kr% &RO.*s '.; o x:,'~H ', WQq ')., f; 3. Should cracks o~r'longithdinal indicatioqs: be found'in th _ rolled area of the, tube 'e~ d n e instead of the mechanical rolled plug.ized as the alter ects ~ '4. Bubble and Drift Tests will be performed to verify whethe the repair is satisfactory. The backup repair method of r a leaktight joint is attained based on B&W's experie and test results. Lh-I ~C. K. Heat Transfer & Auxiliary CKL/atk Equipment Manager cc: J. J. Colitz D. G. Slear B. D. Elam H.A. Schmidtk //A ,,m. . = = = = 1.....,
_., - +.. ~ ~~ ,. -.. _ n m m - w w 3 W " = ^ \\, i . C. SIEJJL March 28, 1983 GPUN's acceptance standstd for CTSC plug velds for welder qualifi more stringent than ASME Section II Code since it is realized that th cation is sLze acasurement/cbeck on production welds is not feasible. e weld ance criteria for welder qualif(cations of DTSC stabilizer plugs are asCPON follows: The velder qualifies (i.e. weld 5 pluge consecutively) on a mocku a. restraint (e.g. access condition, face mash). simulate th p to ca.E.
- b..
. The test set passes the liquid penetraat test as per AStfE Section X t L III Code requirements. c. heeney (20) wcld faces upon sectioning be macro amined at 10I and then micro examined at lOGI for cracks, lack of fusion,.etc. It should be noted that the Code requires only macro *==Luation at 10X for cr only. CPUH does not accept lack of fusion, gross porosity or inclusions ack or any sharp notches in addition to the presence of any cracks. 4. The afnimum veld throat tion is based upon stress analysis data (and not on Code re T) for the actual weld. In the case of the modified design stabilizer plugs the minimum acceptable leak path / weld throat,is.027" (instead of .022" required for Section III & 11 que.lification). borizontal and vertical leg of the welds are measured to assure the In addition. consistancy of the welds. The above acceptance standard reflects very clearly. how it is more string ' than the Codo. Although ast speciff.cally stated in CPUN procedure (s), in ent practice. a welder is given only one chance for-requalification whereac the Code is open on the. comber of requalification tests. that the conservatism applied to the qualification acceptance criteria has a CPUH's position is more significant impact on the quality of production welds than relying on final-inspection to assure acceptable welds. (. ~ A question was taised by Mr. Lee on how CPmt assaces that the pcoduction m + = /:* e
- e p
l.,*., v J; /\\, wide have the mia r== thcost size (.027.* La this' case). The,. 1 mensweemrot' of the production wel4n by mondestructive means 'ts'not feasible veld.sLac ;. / -5 ; The Code Psalizes this ' sod therefore requires either visud or liquid pcoc- ~ f ~ trant test for final acceptance. linear indicatiocs open to the surface.A liquid penetrant test will reveal ~_ In the past twelve (12) onths, ' CPUN Laboratory has examined over 300 such velds and did not observe a crack or linear todication open to the surface. Therefoce, the usefulness of perforstog LP testing on the plug welds in the OTSC's Ls of questionable 'u. , actudly reduce the weld size.value.. It should be noted that during or beforc The writer believes that a chorough and careful visual ern=fnation of the production welds will y,Leid more meaningfu result than a LP test. l WM SES FSCtibq S. K. SAM i CC: R. Schmidt - C. E. Lee ED & CC BA 120012 /m.,. 7,.....: '..v.- s
- ~
g J (-. ,/ inter-Office Memorandum asse March 28, 1983 y p E Y OTSG StabLlizer Plug 9 elds - TEI-L
- o D. C. s. PAR Location Reading 1.
Introduct Lon: On March 25, 1963 Mr. C. K. Lee of Mcchanical Componcats contacted this weiter to discuss and review the weld acceptance criteria for modif Led B&W stabiuzer plug to tubc/ seal welds on the TMI-1 OT50's. This sibj ect was raised by Mr. Lee is context of the recent NEC audit ismae to provide ecgincccJog just Eficatloos oE postveld inspection being perforacd on OTSC stabilizer plug (modJfied design) welds at TKI-1. 2. Braluation mez!
Conclusion:
The writer upon evaluation concluded the follovizig: 1 The present CPUB requircments for welder qualification and postweld. a. Inspection meet the requLroments of.AsfE Section.XI Code. b. The CRIE welder qualification requirements, as discussed below, are more consetvative than ASKE Section II Code requirments. This con-aatvatism provides a greater degree of assurance tMt Code requirements will be met on cbc production welds, Histortcally plug veld qn,11itcation samples have not reve=14 rej ectabic c. - liquid penetrant indications. Therefore, assuring quality welds and minimum throat size on production welds is best a&ie*==ad by adequate weldee gaa.lification and not by the fine.l inspection performed. 4 Discussion (, g gg% ny 4 3g.. A7 3. j., a..!: y y itc.,J':. w n a.., m. j The abovc plug melds fall irithin the Jurisdiction. of AM Section Z{. 1MI-l j is caMtted to acecing the evquireweats 'of AS3E Section II 1974 edition up to vinter 1975 Addenda, alocc this Code edition does not 'a41rc=s tube. plugglog situation, the requirements of ASNE Section II 1980 edition up to shmer '81 Addenda is beiqg utilized by CPUH. The requirements of Sectioo II (1980) Code show that to qualify a WPS or a welder, five consecutively velded 'l 1 1 pings on a simLlar mockup with simulated physical restricticos must pass a
- l 11guld penetrant test followed by macro
--ination (lar) of twenty (20)
- )
resuitaut meld faces (aEtet cmtcing). Thcse er=f cuttoas shall show no cracks and the welds shall have a minimus' throat (or the minimum leaktse path) of 2/3X tube isn11 thickness. For the production welds the sane Code }j specifies a visual or, liquid penetrant examination as the final HDE accept- 'j . anee criteria before lesi test. - l II i
l r;,; f' -e:p,_ &, f. GENERAL PUBLIC UTILITIES-OT5G REPAIRS DATE 3/29/83 DATE ITEM-DESCRIPTION RESPONSIBILITY REQUIRED 1. Restoration Secondary Side A. Temp.' Chem. System 2. Ops OTSG Status . OTSG Level " A" - 576" . OTSG Level "B" - 571" wdl bc Elleal is.h . Ship Backing Plates for "A" Upper Manway. 4/1 . 3. Post Expansion . Felt Plug Blowing Device-Store at Reactor Bldg . Final Freepath - Blow Plugs from Top TBD .~ B&W Equipment 3/27
- . Revised B&W Proposal TBD
-4. Immunel Flush System . Revised Spec for Flushing T. Functions TBD L r 5. Tube Plug Stabilization A g.t. Y s
- rf T-wj
'8 usa. y/ul p as,J A y s o.. L
- 6.. Miscellaneous Items to Resolve 5
i .-Hydrogen Peroxide Tube Soak
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G. _g_ OTSG REPAIRS DATE 3/29/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waiting Documentation MNCR Responsibility 215-82 Plug Exploded at Wrong Area _of Tube B&W 345-82 2 Tubes Plugged Incorrectly 354-82 Documentation for Immunol-1st Batch Eng 426-82 Wire Brush B6-1 009-83 Immunol at Cold Legs -> @ 067-83 Endmilling to 40 mils 064-83 Holders for Stabilizers Removal W Rolled Plugs Two Explosive Plugs in One Tube g=m w_:}w l' .8.. Tube Endmilling Photos
- 9.. Rad Con Exposure Data (Based on SRDs) as of 3/28 W Plugging - 13.8 Man Rem i
" Exposure Estimate - 75 Man Rem Total OTSG Exposure _ since 1st Blast - 778.2 Man Rem Total OTSG Exposure since Nov 1981 - 954.4 Man Rem it. ' Bubble and Brip Test 6 W T*J ~ g
- 11. Cleaning of the Cold Legs Issue. Purchase Requistion for Vendor l
- 12. Anticipated Jumps l
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.,h W GENERAL PUBLIC dTILITIES OTSG REPAIRS DATE 3/30/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED -1.. Restoration Secondary Side -A._ Temp. Chem. System 2. Ops OTSG Status - .. OTSG Level "A" - 576" . OTSG Level "B" Full Wet Layup . Ship Backing Plates for "A" Upper Manway 4/1 3. Post Expansion / Felt Plbg Blowing ~ . Felt Plug Blowing Device-Store at Reactor Bldg . Final Freepath - Blow Plugs from Top ' 'TBD . B&W Equipment 3/27
- . Revised B&W Proposal TBD
. Issue Pmcedure for Felt Plug Blowing G. Kull 4. Immunol Flush System . Revised Spec for Flushing T. Functions TBD 5. Tube Plug Stabilization . Solution for Removing 9 Misfired Plugs 4 i 6. Miscellaneous Items to Resolve Ad sof . ~ Hydrogen Peroxide Tube Soak . lekeup Line Backflush STP N
1 OTSG REP AIRS DATE 3/30/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waiting Documentation MNCR Responsibility 215 Plug Exploded at Wrong Area of Tube B&W 345-82 2 Tubes Plugged Incorrectly 354-82 Documentation for Immunol-1st Batch' Eng 426-82 Wire Brush B6-1 009-83 Immunol at Cold Legs 067-83' Endmilling to 40 mils 064-83 Holders for Stabilizers - Removal W Rolled Plugs 8. Tube Endmilling Photos 9. Rad Con Exposure Data (Based on SRDs) as of 3/28 . W Plugging - 13.8 Man Rem 3 . Exposure Estimate - 75 Man Rem
- . Total 0TSG Exposure since 1st Blast - 778.2 Man Rem 725 4
. Total OTSG Exposure since Nov 1981 - 954.4 Man Rem 94,4 10. Bubble and Brip Test . Results of Drip Test at "B" ujM W ywwa Uu^ MQ/u > ymf
- 11. Cleaning of the Cold Legs
- 12. Anticipated J umps l'
Date Description Responsibility 3/30 A - Upper W@ Levin / Catalytic A - Lower - ': E : Y w u&uAf e
r; ( ~ f. GENERAL PUBLIC UTILITIES OTSG REPAIRS DATE 3/31/83 DATE . ITEM DESCRIPTION RESPONSIBILITY REQUIRED 1. Restoration Secondary Side - [. .A. Temp. Chem. System 2. Ops OTSG Status .OTSGLevel"A"-576"-[ ) . OTSG Level "B" Full Wet Layup . Ship Backing Plates for "A" Upper Manway 4/l '
- 3. -Post Expansion / Felt Plug Blowing
. Felt Plug Blowing Device-Store at Reactor Bldg . Final Freepath - Blow Plugs from Top TBD [oJD . B&W Equipment 3/27 d . Revised B&W Proposal-TBD . Issue Procedure for Felt Plug Blowing G. Kull 4. Immunol Flush System . Revised Spec for Flushing-T. Functions TBD h aan h 5. Tube Plug Stabilization J,)1 M 60 S/ Mwio,]m d . Solution for Removing 9 Misfired Plugs . Removal of W Plugs 6. Miscellaneous Items to Resolve g -fy . Hydrogen Peroxide Tube Soak . Makeup Line Backflush STP 9 I
.c '1. t. r 1,. _z_. OTSG REPAIRS DATE 3/31/83 DATE . ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waiting Documentation MCR-Responsibility 215-82 ~ Plug Exploded at Wrong Area of Tube B&W ?345-82.2 Tubes Plugged Incorrectly -354-82 Documentation for Immunol-1st Batch. Eng .426 Wire Brush B6-1 009-83'.. Immunol at Cold Leils 067-83 ' Endmilling to 40 m' ls' 064-83 Holders for Stabilizers Removal W Rolled Plugs 8. Tube Endmilling i Photos t
- 9. ' Rad Con Exposure Data (Based on SRDs) as of 3/30
. W Plugging 13.8 Man Rem . Exposure Estimate - 75 Man Rem . Total OTSG Exposure since 1st Blast - 794.7 Man Rem . Total OTSG Exposure since Nov 1981 - 970.9 Man Rem i 10. Bubble and Drip Test . Results of Drip Test at "B" l 4M P mw.dkm i NM N 3 aa %k dM bdr.
- 11. Cleaning of the Cold Legs
- 12. Anticipated Jumps Date-Description Responsibility 3/31 A - Upper W W
- N Levin / Catalytic A - Lower
'3/31 B - Upper - tal h h hIch 8 - Lower - l
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., ;e ;:,,. . f -- 3 ~ 4/4/83 to 4/5/83 r DAILY REPORT - UNIT 1 (1) PRIMARY PLANT' CONDITIONS Pressure O psi-Temperature '100*F (90-1100F) Cooling Mode DH Loop B Water Level' Primary side ~- OTSG's draineo; RCS at 10 to 15 inches above center line of cold leg - open to atmosphere OTSG-A . Nitrogen supplied - Drain to 572 OTSG-B Nitrogen supplied - Full wet layup (2) WORK FOR NEXT PERIOD A. RC-H-l's - Engr. 1. Radiation Exposure Rad Con (as of 4-4-83 0001) V.6 a. Total OTSG manrem since first blast - 821.318 Rem b. Number of company employees greater than 2000 mrem (year to date) - 92 11 High individual - company (year to date) - 2317 mrem NC ~ c. d. Total-0TSG man rem since Nov. 1981 - 997.507 Rem l001.7 Ti e. High individual - contractor (year to date) - 2.617 Rem 2.7 C G 2. OTSG-B (24 hours per day) a. Hot plugs / cold leg plugs installed J-leg covers installed - Taper plug to be installed b. Drip test (ft leakers) 1st NR - 21 tubes frfo plugs) - 1 B&W plug - determine where leak is at c. Felt plug blow - In progress 3. OTSG-A (20 hours per day) a. Hot plug / cold leg plugs installed J-leg covers installed b. Westinghouse roll plugs - In prpgress - 6 to remove (4 done) 't') n<7 - 231 tubes to plug c. 5 tubes to weld in upper 1 T dbv T MM B. Rad Waste Area - Ross 1. 4/4/83 (3-11) Rx Bldg. laundry g LWST area c. Neut tank room y Hydrolaser setup for przr inspection /2fp
l' E. EX Steam Defect - (MO-T-2C) =- l. Fix for pipe indication - CAT -O mu6 ,- Start work 4/5/83 2. Install insulation - CAT A 200-856/10-0469; purchasing Bids 4-12-83 F._ Decon Facility - Rad Waste Ops Repair weld leak - MM G.. Valve Inspection (RC-V-2/RC-RV-2) 1.- RC-RV-2 (all parts on site for reassembly) Fuhrer Parts at Batell (Analysis in process) (SP 1101-28-004) for cleaning - QC problem - Valve body - Intermediate Bldg. - Parts to clean 4-83 - Need criteria for PT/X-ray -- X-ray work (2 welds) 4-6 ' - PT work (2 welds and seat area) 4-6-83 - Reassemble WO 11-83 - Leak test - Pop test 2. RC-V-2 - Valve booy - Hot Shop - Wall thickness measurements - Q.C. - PT work - X-ray work 3. RC-V-1 at weld Engr - Weld leak off line (after przr inspection) 4. Przr inspection - Engr./Maint/ Ops g Mag particules test stucs (11 stuos) 4-5-83 a. Manway 1. %* Swf r+ a.amei -00 m 3. 1 stud clean in place and test b.' TV inspections Ar* c. n Entry 4-5-83 0700 p Preparation to take scrapes / swipes K Swipes - Highest point above MW - Scope in SP-1101-22-103 paragraph 4.4 .%p" ( :. Sludge sample from bottom of przr - Rad Con v f.1 A ;) q 4. Rad survey heater area - Rad Con r ad s t2.1 H GL W, (dC x0 IM A
F h 4 % 83 (3-11) L. River Water Interim Lube Water System - schedule M. Snubber Testing (10) - Shovlin bis lb 'l. MS-209 - Failed - need to install D 2. MS-211 - passed - need to install 3. FW-111 - passed - need to install N. DH-P-1A Repair - Harper Works daylight '- Replace / reassemble parts - in progress 0-ring (QC accept) - Concentricity readings - Run pump y p\\ fT gg
- 0.
Hayes Gas'02 Analyzer - Harper /Snyder - Install new pump 4/5/83 - Place in service P. WDL-P-14A/B Mech Seals - Shovlin - In progress Q. WDL-V-128 Diaphragm - Shovlin - Schedule 'R_ Task 8 F S~v%9 9 u ga s W (3) TECH SPEC CLOCK ITEM Hayes Gas 4-3-83 (7 days) 1400 (4) RELEASES NONE (5) RADI0 ACTIVE WASTE A. Limits on shipment - None B. Shipment past period - None C. Planned shipment h --t R. C. Troutman Ext. 8154 Document ID 0037K 9 .a
%g ,W m .m j , {e :?,fl i,- Ia L F duc ear m u E TMI-1 OTSG Repair and ? Return to Service L r L' 7.,u 1-b
==4 i ] NRC Presentation April 5,1983 L h' L- !] ^ i M7 _ = _. =, =
- - -. = - - - - g& at II r U n NRC Presentation 4/5/83 -b Agenda I L I 1.
- Introduction / Repair Status D. Slear C
- Overview of SER Logic
,r -
- Plugging / Stabilization Plans t
- Qualification Zone 8x1 ECT Indications
- ECT Future Plans T e e,
11.
- Leak Before Break D. Croneberger 111.
- Operational Guidelines G. Broughton L
IV.
- Support Systems Sulfur Investigations M. Sanford h
eSulfur Transport Mechanism
- Corrective and Preventive Actions Vi eStartup Program J. Carroll l
G p. m 0
G c_7 E3 E F--~i im E' F! r ~~' O TO r ~' E7 E' i -1 t - ~l E ~) ig 2J E E) LN- ) OTSG REPAIR PROGRESS GRAPHICAL SUMM ARY f ins \\ COMMENCE LEAK TESTING ggg FREE PATN/FlWAL CLEAN TUSES (FELT PLliGS) e s2 PLUS TUBES r 84 -FLUSN TUBES I 75 ' TUBE PLUGGING e iese = ese COMMENCE M 88 END MILL TUBES
- FREE E
888 A PATHING a g 7 4ee j '+#eTSG A-D-ls*TSG e O g 88 E l' ' tee s I g.* I = oRAIN IMMUNOL I p I E 52 -EJECT CANDLES (FELT PLUGS) fee I MAR I APR g ,/ E 44 3 5 2ND EXPANSION /,['/ t g as ,73,, T,SG A DRAIN IMMUN01 f PLAN (11/22/82) ~ EJECT CANDLES
- -*-- - ACTUAL (3/28/83) f
-(FELT PLUGS) 2e 12 IST START RCS EXPANSION CLEANUPt/ kwik 4 y U I.* I g g OCT NOV DEC JAN FEB M AR, APR MAY
7 m %y R n U Exposures from OTSG Program nU y. b Actual to Date - Additional Projected ~f RCS inspection 12 0 $2 Eddy Current Testing 35 10 t i: Pre-Repair Testing 5 0 w . [- Tube Sample Pulling Plugging and 120 0 ~ - Stabilization , h' Plugging and Stabilization i
- W plugs 75 l
.
- Stabilization 235 r
I: Kinetic Expansion r+
- Pre-expansion Preparation 16 0
l ~
- First Pass Expansion 188 0
- First Pass Debris Removal 132 0
T-
- Second Pass Expansion 167 0
L
- Second Pass Debris Removal 75 0
f' End Milling 125 0 i d Clean-up [^
- Flush 30 G
- Soak and Clean 30
- IndividualTube Cleaning 10-40' lA Testing l
- Drip Test 5
y, [
- Bubble Test 5
- Finalinspection and Turnover 5-10*
e-l Totals 855 405-440 1
- ltems for which planning is not complete.
E m B a u
.,a [3 Ea L_ci I:.: il ET LCl [ C. E7 C C C C'C C OC 1 PLANT RETURN TO SERVICE SAFETY EVALUATION OVERVIEW L-PLANT SAFE TO OPERATE FAILURE MEASURES TAKEN RCS & SUPPORTING STEAM NO ADVERSE MECMANISM TO PREVENT SAFETY GENERATORS-ENVIRON. UNDERSTOOD RECURRENCE SYS. UNDAMAGEO OPERA 8LE IMPACT
- METALLURICAL TESTS
- OX10lZE AND/0R
- RCS INSPECTION (N.E) e REPAIRS QUALIFIED e APPENDIX l (N.8)
REMOVE SULFUR (IV.C) - EXPANSION (V 4 VI) CALCULATIONS (XI.8)
- SUPPORTING
- CORROSION TESTS
- REMOVE THIOSULFATE SYSTEMS INSPECTION
- PLUGS (Vil) e ALARA CONSIDERATIONS (N.C & NI) (IV.A) (11.E) e PLANT PERFORMANCE (XI.C)
- PREVENT FUTURE ANALYZED (Vill)
CONTAMINATION (IV.A) e UNREPAIRED SECTIONS
- IMPROVE CNEMISTRY OPERABLE CONTROLS (IV.8)
-ECT DETECTABWTY ADEQUATE (IX.8) -CRACK PROPAGATION ANALYSIS (IX.C) i -FLAW GROWTH PROGRAM (IX.A) CORROSION TESTS (IX.A) e OPERATING PROCEDURES REVISED (X) e TESTING PROGRAM (APPENDIX A) - LEAK TESTS - COOLDOWN TESTS
v.$ L Ei Rd OTSG B { OTSG Post-Expansion Eddy Current Absolute (8x1) Results r [
Background
p-151 tubes kinetically expanded and E/C examined. Nine (9) L tubes were reported by 8x1 as having indications not seen by .540 S.D. k Results .c a f' ABSOLUTE NOISE LEVEL S.D. I ', Rew/Tebe Location Coil Volts Distorties 400 Base Mix c-4-19 US+11 1 .5 1 2V .6V 4-30 US+12.9 2 2 2 '~ 3-27 US+9.4 3 8 2 2V .6V 3-25 US+10.7 1 1 1 2V .6V ,[' 3-24 US + 12.5 2 2 2 2V .6V U 3-21 US+10 1 1 1 2V .6V 2-21 US+13.1 1 1 1 2V .6V 2-22 US+ 13.2 4 1 (MULTIPLE 2 1.SV .5V O '2-25 US+07 1 1 1 1.5V .5V y. 'New Kinetic Transition ~' h $kW hhf den o f-T ur3 d ~ p $Al~ S/4w) N/K.ef, /fa/~ wor e.f&sk a c % avs w i + nwe.u m n s u run. n ~. [fe kAdd 'N6 kr $7,9ArvHe 6"We un yugz h,e q b
- n J
m- . T} E ri E r, u OTSG A U OTSG Post-Expansion Eddy Current Absolute (8x1) Results i t. {r
Background
284 tubes kinetically expanded and E/C examined before and L a_fter expansion. Six (6) tubes were reported by 8x1 as having indications not seen by.540 S.D. Results - Absolute - - Level of Noise S.D. - Row / Tube Location ,Ggil, ,V.gits, Distortion 400 Base Mix AFTER EXPANSION 2-12 Not expanded .8V .4V _{' 8-43. US+4 1 1 1 .8V .2V t. 7-54 US+1 TO 1 1 (mutTIPLE) 1. .8V .3V US+10.7 r 4-4 US+ 0.1 1 <1 1 2V IV i 4-32 US+11.9 1 .5 1 1.8V IV 2-7 US+5.3 1 .5 1 1.2V .4V SEFORE EXPANSION
- 2-12 US 3 TO 1
<1 (mutTIPLE) 1 US+7 3 <.5 1 ^ '5-43 US+4 1 <1 1 j '7-54 US-8 TO 1 <1 (mutTIPLE) 1 US+13 3
- 'J r
L ext n.,.rtw 3 t.6u = hai iwintins b.v.r..x,.mi. \\ /,.,Ar3 U ST / L 7 i k o u r. & s a c rin t a w n o ~ n. ~l gyI %,wrz. -4oo,wr cdeu4 Sm deJe% re sdrierAt. I. k<ein G,oeuee fc ic - D i/
- r c A 4 M G c st/ t.eC 4,
q n hh0f fl l h b
y v$-A l o fu F: x nb m OTSG Post-Expansion Eddy Current I Fiberscope Examination Summary L" VISUAL SIZE (in.) ECT m [' DTSG ROW TUBE INDICATION LOCATION CIRC AXIAL C0lLS VOLTS 8 3 24 Line of Pits US+13 .01 .02 2 2 L 8 2 22 Area of Pits US+13 .01 .06 4 2 f L 8 3 27 Area of Pits US+10 .01 .03 3 6 8 2 25 Scratch US+7 >.05 j~; 1 1 A 4 32 No visible US+11.9 1 <1 ~ indications A 2 7 No visible US+ 6.3 1 <1 [j indications LJ n-l 1 ~* eg a
- u n
U
I
- g
.s c-U g L: = Ld l P L [] Kinetic Expansion O.ualification Length ECT Examination Conclusions 7w F (",
- Many of the indications are from pits or scratches
{' which are of no consequence. {"
- None of the indications have been identified visually as ID cracks.
F L F
- 2U r,
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- 1. 0 e
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3 O [2] [3].O UZI !.~ ~ 3 C EC", ~R C O It C U C Cl C3 C E I } vea rs l = us tut llf 1 TMI-1 TUBE PLUGGING / STABILIZING PLAN p /L g QV) m A Le49 [ / ANY OETECTABLE 10 INDICATION <48 SEFECT 248% TW PERCENT TW AND INDICATION _c-Sal >2 C0lLS i i u u l E u a a u N l 15TN SP TO LS-4 la ANY TUSE SPAN 1ETH SP T!I LS-4 IN 15TN SP T3 LS-4 LANE / WEDGE 15TN SP TO LS-4 US + 4 TO +8 AND NOT ISOLATED BY LANE / WEDGE 15TH SP TO US + 4 81 >2 Celts NISTONfCAL DEFECT Sul $2 cells LS -4 TO -24 BOTTORA 8" 0F HISTONICAL DEFECT AREA KINETIC EXPANSION AREA u$,pe. re w I I' I I I I i PLUG & STABILIZE PLUG AND PLUG ANO PLUG AND TO BOTTOIA 0F STABILIZE STABILIZE TO PLUG OllLY PLUs G;;LY STABILIZE T0 i 14TH SP THROUGH SPAN OF SOTTORA 0F 14TH SP ggges**/ gd BOTTORA OF 14TH SP DEFECT l )
7 9 G8 O Q t. f. c-tc _] f~ !~Tl O " T3 [..II Il O L2'l E'D C 3 e t
- .-f Lane / Wedge Area of Tubes to be Stabilized ROW o
se &3. TYPICAL OPEN LANE Mii@os. (NO TUBES IN THESE LOCATIONS) -coo +ococo. 2-NTELD N3co e ~ e No M D 'eeoeoeoeeee ee eDNMeYis -egggg+ **oo90'mmwopo+o*orecoccusep.oE>wmoce$- 4 77 2%v EWY 3 $?M'Mo9P* TU8E NO.15 TUBE NO. s3 -mo -60 ss g' 0F GENERATOR TYPICAL TUBE NO.1 y i e
= ~~ 3., OU S Tube Plugging Summary 9 (L Plugged NUMBER OF TUBES m j DESCRIPTION OTSG A OTSG B TOTAL ,q PREVIOUSLY PLUGGED 259 88 347 b OR STABILIZED ~ STABILIZED (1983) 395 89 475 m / g }? / PLUGGED (1983) 231 105 338 r r'! 'Y i TOTAL 885 273 1158 Yo g A f (.E i Remain in Serviceg _ tg atee g 6f p DESCRIPTION (<40% TW) qf OTS A OTSG8 T TAL lD,8x1 <2 COILS 3 14 17 ./ q i 1 I 3 -mm-.-.
F ' =7 R. o r-~ 7 r;'l n r H r 1 q gg ta d I C'3 L"Ei I.:) Cr I. ?.] G -!1! }' ~^ TMI-1 POST REPAIR ECT INSPECTION
SUMMARY
.y e s E TOTAL NUMBER OF TUBES [ DESC alPTION SCOPE PROBE BASELINE DATA 90 DAYS DEVELOPMENT k ? e 15 TUBES WITH PREVIOUS F MINETIC EXPANSION INDICATIONS Ox1 15 15 (8" QUAL LENGTH) I A$ JST /e<*/fd/ e 3% BASELINE /0TSG Ox1 830 930 wa onmesn,rCow!<rs. ( db W4g5AR e 10 PERIPHERAL /0TSG .540 SD* ~SO ~6O
- N, w
e 10 WITH DEFECTIN t (INSERVICE TUBES ig6gv5j 15TH, IOTH OR IST ADJACENT TO UNSTAOILIZED SPAN /0TSG .540 SD* ~120 ~120 g 4 jg PLUGGED TUBES) e 5 WITH.540 SD >3V .540 SD* ~50 ~60 'l E e DEFECT LOCATION 9x1 INSERVICE (<40% TW) o I e FULL LENGTH .540SD 55 86 y yo')/ Ary !"ga n 'E l e_ HIGH PLUGGING DENSITY e 50 FULL LENGTH /OTSG .540SD 100 100 h y i g STANDARD INSPECTION e 3% FULL LENGTH /0TSG .540 SD COMPLETED IN 1982 930 i h f TOTAL ~1350 ~2300 iy
- LABORATORY QUALIFICATION USING WEAR SPECIMEN COMPLETED z
2" e cInasemusen -
___..____.:;..._-.-..--...._____-._,-_-___=-a--,---------- 4 y s. f a i g 3 e OTSG Tube Leak Indication Before i !1 Tube Break Introduction j i p 9 l. PURPOSE: a m 1 L Provide the results of critical thru-wall crack sizes in OTSG tubes subject to MSLB and maximum cooldown loa' ding, '~ i[ establish the leakrate for critical crack sizes and to 3 '~ demonstrate that OTSG leakage provides indication of tube l [' cracks before tubes are subject to failure during cooldown ' j l trsnsients. j ~i.J = OUTLINE: j q 1
- Provide critical thru-wall defect sizes for MSLB and j
[ maximum operating cooldown. ]
- Provide results of crack growth due to mechanical effects.
2 2
- Provide single tube leakrate versus thru-wall defect sizes 3
based on tube tensile load. i j
- Provide the leakrate from critical thru-wall defects.
j Establish an operational leakrate limit. t 2 1 a l ^ ia 7 3
- .J a
f
,n a r 2 _ r - - ^^. ^^~ v A. D nk CONSERVATISMS: i N
- MSLB tube loads based on guillotine break with double ended flow through 36" M.S. lines (TMI-1 has 24" & M.S.
nozzles and can't have double ended flow). Cooldown less
- severe, f~
L.
- All leakage is assumed from only one tube.
- The single leaking tube is assumed to be in a location which'will produce the smallest leakrate.
OPERATIONAL LEAKRATE ' [' Lo e Measured leakage following post-repair testing [ establishes base line.
- Post-repair testing assures leakage from any single tube is small compared to leak rate predicted from I
leak-before-break analysis. fl S Guidelines for operational leak rate are a function of 6 GPH 7 increase from baseline leakage. ge,wp1 f fM 'l n C p p r CONCLUSION: 6 [ r Defects will propagate radially and result in leakage due to thr.u wall extent prior to propagating circumferentially to a u critical size. U A leak rate change of no more than 6 GPH assures that a normal plant cooldown can be accomplished and that a more .s U rapid cooldown due to a MSLB can be accomodated ithout A a tube rupture. D*" gpg a $pev* bo qP/ # /eJ c 3J B
= - - I LU a),r -lj. OTSG Tube Load Capability j/ r',g;# ' / y#y h 360 t / ff p b k0 1 h8 / e, [' "2 270 M; p - ASME Fatigue Curves [,, $l g 40 yrs, stress inten = 5 e Design Basis - 100 /h. -l ~
- % Design Basis r7 y
h? p f 'g L g f O L L[ i P u 180 L E U f, = iLi w cm n ECT S IIISITIVITY L 0.540 'lFF. P'R'O'B. 90 L' +40 yrs. A kth = 4 40 .Akth " 1
- c,:
NOT WIUllN Uts DETECT ED h = f e,[" 0 20 40 60 80 100 t, A cl (s m DEFECT TH'RDUGHWALL - % b l' 9< ,7pl g#/d,* bc n a w !o, s ,, J f 1 Q p p A T g$ u a6
= = = =
=
-.m-1 @ TOG Tubo CritiscI Crook Sizac r,U. 2.00 , 0.D. MAX ARC-LENGTH U 100*F/HR C00LDOWN \\ 2 \\ (w/140 F SHELL \\ \\ \\ 1.75 'g TO TUBE AT) \\ \\ (1107 W-(649 LBS) 2 ECT + \\. \\, \\ LBS) N) gd \\. \\ /MSLEl \\. Q\\ ~ e .Q NE +\\. MSLB 1.50 \\ ^ (3140 lbs) \\ (1408 lbs) ~ -s A \\,jhl* 'g 34 b'4 Cen/N IA< A 1.25 Mj g.'# gg5 cf fG, g E /H b ggO -3 y ECT + g 6 p g f h q s. e g 1.00 D^*# L,.eV )l tS hCMO \\ C 0' Li 706 \\ profs x ~ O g
- i Z
.75 pGS N V' 6 arl L.. Q M.# N,o - ~ N*? r(6'C I* 5 F, .50 J$ gg* '!.. I S 1 a/ 30,5 pS' p/ N ' 40' 1[e J .25 0 !.} l l I i a 0 20 40 60 80 100 l-DEFECT DEPTH IN % WALL THICKNESS 7 NOTE: 1) PERIPHERAL TUBES
- Y Nv
- 2) CORE TUBES l
'7/ cud Sfft SJ M4yS/i h 45<g A B g,p e4+ N*C.rraess, R .J
_= 9 ,J TMI-1 OTSG Tubes [ Critical Crack Sizes and Ope' rating Leakra te li .. TUBE LOCATION: CORE PERIPHERY Tube Load @ 100% Power (Lbs.) 200 (Tension) 500 (Tension)
- r. TRANSIENTS:
b -,1 - MSLis L Transient Tube Load (Lbs.') 1408 3140 7 (Tension) (Tension) Critical Crack Size (Inches) 1.28 0.52 Leakrate (GPH) .m @ 100% Power Operation 14 6 f 2 - 100*F/Hr Cooldown L u-(140*F Shell to Tube AT) Transient Tube Load (Lbs.) 649 1107 i (Tension) (Tension) ' l[ Critical Crack Size (Inches) 1.72 1.48 ~. " I? Leakrate (GPH) @ 100% Power Operation 22 72 t. I m c a ~ _.
s U g OTSG Leak Rate as a Function of t[ Crack Length & Tube Tensile Load n too L.: I 1107 # tension so p peripheral tube i,1 load @ 100*F/Hr Cooldown so .y,- 1 E 7o .[ E a; a. ~ S so =/ 500 # tension [7 { u. m Peripheral tube load Ie<f ! as @ Full Power 50 5 ) p I m 7 .E 40 t y i': ( 'L: \\. :\\ \\ 30 r-b 200 # tension t.' 2e
- 's.
f Tore 1ube load 4' ( hu-Power r t I evMc ~ g g'r 10 -- c f f "o -e g 'c pf a ( ,q h3 o' O.1 c.2 c.3 c.4 1 5.' O.s o.7 c.s e.s 1.o 1.1 1.2 t mg AcanM ocHcy mr murm ruel Ji TUBE CRACK OD ARC LENGTH (INCHES) [*'vY @ M8. ' J h k /[/ r P e m p }} ii ,.. ~ -. -.. - - ~ - - - - -,..
y c;; E-a n-$ { ) m CIn [Ti C3 PU - t n i r= Um L_, y, r
- ca m r, L t ri i r9
( @pcratcr Action 3 ca o Funstion cf Leakrate >l< PLANT SHUTDOWN PLANT DPERATING h y g EMERGENCY PLAN ACTION LEVELS ,s. I ALERT g j< UNUSUAL EVENT >g< i i g l. I l i PROCEDURES I g, , PLANT C00LDOWN 1 I 4-OPERATION WITH TUBE LEAKSh: TUBE RUPTURE % .1 1 50 J PRIMARY TO SECONDARY LEAK RATE (GPM) .001 .01 .1 1 10 100 1000 l pMAKE-UP TANK LEVEL l RATE OF CHANGE I MONITORING LT ' U METHODS >l %MAKE-UP FLOWH M TORIN LOW RANGE HIGH RANGE e [# l' / p ALARM ALA'RM H PI FLOW-->- i i OFFGAS MONITOR.h [p g o1 * /kmsryMdW'W l l 0 n'[4" op CorroEW5## l< UNUSUAL EVENT l< ALERT -+- l BATCH SAMPLE OFFGAS-->- g o o y,n e,.. L +
a q Steady State Monitoring Guidelines y ~ OPERATE AT .C STEADY STATE U POWER m j -) P MONITOR l..' LEAKRATE ACTION YES ACTION LEVELS AND LEVELS f '[~' RATE OF CHANGE EXCEEDED REDUCE POWER OR SHUTDOWN L OF LEAKRATE V c y, MONITOR LIMIT ACCESS [ GENERAL AREA YES INSTALL SHIELDING AREAS IF LEVELS REACH RA01AT10N y \\> LIMITS / LEVELS ACTION LIMITS { SHUTDOWN 1 r ) [l t MONITOR > j/ ALL NO TAKE CORRECTIVE SECONDARY .PARAM. A-ACTION PER l J f.- CHEMISTRY IN SPEC CHEM.PRDC. r ~ .g YES x y a /\\ TRENDS TAKE ACTION [" NCREASING, YES TO PREVENT TOWARDS/ EXCEEDING / SPEC LIMITS ../ ' V e l t b. Tja I p-- .,~n ,.... ~. -,. -....
^ b ' L. ^4' '5 > _ kl, l 5. g..~ 'E :.h' j + j Leakage Detection i . LOCATION METH'0D FREQUENCY. LIMIT ACTION I ON LINE l fj CON 0ENSER MONITOR CONTINU0US .5 GPH INCREASE TAKE BATCH' SAMPLE [ OFF GAS (Xe 133) IN 8 HOURS l< 1 GPM COMMENCE SHUTDOWN L ^I SAM LE 8 GPH (.1 GPM) PERFORM NORMAL SHIFT j (Xe 133 Xe 135 ABOVE BASELINE SHUTDOWN WHEN TRIGGERED r TOTAL GAS) / REACTOR PRIMARY COOLANT LEAK RATE EACH SHIFT .33 GPM INCREASE TAKE BATCH SAMPLE SYSTEM CALCULATION t i SE SURVEY EAC AIN MONITOR WHEN TRIGGFREO NONE ,NE (GAMMA) J i LEAK RATES ARE CALCULATED BASED ON RATIOS OF MEASURED SECONDARY ACTIVITIES TO RCS ACTIVITY )
ca is cia d ta m n.; r, rm r, ta r: <=3 r 3 mnm1 a g q f p ) . Radiation Monitoring. LOCATION METHOD FREQUENCY LIMIT ACTION. J P L D" P AND LUSH POWDEX VESSELS TWICE PER WEEK 5 MR/HR @ 10' MON TOR p0WDp ES E POWDEX RECOVERY PORTABLE TWICE PER WEEK 100 MR/HR @ 10' SYSTEM VESSELS MONITOR NORMAL SHUTDOWN t INCREASE l TWICE PER WEEK .5 MR/HR PORTABLE FREQUENCY TO DAILY i TURBINE BUILDING OR DAILY MONITOR PERFORM WHEN TRIGGERED 5 MR/HR NORMAL SHUTDOWN ( TURBINE BUILDING SWIPE WEEKLY 1000 DPM/100 cm2 By DECONTAMINATE l DRAINS 100 DPM/100 cm2 a DRAIN i I, i t i SECONDARY SYSTEM PORTABLE WHEN OPERATING SECONDARY ACTIVITY OBSERVE HP f VENTS AND DRAINS MONITOR VENTS AND DRAINS > MDA PRECAUTIONS 3 1 i
L o m
- t..a c. o Wp
.cm m ra c .~ 1 r-4 F 3 a . 39 r a r f3 ;. Throo Mils Icland Unit 1 j Turbine Building Liquid and Solid Waste Management During Operations with OTSG Leakage POWDEX --~& IWFS RELEASE ...s;. :.s....j'.. HIC / LINER p PROCESSING l SYSTEM i SOLIDIFICATIDN DECANT l CDNDENSATE l [ f STDRAGE TANK WATER RECOVERED l TO TURBINE BUILDING i ~7 -1_y - a SUMP ~~~~* 1 a ~ I TURBINE. BUILDING i IWTS RELEASE SUMP vz- ._e_, tte I L--__-_-_, l l 1 l PORTA RE STORAGE L.- - - -
- TANK
-+ PRD. CESSING DEMINERALIZERS I I
g. , i:2 au .D. Guidelines for Operation During r U Power or Temperature Changes e L Objective: I Reduce tube end loading to reduce [ leakage from existing cracks and to p.revent crack propagation d: f"1 L Limits: ~; The following limits will maintam V tube end loading less than 550 lb. u e L - cooldown limit 1.67 F/ min ..,g g - tube to shell L\\T 70 F l u [? Shutdpwn if leakage exceeds.1 gpm (6 gph) above E-r. baseline. b. n D 8~ n a ,. ~ _ _ _ _
.y$ - { ' Comparison of Existing to Proposed +b Pump Trip /Subcooling' Guidelines %a &m r, fg s pv p. 4 s: [x. k ~.... ~ - / .... _ ~...,. ~... ~..... * * * ~ s ~ i/ p
- s.,,
- i
....r 4 . _ _ _ ' ' ~ - s ...* '.... o...... r-
- ------------Y h
/ PSG,TC T"l l l l l ,g,,, "NN'y 60% n TEMPERATURE g. u ~ n A (current requirements): - 50* subcooling M - RCP trip on HPI actuation 3 p iss/A B-(proposed requirements): - 25 subcooling g 4,,, p #'f g E ,q - RCP trip on loss'.f subcooling [.!. Benefits: - RCP operation during larger breaks q D. - - Lower tube AP - Reduced leak rate .a. I N E
7- - .{}:..,. n 'Q 1: Break Flow for Single Ruptured Tube e, U 1050 i i i i 945 ss I il lli r, t 840 r I;; 735 i n.
- a.
a 630 7,
- =
th l!! l2 525 an. c, 3 420 rC 5 315 210 I: 25'F SC, PuliiPS 6N II: 50*F SC, PUMPS ON I 105 Ill: 50*F SC, PUMPS OFF - I' I l I ~~ u O 0 10 20 30 NI FLOW LBM/SEC a P = \\ w., Id n n ~[6 2 m n b
n. n-... :.,........;,. v a,..., m :..:... naaa.uu.:x.a.. :
- .uwa.w
&. e m u n. n. HGURE 3 i i Effect of RC Pump Operation on Integrated System Leakage for Single Ruptured Tube 180 I e, ISO 25 F SCM, RCP'S ON ~ --- 50 F SCM, RCP'S ON = E 50 F SCM, RCP'S OFF ~, 14e at es s-U e',#' /e/ 120 v 4 E o / ac / /p/,/ u.y 199 i 'I <w / i w / 50 ' / g E 80
- /'
~
- /
m p/./ / /,/'/ I 48 7 f' 1 o g a. i i. l I l I l 30 40 _ l 1 I.. . _I -- 110 so 89 10o TIME IN MIN 'Eill .G E L3J LE:, L1J-crj L?.O U~1 t 'J - La i; eel CUT E21 62.1 O EE3 EE3 i
m L!I [j Tube Rupture Guidelines t- {){[( g / 'l 0, Primary to / Secondary \\ / Laakage h ) > 50 gpm 'v' J( l 1 Manual Automatic ri i Shutdown. Shutdown ' bi w 3 x ? ? { Cooldown , j f gp/# ~ o f. M f" iI Forced Natural (HPl{ g//>/ 4_ g ( Circulation Circulat,on Toolmg gc i [ N L 1 86 ,4 4 Decay x Hut .u J Removal b New Guidance: ,0 - multiple tube ruptures - ruptures in both steam generators li - HPl cooling - Secondary water management P L-p p Improved guidance:
- \\d af f )[t({ b f
\\ kv 9 ,3 - Minimum subcooling reduced to 25 (i L - RCP trip criteria - tube to shell AT - steam generator steaming, feeding, flooding B C
~ 7 i -? u, E, e ~ C.C[i b3 I " .) ' L.. ;,j .) )' {1.., j ' - k .b) C) C J. -n f.- TMI-1 Sulfur T investigation & Resolution ,s 4 CORRECTIVE EVIDENCE ACTIONS e OTSG e 1979 PIPE CRACK e WDG PROBLEM CONTINUED ePORV RESOLUTION FOLLOW e RCS INSP. A 4 PREVENTATIVE 4 ACTIONS I I I I I L _ MECHANISM DETE3M! NATION A SAMPLING PROGRAM
7,_ .g'. s L 9 Evidence Relating to Sulfur Attack . ;.6 - r: ~ -(, e 1979 Pipe Cracking h -Through wall cracks in Spent Fuel Pool Cooling Pipe at weld H AZ -Extensive NDE program u~ndertaken c,W c; Total Welds ~S system Wolds Inspected u) SPENT FUEL 566 566 i7 DECAY HEAT 408 408 b BUILDING SPRAY 241 241 MAKE-UP 1061 897 CORE FLOOD - 31 31 4 REACTOR COOLANT SURGE 11 11 REACTOR COOLANT J SPRAY 28 28 (~ l -Disposition "l Periodic monitoring of 20 indications Remaining joints removed - replaced.with 304L e. f2! -Conclusion ' L' IGSCC of some HAZ's in stagnant, borated, oxygenated i9 stems pl h"j;g CU RO m n O = = =. ~ -..
Q,.; fj 1 3 Evidence Relating to Sulfur Attack p, 08 Q, Swne 1 .M
- Waste Dispo. sal Gas Piping - 1982 7
7 -Through wall crack on Aux Bldg side of WDG-V4 c.t -WDG piping examined between RCDT and MWST N L. Wolds Pipe segment Examined Indications U RCDT to WDG-V3 3 (U.T.) NONE n WDG-V3 to WDG-V4 11 (2 UT,11 RT) 4 WITH PITTING {' NO CRACKING WtiG-V4 to H0RRIZ. PIPE 7 (7 UT,4 RT) 4 CRACKS i, HORRIZ. PIPE TO MWST 7 (7 UT) NONE MWST DISCHARGE 17 (17 UT) 1 POSSIBLE CRACK h -Disposition ~ " [' WDG-V4 replaced 50 feet WDG pipe replaced with 304L i-1 Periodic monitoring of one weld d [7 -Conclusion u Localized sulfur assisted IGSCC in HAZ p:. u
- a:
.,?..,* 1 -. . {4 fN C) h a PU = _..: :-
r=. 4.,J. s .l.J I j Evidence Relating to Sulfur e Attack ( ePORV d e "N'*## W ) -PORV 1 (in service 4/76 - 4/81) - No unusual corrosion observed during 1979 refurbishment }.j General and pitting corrosion of Martensitic and inconel X-750 parts observed during 1982 refurbishment r; -PORV 2 (in' service 4/81 - 2/83) f/6 /
- G General and pitting corrosion of Martensitic and inconel X-750 parts observed during 1983 examination
{I Pure crystalline sulfur and sulfur compounds found on PORV body & parts -Block Valve [vf SMihu 1).l0Ab No unusual corrosion observed (no Martensitic or X-750 parts) J H!gh sulfur deposits present l5 -Disposition U Clean, inspect, and re-install block valve ww-j Clean & inspect PORV body; replace internal parts -Conclusion m
- 1) Damage mechanism existed after 1979 and prior to 1981 HFT as
.p well as during 1981 HFT E
- 2) Martensitic and inconel X-750 parts are susceptible to corrosion p'
- 3) Non-sensitized austenitic parts are not susceptible to corrosion
.0 'IID d
m qL g Evidence Relating to Sulfur Attack en
- d. '
j Pressurizer Area Valve Examinations 6.' VALVE SERVICE IN0lCATIONS RC-V1 PRESSURIZER SPRAY S DEPOSITS NO CORROSION {.- ' ~ ' RC-V17 PRESSURIZER VENT MINOR PITTING ,r ? L-RC-RVIA SAFETY VALVE NONE RC-RV1B SAFETY VALVE MINOR PITTING WDG-V1 RCDT RELIEF MINOR PITTING J !n Disposition: All corrosion indications are minor and do not ~ affect valve integrity or function. i r o;)
== Conclusion:==
- 1) Safety valves were protected by loop seal.
!3
- 2) Valves not in close proximity to pressuriz'er
) are not significantly attacked. e, L:j ..r. i ,i' a ui
- 0
, u.: i LJ i 1 -v ag w.. s
.~ ~.., - 3 {; Evidence Relating to Sulfur Attack fl Li g RCS Component Examinations P c0MPONENT AREA EXAMINED METHODS INDICATIONS L UPPER & LOWER HEAD PT,W NONE OTSG q UPPER & LOWER TUBESHEET PT W NONE 2"' MAKE-UP & HPI RT,UT NONE PRESSURIZER SPRAY & SURGE RT,UT NONE LEADSCREW V, W NONE rq CROM MOTOR TUBE UT NONE g END FITTING PT, M, W NONE RV N0ZZLE EC NONE m i INNER 0-RING M,PT,W NONE PLENUM LIFT LUG BOLTS UT NONE RV & PLENUM ASSEMBLY V NONE j PLENUM PLENUM CYLINDER BOLTS UT NONE INCORE DETECTORS & SHEATH F. PT, W NONE VENT VALVE TC N0ZZLE EC NONE TOP OF CORE & CONTROL COMP V NONE [. ; FUEL ASSEMBLY & CONTHOL COMP V NONE i;. RV HNS RETAINER PT,M NONE i INTERNALS CORE SUPPORT SHIELD TO BARREL BOLT UT NONE (O 0 LOWER HEAD & BOLTING RING V NONE BAFFLE PLATE REG:0N V NONE VENT VALVES & CORE SUPPORT SHIELD V, F NONE KEY: UT ULTRASONIC PT DYE PENETRANT V VISUAL OR VIDEO O W WIPE SAMPLE F FUNCT10NAL d RT RADIOGRAPH M METALL0 GRAPHIC n L.
== Conclusion:== p No general RCS component corrosion had occurred. e 'D l 9 7a \\
P %s Q; SIMPLIFIED - CONTROL ROD DRIVE MECHANISM F3 .o f]. u POSITION END CAP Q) INDICATOR U ASSEMBLY 4 MOTOR TUBE TORQUE TAKER D q r0 L:. p ~ MAGNET r~ f"' s TORQUE TUBE p ASSEMBLY 5 li s W c:: $ 1 SNUBBER ASSEMBLY c:: ' O .a A OR STATOR WATER '{ COOLING JACKET P L U SEGMENT ARM 4 PlVOT PINS s COMPEESSION }e' SPRING I. ROLLER NUTS La N W, s THRUST r r, BEARING
- .,7 I.
ASSEMBLY 1 LEADSCREW THERMAL BARRIER r; [:; ASSEMBLY REACTOR C 4 VESSEL l b HEAD {l 4 CONTROL RODS w .3 l l lNSPECTED COMPONENTS 7 J - _ =
.. p., O e w .I O Oa [. Inspections to be Performed Pressurizer Internals r L-
- Spray pipe & nozzle r,
- Shell lJ
- Ladder welds r
- Heater bundle L
1 RCS Piping o e Hotleg vent n
- Pressurizer vent L
L:,' Auxiliary Systems I. i e Make-up tank relief valve h & nozzle ' u e g 1s ('u r' 1 ' l[.I J
E13 EED EU E? CZ F. ~71 E;D F" ~'] i..' R '-] lE' '~l '.7
- 17 7
EJ t-5 ) f f SDDIUM TH10 l ^^^^^^^ owy"z:nz:zzz ^8WST x i ,y V/M[ AAAAAA' / l (, _- _ _-_ n 39, WASTE GAS f ( j n ruurs gggLDING SrRAY j ,-g l lll.
- Z'.
',',',',',"i 'h' l (VENT HDR) '"'"{f \\- O ( ) @,'kY//)((//j,BV//) W87/4 l l MISC WASTE I I I I p g im sutDimS g <oi.)- i m e th<._s /s p' E I ~ l4LALAL (kg.c Mo1 4 I ,f , ace Hri v ~ m Ih) M // s2 b a,$llff -WVV+ Q D uzzz'zz l M ~G-ut l j g??mes jg j ""'""'8 / /' s
- wvl'r'0; z(""""'"""' sur/unsuun n u u s u u u u i
..,,. u o,,, o - - cu. hINSPECTED N PUMPS {
fM ~ k ' fi A 1 ..) N3 R . L: rg' Corrective Action Summary. 77 ld 3, c. v: OTSG cr+ . a Kinetic Expansion Plugging PORV a Clean & refurbish (i t: WDG r. Replace 50 feet of pi'pe Replace WDG - V4 (.< u r' ! ~l LJ 9l.; Ye C [ 13 n !b rr = a a L-
y r k.c h U. Liquid and Wipe Sampling t w.': a' C WIPE SAMPLES y,. g:0 i .... d- > iiiUWST: 1
- !: : LIQUl0 SAMPLES
- .:..*.a.
. ~.... I L .f A WDL & WDG 4 f. i;iBulLDING 0:.. !!!6'iggij!!: b. iii! SPRAY:::::::*:+-* i ijj!HEATi:Y.STEliijl},- jiSYg,,T,Ep:j j j, r-1,2 PZR y c, / I OTSG ,J g .::5 O "I, CFT .::;.a. RC PUMP V T: J l r "C nC ra L
- NUCLEAR 0*
. iE9 9.;9 ?:0:0Nf0:0:0 ii. CHEMICAL
- l i:! ADDITION ::::
- !fi.gygg::::::::
!!!.Sy.$TEIF ::*::: p. 1
- :?:......,.:. +:
qy
- g..
^ p., i.ii.M..k. i.ti..U.p:....I, l.
- ..
- .. :.4:::..:.:.
- !iiPURIFICATib..:..,
e ii.SYS. TEM.ii,N!!! FROM ACS FROM RCS & OTHERS &OTHERS g i,u y v v y ,?.:. WNiy-....
- 0.: 3rAsy !:.,
(:.:.:.:. iD EMiN..l.0.: !!!! WATER *0.:.0.: La. ,.:0.:.. P0 SAL:...%.0.:. D. iSPOSA.. !!' m, . LIQUIDj.. !! SYSTEM 0:0,
- l0::
- 0:+:.
- ::: SYSTEM l0::
- 3YIT..E..M..':i:
r-f-} v L flu L
r4s b a Ru P I- !p Sulfur i[ Transport & Corrosion Mechanism o OTSG Tube Cracking (review) !F G e ID initiated stress assisted IGA
- Temperature + oxydation potential + sulfur +
r. potentially aggressive form
- Sulfur co,ncentration mechanism + oxygen +
l cracking on draindown Lp PORV Pitting and General Corrosion & WDG Cracking
- Gaseous sulfur compounds are transported from liquid r:
phase L, o Condensation areas result in potentially corrosive ) H local concentrations e Corrosion occurred at low temperatures .p ~O (? L e f'b .m 1 bU
y s s yO Pd Susceptible Materials & Conditions a U Rb CRACKING GEN CORR OR PITTING 7., 4.. L: SENSITIZE 0 AUSTENITIC MARTENSITIC STAINLESS {! MATERIAL STAINLESS OR HIGH DR INCONEL X-750 NICKEL ALLOY c:
- 1) EXPOSURE TO GASEOUS h~
FORM WITH A CONDENSING
- 1) EXPOSURETO GASEOUS CONDITIONS SURFACE.
FORM WITH A CONDENSING SURFACE [,
- 2) EXPOSURE TO A CONCEN-TRATION MECHANISM l
J [1 ,~ Conditions NOT Associated with Attack r. b o Non-sensitized materials
- Flooded & flowing piping j
- Piping drained well after shutdown Pu u
7 ', ? d T L
c_ 7..,t s nb S Preventative Actions ti J Eliminate Sulfur Source
- Sodium thiosulfate tank eliminated a
- Monitor chemical additions J.
m Clean Residual Sulfur d -* Hydrotaze pressurizer ~
- Peroxide clean: Reactor Coolant System Decay Heat System 7
Make-up and Purification System a n Prevent Recontamination i j
- Sample storage tanks to assure quality j
- Monitor building spray and fuel pool cooling d
Propide Continued Monitoring
- Daily RCS sulfur samples i
d' l -.7 .J. 7 i t = .=
7.g: 3 d
- j m
Ib TMI-1 Sulfur investiga. tion J 2 Conclusions J
- 1. Sulfur phenomena is understood fr.om full spectrum of studies.
aA -. 2. Sulfur related damage has been or is being located and repaired u as appropriate.' n L
- 3. Recurrence potential is minimized by system modifications, system cleaning, and chemistry control.
L
- 4. Chemistry monitoring will provide rapid detection in the
.2 unlikely event of recurrence. M a J n. d i n
- U
- C u
>-::. u=e- ,-_:le.._.__-..- - -. - - - - - - - - - - - - - - - ~ ~ - - - - -
- =__:_-
ps IJ y TMI.1 Restart Test Program 7 Purpose 'l[ e To provide a deliberate, methodical well planned verification of proper modification installation and performance in accordance with design e Verification of the adequacy of the OTSG Tube J Repair Program by operational leak testing and } on-line monitoring throughout the test program e Determination of plant transient response characteristics and verification of acceptable integrated plant operation with modified [] systems / components r. e Verification of acceptable system readiness and p; plant operation with new and modified plant k operating, surveillance, emergency, abnormal ll and maintenance procedures e Performance of sufficient modified ] system / plant steady state an'd transient operations to provide operator training and familiarization with modified system / plant m response throughout a range that he is likely to a ,a experience during the design life of the plant J l i C Yh
c m o .ga ^ l TMI-1 Rootcrt 4 Test Program j including OTSG Repair - l COMPLETE OTSG OTSG RESTORE FILL A RCS OTSG DRIP BUBBLE ECT. RCS_ VENT H02 +A REPAIRS TEST TEST 2 RCS CLEANUP - ~ I l g ' bA&f /*A h ? lldAO fo //dattAM l SEC. PLANT READY TO I SUPPORT I HEATUP l
- 1 i
? ESTABLISH OTSG/FW HEATUP OTSG HOT ZERO COOL AH CHEMISTRY FOR OTSG HOT TEST FUNCTIONAL PO DOWN TO SUPPORT HOT TEST AND SOAK TESTING PHY ICS 48 HEATUP TESTS i
- 3 4
'2 9 NATURAL POWER RETURN OTSG ay CidCULATION ESCALATION TO 100% EDDY TESTING TESTING ~ 90 DAYS TEST p
- Formal Management Review I
i 40% 75% 100% e e e i
rz(9 t r 3 u -r a c a ta rm at a t i E + Lt >r a1a in J-rn cr1 @TOOTesting L*'-} ' DRIP / -l 'l l l l l Nr l RCS I I 8 j l THERMAL SOAK i THERMAL SOAK-l' THER BUBBLEi SULFUR j -k TEST l CLEANING i 600 I i I l l l e "g .l l i 500 2150 psig 400 -] I' pd (to -90*/hr geef fe < N'""4 300 fe ll' W )lY' N g u 200 N" -*- TO HFT 100 300 psig l l t I l ,' ~ 1, TIME 1 ~4 WKS l ~4 WKS l DURATION , WK l 3 I i 1 SG TEST TUBE 8 + - HOT, PRESSURIZE 0 INTEGRAL SG LEAKAGE i LIAKAGE l . CORROSION ARREST i DBJECTIVE REPAlR JOINT /TU8E STRUCTUPt.i. 8 i 8 l l l - EFW SPRAY / TUBE iiESPONSE l t i MEASUREMENT! l l4 LEAKAGE >l 9 i l l l
g o e o aw m o t. t -4 E; e si t j t. rmt E1 E3 eel a -@TuS Tcctina 3 3 !g during HFT & Power Escalation yt J QJ (/ 't STO l' I 8 i HFT & O l OWERl LOW ! 40% POWER OWELL lj 75% POWER OWELL lI FULL POWER i POWER P {i-100 i elt t i i i e l 8 $j ECT - 90 DAY 75 l l 1 e i 1 p$ B 50 i l ? E 25 g l M 9 / TT I FEE 0 1 TURBINE l TRIP I i l TRIP TEST OURATION i ~2 WKS l-1 WK ~4 WKS ~4 WKS l 1 I l 1 SG TEST - CORROSION 8 - CORROSION ARREST I - CORROSION ARREST l - EFW/ TUBE RE l - TUBE VlBRATION l - TUBE VfBRATION
- - CORROSION ARR'EST OBJECTIVE iARREST l
- NATURAL CIRC l I I-l TRANSITION I l l TUBE VIBRATION l 8 I I I I I I i i MEASUREMENT. j c LEAKAGE
- ADJ FOR STABILITY I
f3
br , ;, TT
- x
..ft.. 8 so:w ?*coude M Q GENERAL PUBLIC UTILITIES Ul bb Kt.FAIK5 DATE 4/6/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 1. Restoration Secondary Side [ -A. Temp. Chem. System 2. Ops OTSG Status- . OTSG Level "A" - 576" . OTSG Level "B" Ful1: Wet Layup . Receive Backing P1ates for "A" Upper Manway 4/4 - 3. ~ Post Expansion / Felt Plug Blowing . # of Tubes Blown 9 " A" ---- . # of Tubes Blown 9 "B" 2533 MS/ e-B&W c.Jahn 90% . # o f Tubes Bl ock e d 9 " A" ---- . # of Tubes Blocked 9 "B" 12/t(, B&W 4 4. Immunol Flush System . Revised Spec for Flushing )Y i g "GM p 5. Tube Plug. Stabilization A . Removal of W Plugs . 5 StabilizFs in "A" upper B&W . Reroll Tube "B" upper thbe. Westinghouse - 1% kkes md4 4 AW *II V * * - - ii - 6. Miscellaneous Items to Resolve . Hydrogen Peroxide Tube Soak. . Makeup Line Backflush STP F. Paulewicz 4/5 ~ /27
.?; o f~ .g OTSG REPAIRS DATE 4/6/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waiting Docum' ntation = e p MC R-Responsibility 215-82 Plug Exploded at Wrong Area of Tube QC 345-82' 2 Tubes Plugged Incorrectly E.- 354-82 ' Documentation for Immunol-1st Batch' QC 426 Wire Brush B6-1 009-83 Immunol at Cold Le<p 067-83 'Endmilling.to 40 m' 1s QC 064 Holders for Stabilizers QC 073-83 Explosive Plug that fell out QC 8. Tube Endmilling. Photos d '.*9 Rad Con Exposure Data (Based on SRDs) as of 4/4 ..- W Plugg'ing - 13.8 Man Rem . Exposure-Estimate --75 Man Rem es7. tr . Total OTSG Exposure since 1st Blast - 821.3 Man Rem . Total OTSG Exposure since Nov 1981 - 997.5' Man Rem 10o3.9 [10. Bubble and Drip Test .f % .. Receive Hard Rollers J. Martin Week of 4/18 . Bubble Test Procedure
- 11. Cleaning of the Cold Legs
- 12. Anticipated Jumps Date
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.1 r '... ~, I GENERAL PUBLIC UTILITIES 0TSG REPAIRS DATE 4/7/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 1. Restoration Secondary Side A. Temp. Chem System 2. Ops OTSG Status . 0TSG Level " A" - 576" s 72 . - OTSG Level "B" Full Wet Layup . Receive Backing Plates for "A" Upper Manway 4/4
- 3. ' Post Expansion / Felt Plug Blowing
. # of Tubes Bl own 0 " A" ---- . # of Tubes Blown 0 "B" 3685 6 Kesi B&W . # of Tubes Blocked 0 "A" ---- . # of Tubes Blocked 0 "B" 12 it . # of Tubes Unreachable at "B" 18 . Receive Heapa Filters TBD 4. Immunol Flush System . Revised Spec for Flushing PMA ]M sT30g's 5. Tube Plug Stabilization . Removal of W Plugs 4/6 i . 5 StabilizFs in "A" upper B&W . Rerulled Tubes "B" upper Westinghouse 6. Miscellaneous Items to Resolve . Hydrogen Peroxide Tube Soak . Makeup Line Backflush STP F. Paulewicz 4/5 .. n ; 7 :- mg - s W 4g l E '#bb l /29
~ l 1 2-OTSG REPAIRS DATE 4/7/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waiting Documentation MNCR Responsibility 215-82 Plug Exploded at Wrong Area of Tube QC 345-82 2 Tubes Plugged Incorrectly QC 354-82. Documentation for Immunol-1st Bitch QC 426-82 Wire Brush B6-1 009-83 Immunol at Cold Legs 467-83 Endmilling to 40 mils QC <064-83 Holders for Stabilizers QC 073-83 Explosive Plug that fell out QC see 8. Tube Endmilling Photos 9. Rad Con Expsure Da+a (Based on SRDs) as of 4/6 . W Plugging - 13.8 Man Rem 21.9 . Exposure Estimate. - 75 Man Rem . Total OTSG Exposure since 1st Blast - 836.7 Man Rem . Total OTSG Exposure since Nov 1981 - 1012.9 Man Rem 10. Bubble and Drip Test N M "$ . Receive Hard Rollers J. Martin Week of 4/18 . Draft Bubble Test Procedure 4/6 1]. Clea of th Legs W Jio
- 12. Anticipated Jum s l
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y 7 f. v: + iy 4 GENERAL PUBLIC UTILITIES OTSG REPAIRS DATE 4/11/83 DATE ITEM -. DESCRIPTION RESPONSIBILITY REQUIRED 1. Restoration Secondary Side A. Temp. Chem. System 2. Ops OTSG Status . OTSG Level " A" - 572" . -0TSG Level "B" Full Wet Layup 3. Post Expansion / Felt Plug" Blowing .. # of Tubes Blown 9 "A . # of Tubes Blown 9 "B" 6304 7G B&W . f of Tubes Blocked 9 "A" ---- . # 'of Tubes Blocked 9 "B" B&W . # of Tubes Temporarily Unreachable,~ . Receive Hepa Filters 4/8 - 4/12 -4. Immunol Flush System . Revised Spec for Flushing . Samples From Filters TBD 5. Tube Plug -Stabilization . Fab Tool for W Plug (Removal 4 eel beeks. D. Harper 4/9 . Removal of W 1rlugs t # s. dae) 4/6 . 5 Stabilizes in "A" upper B&W All Abibws one. % euept ag
- 6. - Miscellaneous Items to Resolve
. Hydrogen Peroxide Tube Soak . Makeup Line Backflush STP F. Paulewicz 4/5
- 7) W A>eg, B %d 13 M JM AM dA. dwd.
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.r.,*. .), OTSG REPAIRS DATE 4/11/83 DATE ITEM DESC'lIPTION RESPONSIBILITY REQUIRED 7. Waiting Documentation MCR Responsibility 215-82 Plug Exploded at Wrong Area of Tube QC 345-82 2 Tubes Plugged Incorrectly QC 354-82 Documentation for Immunol-1st Batch QC 426-82 Wire Brush B6-1 009-83 Immunol at Cold Legs 073-83 Explosive Plug tnat fell out QC 8. Tube Endmilling Photos 9. Rad Con Exposure Data (Based on SRDs) as of 4/6 . W Plugging - 21.9 Man Rem . Exposure Estimate - 75 Man Rem . Total OTSG Exposure since 1st Blast - 836.7 Man Rem . Total OTSG Exposure since Nov 1981 - 1012.9 Man Rem 10. Bubble and Drip Test . Ship Hard Rollers J. Martin 4/19 . Draft Bubble Test Procedure 4/6 . Receive Spec for Hard Rolling T. Functions TBD DJp 4M - A 4e M I!oo 11. Cleaning of the Cold Legs . Issue Change Notice to Contractor S. Levin TBD Pa k..
- 12. Anticipated. Jumps Date Description Responsibility 4/11 A - Upper - 6 M /4c. g Levin / Catalytic A - Lower -
4/11 B - Upper - B - Lower - p) ty. ,. -., - - - - -.. ~
Jy7- . se GENERAL PU8LIC UTILITIES OT5G REPAIRS DATE 4/12/83 DATE ITEM DESCRIPTION RESPONSI8ILITY REQUIRED '1. Restoration Secondary Side . Temp Chem. System S. Levin' TBD .2. Ops OTSG Status . OTSG Level "A" - 572" . OTSG Level "B" Full Wet Layup '8' A 8 Ed % -3. Post Expansion / Felt Plug" Blowing . # of Tubes Blown 9 "A . # of Tubes B1own 9 "B" 9836 B&W . # of Tubes Blocked 9 "A" ---- . # of Tubes Blocked 9 "B" 20 B&W . # of Tubes Temporarily Untwachable at "B" 202 . Receive Hepa Filters 4/15 ,... m 4. Immunel Flush System . Revised Spec for Flushing . Results of Samples From Filters 4 4 &&#r, T80 i 5. Tube Plug Stabilization . Removal of W Plug ~ in "A" Upper 4/6 . Resolve 6 CRs from W Eng. T80 Y & es. --l 1' f 6. Miscellaneous Items to Resolve . Hydrogen Peroxide Tube Soak . Makeup Line Backflush STP F. Paulewicz 4/5 1 e l l /4/
.] OTSG REPAIRS DATE 4/12/83 DATE ITEM DESCRIPTION RESPONSIBILITY REQUIRED 7. Waif.ing Documentation MNCR Responsibility 215-82 Plug Exploded at Wrong Area of Tube QC 345-82 2 Tubes Plugged Incorrectly QC 354-82 Documentation for Immunol-1st Batch QC 426-82 Wire Brush B6-1 009-83 Immunol at Cold Legs 073-83 Explosive Plug that fell out QC 8. Tube Endmilling Photos. 9. Rad Con Exposure Data (Based on SRDs) as of 4/6 . W Plugging - 21.9 Man Rem - 48 a--- Exposure Estimate - 75 Man Rem Total OTSG Exposure since 1st Blast - 836.7 Man Rem Total STSG Exposure since Nov 1981 - 1012.9 Han Rem N4 Ag as-mo le. Bubble and Drip Test Ship Hard Rollers J. Martin 4/19 4 Draf t Bubble Test Procedurs 4/6 Receive Spec for Hard Rolling T. Functions TBD STP for 3 Leakers in "B" TBD Install Stoppers for 3 Leakers in "B" 44Jh M m ~Ak d i
- 11. Cleaning of the Cold Legs Issue Change Notice to Contractor S. Levin TBD
- 12.. Anticipated Jumps Date Description Responsibility 4/12 A - Upper - se 635/wslalds Levin / Catalytic A - Lower -
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r.] / N PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I PRIORITY ATTENTION REQUIRED 4-18-83 TZ: James Blaha, Chier, Program Support Branch, IE FROM: James M. Allan, Acting Regional Administrator, Region I Licensee /racility Notification / Subject Description or items or Events DPRP Ginna SRI rax Daily Report 4/8 Update. The licensee has completed a sampling UT examination 50-244 or reedwaster ring "J" tubes in the "B" Steam Generator (S/C). Results indicated wall loss similar to that identitled in the "A" S/G. The Ilcensee intends to cut out all existing carbon steel "J" tubes in both S/G's, and replace them with -~s inconel "J" tubes. Work is expected to start in ea rly May. Sho reham SRI rax Representative Markey will be holding hearings on Long Island on Emergency 50-322 Planning Regulations and Requirements as they apply to Shoreham. Expected to testiry: Gove rno r M. Cuomo-S Dircks,enator D. Hoynthan; County Executive P. Cohalen; NRG starr members, W. G. Cunningham, J. Snlezek, R. Blond. Susquehanna ENS call The licensee reported that Reactor Dullding ventilation isolated and the Control Unit 1 Room Emergency Outside Air Supply System (Creoass) Initiated while the licensee 50-387 was transrerring the Molsture/ Separator f rom the Reactor vessel to the storage a rea. The transfer caused radiation levels at the Refuel floor exhaust monitoe channel "A" to peak at 6 millires/ hour with the trip setpoint presently set at 5 mill f res/ hour. The Isolation occurred at approximately 00:15 a.m. on April 17 and was reset by 00:20 a.m. The licensee is continuing to isolate the source of the noise that was being sensed by the Loose Parts Monitoring System. Limerick There will be a SALP Board Meeting today at 2:00 in the regional orrice to Units 1 and 2 evaluate licensee performanet in the operation of Limerick Generating Station. 50-352/353 Three Mile island 4/18 SRI rax/ Late on April 15, 1983, the Ilcensee completed a leak tightness test at 150 lb. Unit 1 Dnce Through Steam pressure (drip test) on both "A" and "B" OTSG. The "A" OTSG appea red to have 50-289 Generator (OTSG) 15 tubes leaking while the "B" OTSG appeared to have 22 tubes leaking. The drip Tube Degradation test was conducted at this time to obtain an indication of the number or tubes Update that are leaking arter kinetic expansion. The licensee plans on conducting a nitrogen bubble leak tightness test af ter the completion or final free path check of all tubes and selected Eddy Current Testing. Preliminary plans Indicate that tubes which were round to be leaking will be mechanically hard rolled to form a new leak tight sea t. The licensee is on schedule for Hot functional Testing in the late part of May 1983. J
2; = A,, c 2, : SEDelillIIG REP 00ti - ItEGICII I 4-18-83 1 Licensee /fsellity IIetification/ Subject Description er. Itses or Events DestP (cent'd) Three Mile Island 4/18 SRI fax / -On April 15, 1983, the licensee reported the failure 'or a bearing on one Decay. Unit 1 Prompt Iteportable fleet Removal Pump (DN-PIA 50-239 -Occurrence ~ metion ledicates leproper,oilLow Pressure injection System). Prei seinery infor. level subsequent to the. Instellation or a remote oil. system. The licensee considers this reportable per. Technical Specification-6.9.A.9. The redundant pump was operable, ,q DETP Sales 4/18 Itsti rex / At about 4:30 p.m., '4/16, workers exiting containment were Found conteelneted ~ ~ Unit 2 Airborne Radio-a round the nosa l a rea.. Grab sempt ing or containment air et 5:00 p.m. .50-311 octivity in Primary indicated Cobelt-58, 60 and peongenese 54 at about 41.7 times Appendix s Containment limits. The activity was apparently stirred up by air currents while conducting vibration testing.or a reactor coolant pump motor in the vicinity of Steen Cenerator 22. Other workers in the stese generator were removing a broken nozzle dem stud free the hot leg. An airborne cleanup system used during this work ws. Found to be out-of-service. Containment access was restricted. Or 200 workers who had been in containment during the period, ' 150 have been given whole body counts as or 7:00 a.m., 4/18. Sixty-seven ; sustained low latehes of radioective esteris ts. (The highest was $5 or.10 CfR 20 quarterly limits.) Local media interest was high. ;The resident ^ Inspector and a heelth physics inspector were dispatched to the site.. . Pfl0-83-32 was : Issued 4/18 for inforestion. C'
T111 - DRAFT MORfCMG REPORT -- REGION I April 12, 1983 ji}} i r l'icensee/Facili ty Notification / Subject Description of Iter. or Event i Three Mlle Island Fax from SRI 4/12 During the past week (4/4 - 11/83, the licensee Unit 1 Pressurizer Entry completed various evolutions assoc)iated with the DH 50-28g Pressurizer Internal Inspection. Before hydrulazing the internals, visual, video white), and photographic (color) surveys o(black and f the pressurizer internals were completed along with O radiological surveys and tt C ..;-e' surface N
- ng samples for laboratory analysis.
Subsequent to W hydrolazing, additional visual, video, and photographic- ) surveys were completed. 3 g On initial entry, yellowish deposits (purported to be sulphur) were noted near a vent nozzle and on a U-Bolt (spray nozzle support) at the dome of the pressurizer. Small arounts of a red deposit sulfide) were noted on the press (urizer internal, purported to be fron surface. noted on the heater banks.Smallamountsofa,rustydepositwerg !% y/sf !! rp;: rs Itydrolazing was effective in removing the yellowish and rusty deposits and most of the red deposits on the walls of the pressurizer. O, \\ L'\\ C AT ~ As expected, general area radiation levels were an increasing gradient fror.: 5 mR/hr (gansia) at the ~ manway at the top of the pressurizer to approxinately 500 mRfhe (gamma) at the bottom of the pressurizer. Pcelini..y uusi.,chy dato i.miw i.c3 dia i unuse o;.o gad the precurher r&ci,ed exgsu e> w.G.... HE ..-u. The resident inspectors followed licensee work activities and visually inspected the pressurizer internals. e e J}}