ML20128M649
| ML20128M649 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/16/1993 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20128M638 | List: |
| References | |
| NUDOCS 9302220237 | |
| Download: ML20128M649 (125) | |
Text
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OWNER'S DATA REPORT FOR INSERV1CE INSPECTION < EDWIN I. -1LWCH NUCLEAR PLAN 7? ' c
,,- M UNIT 2 ho- .
SEPTEMBER 1992~- NOVEMBER 1992
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'I.- ASME NIS-1/ FORM AND.SUPPLEMFNTARN INFORMATION ~1-8 p . i
^ II. ABSTRACT. 9-18' it III. EXAMI:1ATIOli
SUMMARY
A. (' LASS 1 EXAMINATIONS : 19-53 '
, B. CLASS.2 EXAMINATIONS 54-61:-
C. PRESSURE TESTING - 62-641 D'. COMPONEUT SUPVORTS i5 '65-85 , J. AUGMENTED EXAMINATION '.86-99 ; F. REAC.I'OR FMECSURE VESSEL INTERNALS- .90-92 G. REPAIRS.AND REPLACEMENTS 93-12*= "* l AV. CODE CASE SIIMMARY 122 u j%- - t ,- p
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Mh q%- ): ._[ NOTE:- 'Portiona of this report are-compiled from Southern huclear' Operating ll . Company _ issued. report; " Nondestructive Examination Of Selected -91 ant '.-1, p 2, and 3LComponents",-for.the Fall-1592 Refueling Outage-at E.I. Hatch: L- Nuclear Plant, Unit 2. This' report is available,for' review:1n the- ' q Records Nanagement Department at the plant _ site. l i I i
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"q" V ).- LLST OF " AGBREVIATIONS = -E ANI/ANII- Attthorized~ Nuclear'. Inspector /AuthorizedLNuclear. Inservice , Inspector ~ . ASME ~ American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing: BC Br6nch Connection - _go ,, BWR- Boiling Water Reagpb,r. z_ CH Closure Head CONT Containment # CPI Containment Purge and.Inerting System; - CRD Control Rod Drive System CS Core Spray System ; CU Clean-up C&L- Cramer and Lindell Engineers
-DCR Dasign Change Request ECCS EmergencyLCorel Cooling Systems ET Eddy Current Examination-EPRI Electric Power Research' Institute-FB Flange Bolting . ._
FPC Fuel Pool Cooling System ,
'FW Feedvater System o
. GE General' Electric
/' Georgia Power Company k ')N GPC
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HL Hanger Lug ~
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HPOI High Pressure Coolant: Injection' System IMP Indication Notification Form
-IGSCC Intergranular Stress Corrosion-Cracking:
ISI Inservice Inspaction . LD Longitudinal' Seam Weld Extending Downstream LD-I Longitudinal Weld Downstream on Insiderof Elbow-LD-O Lonoitudinal Wold Downstream on-Outside'of Elbow Lo Zurb-Reference, Location-LPCI Low Pressure CoolantEInjection LU Longitudinal Seam-Weld Extending Upstream = LU-I Longitudinal Weld Upstream on Insidelof-Elbow-LU-0 Longitudinal Weld Upstream on outside of-Elbow . MSIV Main Steam Isolation Valve MS . Main Steam. System NSA ~ Main Steam Auxiliary System MT Magnetic _ Particle Examination NWO Maintenance Work Order NDE Nondestructivo Examination NI No Indication NRC Nuclear RegulatoryLCommission NRI No Recordable Indication OL Overlay
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')t v Abbreviat;igns -- c9nt.L PL . Pipe; Lug PLT. Plant ,
-PR PipeLRestraint PROD Product PS . Pipe Support PSW Plant Service Water System PT Liquid Penetrant Examination QC Georgia Power Company. Quality Control ,
RC Reactor Recirculation System RCIC Reactor Core Isolation Cool 3ng. System-RHR Residual Heat Removal System-RHRSW Residual Heat. Removal Service Water System RI Recordable Indication RINTSA Recirculation Inlet Nozzle Thermal Sleeve Attachment' Welds RL Refracted Longitudinal -
-RL Restraint Lug.
RPV Reactor Pressure Vessel RX Reactor RWCU Reactor Water cleanup System SBLC Standby. Liquid Control Systen " SIAI Structural Integrity Associntes,JInc.
- l. SER Servico
.[' - S RV. Safety Relief Valve ,
-. \ SNC Southern Nuclear Operating Company TDP Torus Drainage and Purification bystem TSB Turbine Steam Bypass Systum UT Ultrascnic Examination TJTL Universal Testing Iaboratories VLV Valve VT Visual Examination This list is cc.nprised of standard abbreviations used in Inservice.
Inapection t'ocumentation. All of these abbreviations may not appearLin this report,
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-TOTALiNUMBER OF SHEETS: -122
, FORM NIS-l'
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_\ FORM NIS-1' OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As Required By the Provisions Of The ASME Codes Rules
- 1. Owner: Georaia Power ,qqspany. 333 PiedmoD1-. Ave . . ,[{E . P.02 _E,Qf45 % ,
Mlanta. GeQraia 30102
- 2. Plant: Eglwin I. Hatch Nuclear Plant,_Re.tjte 1. Bo.x 278. Baxlev,_oA 31513-:
- 3. Plant Unit 2, 4. Owne:' Certificate of Authorization (if req.) 1]/2 ..
- 5. Commercial. Service Date 09/05/7J 6. National Board No. for Unit IJ/.A ,
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- 7. Components Inspected: l Component or Manufacturer State or Appurtenance Manufacturer or Installer Province National
, or System or Installer Serial No. Number ; Board No. ' 3x. P, rag.gure Vesagl- RQp_b. nation Enu. 70101 _ _ N/ A 1157Q Ex. Pressure Vessel l C.2E.ntstion lna _._ 71 U*S A EA_ 11570 2321 Main Steam Pullman Power _Prgh ,_.li / A J{fA_ - 2B21 Feedwater Pullman Powe.r_EIOL ._ . N/A- N/A 2B21 M.S. Relief Pullman Power Prod,
- N/A E 2._
2B3L Rx. Recire Pullman Power Er_ gam
- N'A__ _
_J/JL.L 2B31 Recirc B1mo B._yron Jackson _ ___,_
- E A_ N/A 2C11 Q_ED Pullman Power Prod _.__
- N/A _B/.A.,,,
p*. 2SEL SBLC _. EullnadQwer Prch
- EA_ El_ . ;
2E11 RHR . Pullman Pqwer Prod. * ,N/A_ N/A l 2E21_ Core Sprav Pullman Power Prqd.,,,,,_
- N/A ,_t{lA ,
i 2EA1 HPCI Pul1 man _Egwer Prod 2
- EA_ .N/A.
2 H 1._ E C I.9 . _ _ Evilman Poyer Prod.
- h / A ___ _l!/A Note: Supplemental sheets in form of 14.sts, sketches, or: drawings saf be used provided-(1) ~ size is 8 1/2 in. x 11 in., (2) informaticc. in-items 1 through 6 on this data report is included ou each sheet, and (3) each sheet. is numbered and the number of sheets _ are recuuled at the top of this form. **
Spool piece.of_ fitting nunbers too numerous to list for each specific system. Material certifications for all piping, fittings, l etc. , are available for review in the Records Management Department at the plant site. l
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- Exception taken to note 2.
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-7 Compononts Inspected _(continued)i Component- Manufacturer State or f Appurtenance Manufacturer or Installer Province- He.tio nal .
( or System or Installer Serial No. Number Board No.
.; mu 2G31 RWQU Pullman Pqwer Prod. * ?OA_ N/jk 2.Q41 FPC-& CU- Pu11 man Power._ED2d2
- D/_A _ ,_H/]L 2G51 tor.u.s Wtr CU Pullman Power Prod _ * . _ , _F/A_ .J.(/h ,-
2N11 M S_AgKl.liary Pullman Powe.r_Ersi.
- N/A ,.B/fL 2P11 C9_Dd. Systam- Pulltn.an Povq,r Prod.
- U/A N/A 2 P41 Plt Sery Watqr Egllaan Power Prod 2
- _N/A .N/A, 27_98 Cont, Purce Egllagn_P.Qy&dQA2 . , , ,
* ,_E/A.. N/A Spool piece of fitting numbers too numerous to list for each specific system. Material certifications for all piping, ' fittings, etc. , are available for review in the Records Management Department-at the plant site.
O 1 I i O 2
1 FORM NTS-1 (Back)-
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- 8. Examination-Dates 06/02/91 to 11,'20/92.
I\ /f 9. Inspection Interval from 01/86 to 01/96.
- 10. Abstract-of Examinations. . Include a list of oxaminations and a statement 'concerning status of work . required- for: current interval.
- 11. Abstract of Conditions-Noted. ***
- 12. Abstract of Corrective Measures Recommended and Taken. ***
We certify that_ the~ stat ements made In this-report are correct and-the ex$.minations and corrective measures taken conform to the rules of the ASME Code, Section XI. Date3_]D 193}_ Signed GRo.rala Power C ap_aD% Ey M . IV.h-h Owner Certificate of Authorization No.(if applicable)_H/A Expiration'Date,HZA_ , CERTIFICATE OF INSERVICE INSPECTION
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1, the undersigned, holding a valid commission lasued by the National Board of Boiler and Pressure Vessel Inspectors and/orithe Gtate or Province of GA and employed by **** of Hartford, CT have inspected tha components described in-this. Owners'1 Data-Report during the period 06/91 to 11222 and atate thattto the best-of my-knowledge E nd belief, the Owner has performed examinations and taken corrective measares descrlhed-in'this-Owners' Data Report in' _ accordance with the requirements of the ASME Code, SectionLXI. - By signing this certificate neither the . Inspector nor'nis -employer makes any varranty, expressed at-implied, concerning the examinations and corrective measures' described-in-this owners' Data Report. Furthermore, neither the Inspector nor his employer'shall be. _ liable in any manner for.any personal injury or_ property ~damago or a' - loss of any Kind arising from or connected =with this' inspection. Date 19 N q's 9 h') b)L -n - <A_ Commissions Georcria-GA00116 Inspector's' Signature -National. Board, State, Province,6;No. ,
*** The following NIS-1 form supplementary information and report includes the responses to NIS questions #10, #11, b.d 312.
** ** Hartford Steam Boiler- Inspection and Insurance Company, t
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1 i NIS-1 Form Supplomantary-Information; ,
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_- Owner's Data Report; [T for--
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. Inservice Inspection- '
Data,i January 20,- 1993-Owner IMpe & Addrays,: Georgia. Power Company 3 33 Piedy ont:- Avenue, - N.E. P.O.: Box ~4S45
. Atlanta, Georgia 30302 Namq J,,Jddress.pLNuclear Gemgrgtina Pignt;: ,
Edwin I. Hatch Nuclear Plant: Route 1, Box 278-Caxley,-Georgia 31513 Habte Assioned to tutqlgar__ Planti. Station:
-Edwj.n I. Ilatch Nuclear Plant Unit 2-
_Copercial Set vic_p Date: September 5,-1979 GrJ; Lgs Generatipo Canability: 2436 MWt, 817.3'MWe Et;AtA., Province, or_ Mqnis1DahAssioned NumbpI: ' N/A-National Board Nyp_];te d pSigngd by ManutapintgI: . H/A s A L 'tm)-s. l-it 4
Name of=ComJtQnent or Part cf Comngngnt.,,lSI-Involveds
,_s' Representative!samploslof the following components and areasc wore ,
l _- ' examined withEnondestructivo testing tecFniques.
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Class 1 Reactor Pressure-Vossel-Reactor Pressuro Vessel Clonure Head Main Steam Piping Systemi Feedwater Piping System-Residual Heat Rennval System Control Rod Drive System Reactor Recirculation System 'l Core Spray System Reactor Water Cleanup Systeu Valve Internal Surfaces High Pressure Coolant Injection System Class 2 RHR System core Spray Systen HPCI System RCIC System Control Rod Drive System Containment Purge and Inerting System Reactor Water Cleanup Syctem Main Steam Piping Systen Torus Water Cleanup System s_
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- Sya. tem Pressure /Idhikage - Tests e v.A S.YatfB ' ' ClDH - ISS.t - Recujrgtrl'>-
(_jz noactor Pressure Vessel and 1 <1= Leakage. - associated Class 1 Piping and Components-SBLC (2C41). '2 11 Hydrostatic * ' RHR (2E11) 2 2' _llydrostatic* HPCI (2E41) 2 Hydrostatic; HPCI-(2E41) 2 1 Hydrostatic *
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FPC (2041) 3 1 Inservice' , PSN (2P41) 3 - 4 Hydrostatic ;
- Pressure test performed per ASME Section XI code Case N-498.
Piga,_Euonort & Hancer ExarginatioJ1 91533_ 1 Main Steam System Residual Heat Removal System
/Sos Feedwater System Reactor Recircalation System ,
Slass 2 . High Pressure Coolalit Injection System Rasidual' Heat Remcval System - Reactor Core Isolation Cooling System Main Steam System Torus Water Cleanup System Main Steam Auxiliary System Standby Liquid Control SBLC System core, Spray System Drywell Ccoling System Class 3 Main Steam Safety / Relief Valve Discharge System- , RHR Service Water System Plant Service Water System Pue'l Pool Cooling & Cleanup System Reactor Building Chilled Water System
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'Name k_ Address of Manufa_cturgr of Comnonenta: 1 i
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.- l . ; Reactor Pressure Vessel'and Closure-Head:-
.'[N- Combustion. Engineering, Inc..
lll[\ Chattanooga,-TN
- 2. Piping'(Classes 1,.2,;and 3)'
- a. Pullman Power Products Div.ision of Pullman-Kellogg Wil11ausport, PA
- b. General Electric Company San Jose, CA Note: Piping purchased by General Electric and Pullman'and installed by Pullman. Material certifications and manufacturer information are available for review in the Records Management Department-at the. Hatch Plant Site.
- 3. Piping Supports-and Hangers (Classes l', 2, and 3)
- a. Bergen-Paterson Pipe Support Corporation Laconia, NH
- b. ITT Grinnell Corporation Providence, Rhode Island
- c. Pacific Scientific
-A Anaheim, CA
> d. Lisega USA Laconia, NH
- 4. Valves,. Pumps, and Heat Exchangers
- a. Byron-Jackson, Inc.
Los Angeles, CA
- b. Crane New York, NY
- c. Wm. F7well Company Cincinnati, OH
- d. General Electric i- San Jose, CA
.Date of Inservice InspectiMD:
September 1992 - November 1992 t As. 7
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- Completion-Date of' Inservice Inspection:: .
November 20,.1992. . ( -..
'Name of IDsnectqrt Donald R. Laakso-(ANI/ANII)
. Name' fr Mailing _Mgr3ss of Inspagion'.s Emoloyer:l The-Hartford Steam Boiler-Inspection and Insurance Company-200-Ashford Center - North Suito 300 ,
Atlanta, Georgia 30338 ( T p l[+.yN L 8 L l! , , , , . . _ .
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' ABSTRACT 7 An Inservice Inspection of selected Class 1, 2- and 3-components at Georgial ,
j Power Company's Edwin I. Hatch Nuclear Plant Unit 2 was; performed'during. '
\ the Fall-1992 Maintenanec/ Refueling Outage._ The components were= examined in accordance with the applicable ISI Outage Plan, including anyl changes made during the outage as approved by GPC.
Edwin I.' Hatch Unit 2 is currently in the. third period:of the secondi 10-Year Inspection Interval. The required _ examinations are presently?on ) schedule as specified in the Second Ten-Year Inspection Plan. The nondestructive examinations were performed using VT, PT, MT and UT examination techniques. SNC personnel and their contractor (GE) performed NDE of the selected welds and components. In addition, GB assisted SNC personnel with VT examination 'of selected RPV internal components. SNC or GPC NDE procedures were utilized for all ASME Section XI Examinations except as noted below. GE personnel were qualified to_ the applicable SNC procedures. EPRI certified inspectors were utilized for all examinations involving-IGSCC susceptible materials. GE procedures _Uere used for mechanized ultrasonic examinatJon and exams were performed by GE-inspectors. SNC and C&L personnel performed eddy current examinations of ASME and non ASME Section XI components per a request from GPC. C&L procedures were utilized for the performance of the eddy current examinations. , In addition to NDE testing of Class 1 and 2 welds and _ components, pressure testing, visual examination of Class 1 coraponent internal surfaces .and s) visual examination of pipe supports and hangers were also performed. Third . d party review (e.g. an ANII) was utilized for all examinations of ASME Section XI components. Selected components were examined in accordance with GPC commitments to the following documents: Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1980 Edition with Addenda through Winter 1981. United States Nuclear Regulatory Commission, Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Stool Piping" which invokes much of NUREG 0313, Revision 2, " Technical Report on Material Selection and Processing Guidelines for BWR_ Coolant Pressure Boundary Piping" United States Nuclear Regulatory Commission, NUREG 0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking". United States Nuclear Regulatory Commission I&E Bulletin 80-13 Visual Examination of Core Spray Spargers.- SNC " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant, Unit 2 1992 Fall Refueling Outage, Revision O." SNC "Second Ten-Year Examination Plan, Edwin I. Hatch Nuclear Plant' Unit 2." United States Nuclear Regulatory Commission NUREG 0803, " Generic Safety Evaluation Report Regarding Integrity of BWR SCRAM System
) Piping."
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Raprcrentativa etmples of tho following nystems, compriscd, of: colcct:d-- Class 1, 2, and-3 components, wero_examinedLusing various NDE techniquest g in.accordance;with the above,documentst '( ,,, Class 1 Reactor Pressure 7 Vessel (2B11) Main. Steam System (2B21) Feedwater_ System'(2B21) Reactor Recirculation-System'(2B31) Control _ Rod Drive System (2C11) Standby Liquid Control System.(2C41)
' Residual-Heat Removal' System (2E11)
Core. Spray System (2E21) High Pressure coolant Injection System (2E41) Reactor Water Cleanup Statem (2G31) ,_ Valve Internals Valve Bolting Clasg_2 Residual Heat Removal Cyctem (2E11) Core Spray System (2E21) High Pressure Coolant Injection System (2E41). Containment Purge and-Inerting System (2T48) Control Rod Drive System (2C11) -i~ Reactor Water Cleanup System'(2G31) Reactor Core Isolation Cooling System (2E51) Main-Steam Auxiliary System (2N11) Torus Water Cleanup (2G51)- 1% i
\~ e j class 3 Servica Water System l(2E11) (2P41)
Fuel Pool Cooling System (2G41) Main Steam Relief Valve Discharge Piping (2B21) Condensato Storage Tank (2P11) Other - Augmented (Non ASME Section XI) Eddy-current examinations were performed-on the following-components:- Unit 2 Feedwater Heaters 4A~,-4D, 6A, 6B, 8A, aB, 10A 110B, , one 1 ( 3 )- Reactor Building Chiller, Turbine' Stator _ Cooler 2B, and_ Emergency Diesel' Generator 2C, and 1B Jacket -- Water Coolers, . Lube Oil -Coolers, - and Air Coolers. UT_ thickness measurements were performed on selected components dn1the-Extraction Steam anc Condensate /Feedwater Piping-Systems.- A. portion of these components were selected due to their similarity in design arxl operating cor.ditions to components involved with- the "Surry pipe break incident". Additionally four Class 1 Feedwater components were measured for thickness in response to reportedf erosion / corrosion at Suoquehanna. : Seven (7) RWCU System wolds were examinnd using ultrasonic examinations-techniques (UT) due to augmented commitments made by_GPC. These exams-are not required by the ASME Section XI Code but were performed:due to, augmented commitments to NUREG 0313. 10 .
~ CLASS 1 EXMili{MIQLS
-_ --IGRE1_0112
.k GPC is committed to the-performance of surface and volumetric examinat' ions
~ on IGSCC susceptible welds in accordance with NUREG 0313.-This commitment is formalized in GPC response to NRC Generic Letter 88-01. The below listed -
summary gives the total number of exams-performed by outage ond. Catecory A Fourteen (14) Category A welds were examined using UT and PT. examination techniques. No reportable indications were detected. Cateaorv D There are twenty (20) Category D circumferential welds at Plant _ Hatch Unit
- 2. Eleven (11) of-the total of twenty (20)' Category D circumferential-welds were examined during the outage using UT a'id PT techniques. No-reportable indications were detected.
Five (5) RINTSA wolds were examined by UT and no reportableLindications were detected. Five (5) of these welds (50%) are examined each outage. These welds are categorized as "D" for NUREG 0313. _QAtecory E A UT examination was performed on weld 2B21-1FW-12AA-9 which was overlay A repaired last refueling outage. No crack growth was observed. cateaory L Two (2) Category L Support Lug attachment welds were examined using PT NDE. techniques. No reportable indications were detected. , ITU_ REG 0619 GPC is committed to the performance of surface and volumetric examinations on welds susceptible to crack growth due to thermal-cycling in accordance with NUREG 0619. - Twenty- (20)- welds were exhmJ ned ' as' augmented exams in response to this NUREG. No reportable indications were detected. t-I i l a I e (- 11 -
PM1gr Clasd 1 Examinations. Farty-two (42) ASME Section XI component examinations were performed ntilizing UT, MT,. PT and VT as applicable. These examinations included RPV. RPV bolting materials, piping welds, valve internals,- and valve c /(D /we2ds, bolting materials.
- Per IE Bulletin 30-13, the core spray sparger and associated piping-were VT axamined. No reportable indications were detected.
Per ASME Section XI, Eelected RPV internals were examined. These examinati<.,ns included portions of .the vessel interior, interior attachments boyond the belt line region and the RPV internal components. Indications were found on vessel internals that indicated an off center lift of the. Steam Dryor. Additionally reportable . indications were found on the Azimuth 180 degrees Shroud Support Ring Access Cover Weld. See the Invessel Inspection sect.i un of this report for more detailed information~ on renolution and disposition of invessel indications. Nine (5) Class 1 valves were disassembled for maintenance / inspection during the outage. The internals of these valves were VT inspected by '; GPC Q.C. personnel . Feedwarer valves 2B21-F010B and 2B21-F077B, Core Spray Valve 2E21-F0068, and RHR check valve 2E11-F050B failed their_"as found" internal VT exam. Repairs were nade. under MWO 2-92-5258, 2-92-5149, 2 3628 &nd 2-92-5237 respectively. None of the remaining valves exhibited any unacceptable conditions relevant to the visual examination. C.lmts II Examinations OThirty-four(34) welds were examined using surface and/or volumetric NDE techniques as applicable. Three (3) of these welds were examined per NUREG 0619 (UT only), one (1) was examined per NUREG-0803 (MT only), six (6) were augmented surface examinations and the remaining twenty four (24) were per ASME Section XI requirements. One weld on the HPCI system detected two linear surface indications and a surface planar indication.- The surface linear indications were removed and the planar indication was code acceptable. l 12
s Pressure' Testing Five (5) Class .2 Hydror,tatic Tests, four (4)_ Class 3' Hydrostatic Tests,- one- [7 -(1) Class 3 Inservice Test, and a Class 1 System Leakage Test wore all J ) performed satisfactorily _ Four (4) of the Class 2 Hydrostatic Tests were performed per ASME Section XI Code Case N-498. See-Pressure Test Section-of Report for specific test identifications and details.
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-Augmqnted Examinption Seven (7) welds in the Class 3 portion of the RWCU System were examined by UT per a GPC commitment to the NRC for- HUREG 0313- augmented requirements. No reportable indications were detected.
Pine Support Egaminations (Class 1. 2 and 3) Twenty-three (23) pipe supports were VT examined during the outage. -of these, four (4) produced unacceptable results. After maintenance and/or engineering evaluation, all of the unacceptable component supports were determined to be acceptable. Where maintenance was required, the component . supports were re-examined to confirm acceptability. Eauinment Suonort Examinations (QJass 2 and 3) Ten (10) equipment supports were VT examined during the outage. No unacceptable indications were reported. Snubbers (Class 1, 2 and 3) m I T Three hundred and eight (308) snubbers were VT examined por GPC QC. 'Nj procedures. Of these, six (6) were reported with unacceptable results. After engineering evaluation, all' of the unacceptable snubbers were determined to be acceptable. Renairn and Reclacements (Class 1 and 2) Numerous repair / replacement activities were performed during the outage. Major repair / replacement activities included replacement of two HPCI valves (F001, F008) under design changes _as part of an overall system upgrade. An itemized list of the repair / replacement activities is included in the Repair / Replacement Section of this report. Reportable Indications Following.is an itemized list of all welds and components which_ wore reported with indications or-were considered unacceptable. All of these items' were either repaired and/or evaluated and then determined to be acceptable. -O V 13 r
Egmparv of' Indications Identification _ Indication Corrective Action
/ Y COMPONENT THICKNESS'BEIDW THE ACCEPTABLE'AS IS WITH A ,) 2-MS7-9 ACTION LEVEL FUTURE' MONITORING COMPONENT- THICKNESS BELOW TIIE ACCEPTABLE AS-IS-WITH--
MS7-11 ACTION LEVEL FUTURE'HONITORING COMPONENT -THICKNESS BELOW THE ACCEPTABLE AS IS WITH 2-MS7-12 ACTION LEVEL ' FUTURE MONITORING COMPONENT THICKNESS BELOW THE, ' REPLACED WITH STAINLESS 2-1R4-8 ACTION LEVEL STEEL REDUCER MWO~2-92-5083 * - COMPONENT THICKNESS BELOW THE. CLAD WELDED WITH 2-1R4-9 ACTION LEVEL STAINLESS STEEL WELD MATERIAL' MWO 2-92-5083
- COMPONENT THICKNESS BELOW THE CLAD WELDED WITH 2-1R4-10 ACTION LEVEL STAINLESS STEEL WELD MATERIAL MWO 2-92-5083
- COMPONENT THICKNESS BELOW T!!E REPLACED WITH STAINLESS 2-1R4-11 ACTION LEVEL STEEL REDUCER 73I i
MWO 2-92-5083 *
'w/ COMPONENT THICKNESS'BELOW THE REPLACED WITH CARBON 2-2R4-3 ACTION LEVEL STEEL REDUCER-MWO 2-92-5083
- COMPONENT THICKNESS BELOW THE REPLACED WITH STAINLESS 2-2R4-10 ACTION LEVEL STEEL REDUCER MWO 2-92-5083
- COMPONENT THICKNESS BELOW THE . ACCEPTABLE AS IS'WITH 2-2R4-8 ACTION LEVEL FUTURE MONITORING COMPONENT THICKNESS BELOW THE REPLACED WITH-CARBON 2-1R4-4 ACTION LEVEL STEEL REDUCER MWO 2-92-5083
- VALVE BOLTING HEAVY RUST ON NUTS ACCEPTABLE AS IS 2B21-F013A AND BOLTS VALVE BOLTING HEAVY RUST ON NUTS ACCEPTABLE AS IS 2B21-F013C AND BOLTS VALVE BOLTING HEAVY RUST ON NUTS ACCEPTABLE AS IS 2B21-F013E AND BOLTS
;{3 VALVE BOLTING DAMAGED BOLT THREADS ACCEPTABLE AS IS-
_g / 2B21-F013D
%/
14
Identification Indication. Corr *ctivo Action. .
. VALVE BOLTING' DAMAGED BOLT THREADS ' ACCEPTABLE'AS-IS
- 2B21-F013B i
(,)) NOZZLE FEEDWATER SPARGER: DEBRIS IN6IDE SPARGER NOZZLE, DAMAGED OUTLET REMOVED-AND ANALYZED DEBRIS.- -OUTLET 45 DEG NOZZLE NOZZLE IS ACCEPTABLE-0-1D AS IS. FEEDWATER SPARGER ' DAMAGED TACK WELD = ACCEPTABLE AS IS_WITH TACK WELD FUTURE MONITORING
.45 DEG O-1D STEAM DRYER CONTACT DAMAGE REPAIRED SUPPORT-LUG SUPPORT LUG MWO 2-92-5156.
145 DEG K-13 STEAM DRYER CONTACT DAMAGE REPAIRED SUPPORT LUG SUPPORT LUG -1940 2-92-5156 215 DEG K-14 STEAM DRYER CONTACT DAMAGE ACCEPTABLE AS IS - SUPPORT LUG 325 DEG K-15
.( )UPPERGUIDEROD GUIDE ROD DAMAGE ACCEPTABLE _AS IS L/ BRACKET ATTACHMENT WELD 180 DEG A-6 STEAM DRYER TORN WELD, BUCKLED ACCEPTABLE AS IS WITH UPPER DRYER BANK PLATES FUTURE MONITORING 180 DEG STEAM DRYER CONTACT DAMAGE -ACCEPTABLE ~AS IS LUG 146 DEG C-10 STEAM DRYER CONTACT DAMAGE ?.CCEPTABLE AS IS LUG 214 DEG C-11.
SUPPORT CORROSION, DEBRIS REMOVED CORROSION \ 2E11-RHR-H314 IN SPRING CAN AND DEBRIS MWO 2-92-5215-* i l
-'N_(O//
15
i: Ident'ification Indicatibn Corrective' Action
-STEAM DRYER INDICATIONS IN~ ACCEPTABLE- AS IS WITil
-PLATE MATERIAL. BEND AREA FUTURE _ MONITORING j,3,__}ADJACENTTO-
- A/ BANK VERTICAL TWELD #12 STEAM DRYER- INDICATIONS IN -ACCEPTABLE AS IS WITH PLATE MATERIAL BEND AREA FUTURE MONITORING ADJACENT TO BANK VERTICAL WELD #27 STEAM DRYER INDICATIONS IN ACCEPTABLE AS IS WITil-PLATE MATERIAL BEND AREA FUTURE MONITORING ADIACENT TO BANK VERTICAL
- WELD #32 VALVE BOLTING IIEAVY CORROSION ACCEPTABLE AS IS 2E21-F006B SUPPORT IDENTIFICATION TAG REMOVED TAGS AND-2B21-MSRV-H12 WIRED TO SPRING REINSTALLED IN PROPER LOCATION MWO 2-92-5346 SUPPORT IDENTIFICATION TAG- REMOVED TAGS AND' ss 2B21-MSRV-H15 WIRED TO SPRING AND REINSTALLED 5IN PROPER
( l WEDGED BETWEEN COIL LOCATIONS
]>_ / MWO 2-92-5346 SUPPORT SPRING CAN READING LACCEPTABLE ASLIS-2B21-MSRV-H15 .OUT OF TOLERANCE
~
SUPPORT 3/16" LINEAR 1 REMOVED INDICATION 2E11-RHR-R84 INDICATION ON LUG MWO 2-92-5301-TO-PIPE ATTACHMENT WELD ACCESS HOLE TWO NON-GEOMETRIC ACCEPTABLE FOR CONTINPED COVER PLATE WELD PLANAR INDICATIONS OPERATION 180 DEGREES I-4 EMERGENCY DIESEL EIGHT TUBES RECORDED PLUGGED' TUBES COOLERS WALL LOSSES OF 40% MWO 2-92-854
- 1R43-B003B OR GREATER 1R43-B004B ,
1R43-B005B - WELD 1" AND 1 1/4" INDICATIONS REMOVED 2E41-2HPCI-10-D LINEAR INDICATIONS MWO 2-92-3424c* MWO 2-92-5472 *' j'~ ~% . . THICKNESS BELOW THE ACCEPTABLE AS IS WITH l.(% f COMPONENT 2-6E-24 ACTION LEVEL FUTURE MONITORING. 16
Identification. Indicatign Corrective-Action COMPONENT THICKNESS-BELOW THE- ACCEPTABLE-AS:IS WITH' 4 2-6E-25 ACTION LEVEL FU_TURE MONITORING COMPONENT THICKNESS BELOW THE ACCEPTABLE AS IS WITH 2-10E-4 ACTION LEVEL- FUTURE MONITORING WELD 0.3" SURFACE PLANAR ACCEPTABLE AS IS-WITH 2E41-2HPCI-10-D-27 INDICATION _ FUTURE MONITORING,
- These MWOs did not require initial or final ANII review.
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.B-K-1 DEVICE 2821-MS-R44 ASME 89.11 A-8/07 2821-1MS-24C-15 MT-M-500/05- 147-n 592M2M044 mat ONE-SIDED EXAM COE TO B-J PIPE TO VALVE UT-H-400/10 . S92N20057 m/A UT CAL VALVE CONFIGURATION.
ASME S92H20123 mRI S92N2C058 N/A UT CAL 592H2u124 mRI S92H2u125 m/A intCKMESS 1 89.11 A-9/06 2821-1MS-240-1 MT-n-500/05 152-n S92M2MOZ3 NRI CDDE CASE N-461 USED. B-J N0ZZLE TO TRANSITION PIECE UT-M-400/10 SV2N2C016 m/A UT CAL ASME S92H2UO57- NRI
$92H2UQ59 N/A WELD PROFILE 592M2UO58 t/A THICKNESS 89.11 A-9/06 2821-1MS-240-2 MT-M-500/05 152-5 $92N2M020 WRt CODE CASE N-461 USED.
B-J TRANS! TION PIECE TO PIPE UT-M-400/10 147-N $72H2C059 N/A UT CAL-ASME S92H2U126 mRI S92H2CD60 N/A UT CAL-
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'8-G VALVE BOLTING $92N2V194 SAT E.s lATION. SEE INF 192H2003. -
ASME 87.70 A-5/01 2821-F013D BOLTING VT-n-710/03 N/A $72n2V014 UNSAT THREAD DAMAGE USE As IS PER ENGINEERING' 8-G-2 VALVE BOLTING $92N2V195 SAT EYALUATION. SEE INF 192N2006 ASME 87.70 A-5/01 2B21-F013E 80LTING VT-N-710/03 N/A 592M2V019 UNSAT NEAVT RUST USE AS IS PER ENGINEERING . B-G-2 VALVE BOLTING $92M2V1 M ' SAT EVALUATION. SEE IMF 192K2003.
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7 s VISUAL' EXAMINATION OF CLASS 1 VM.VE INTERNALS ~
~( Thib, section provides a summation of the ASME required viaual examinations of Class 1 valve internal surfaces. These examinations were performed on valves that were disassembled - for maintenance during - the' 1992 Refueling '
Cutage. The examinations were performed by Georgia Power Cotopany Quality-Control Inspection personnel in accordance. .with' GPC _ Procedure 4 50C-I~.4S-012 -OS . Copies of the inspection reports are available ' at~ the plant site. 'The valves inspected were from the following systems: Main Steam (2B21) , High Pressure Coolant Injection (2E41), Reactor Water Cleanup (2G31) , Residual Heat Removal (2E11) and Core Spray System (2E21) . Listed below are the valves examined and a brief summary of the teaults. VALVE NUMEJ2 MWO NUMBFJ? MMlJMS. , 2B21-F010B 2-92-5258 Disassembled dua to LLRT f ailure. ' Eroded areas found on dirsk seating surfaces. ' Thread ; danage on hange pins over bolts. Rtpairs perfermod and leak rate test passed. 2B21- F013H 2-92-1874 This SRV was removed and-shipped to Wyle Labs for inspection. VT was l acceptable. -
') 2 Ell-F050B 2-92-5237 Disassembled'dde to V LLRT failure. No service induced discontinuities recorded.
2E41-F002 2-92-195 Partial disassembly due to-electrical backseating during previous cycle. VT was acceptable. < 2G31-F004 2-92-2927 New Bonnet, Yoke _and Actuator-installed per HELB design change l No service induced discontinuities j noted. I- 2B21-F028C 2-92-4S01 Disassembled due to LLRT failure. VT of internals acceptable. ' Main and Pilot Poppet Assembly replaced with VT baseline perforned. l 2B21-F077B 2-92-5149 Disassembled due to LLRT failure. + l As found VT reported evidence'of . l ocosion on disk seating surfacen, and evidence of stuffing box leakage. Repairs performed and ' l leak rate test passed. I 52
-e. - -
., 3 3 i ' 'M . i ,s (
s/i > 7.1 'y i i, @ , j '; .- VISUAL EXAMINAT10N OF CLASS 1- , ..
> VALVE-INTERNALS , ,' 4 (Continued)i m,,,
. /~3 lDisassembl4 and inspect internals.
i, 12G31-F001.' 92-197-
~VT v e acceptable.
2E21-F006B-- .2-92-3628' : Disannemble and inspect b ternals. 3 indica'clors were recorded in thel ' ' seat area. These indications voi'e' - removed after 3apping-the seat a r e a'. 9 9 4 d
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SUMMARY
m Oy . 1 V CLASS 2 EXI.MINATIONS l s l' l-i,- I
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E.I. HATCW UW1T 2 siaRtzG 1972 REFUELING OJTAGI CLASS 2 COMP 0NEM15 ADtE EXAM EXAMlWA?!CN CAL EXAM / CAL ECT!ou r1 LtGi%F Wo. ExMWAf f 0WMf A r#0CE00CE stock 5"fET 40. EESULTS REwaag couTrot too ee:ve s m tM ,
-- B-83/04 2C11-2CED-3 2rW-1611 Ur-N-400/10 4-H E92x2C067 N/A UT CAL OME-SIDED EIAM DUE To;
- FIPF YO AEDUCIR $92h?u136 WRt COEFicuRA!!oN.
WREG-0619 S92H2CO66 N/A UT CAL EyAMINED OELD AND .5" B2SE 192HZU137 NRI METAL. CODE CASE W-98 N D. B-83/04 2C11-lCRD 4-2FW-1611 UT-H 400/10 142 si S92N20063 m/t UT CAL cart-SicED EXAM DUE To REDUCER TO TEE SG2P?J132 NRI .CCWFIGURATICW. sitTIG-Ca19 $9M20064 4/A bT CAL -EXAMINED WELD AmJ .5" BASE' 592N2013' .NR; METAL. B-85/04 2c11-2Cao-84-sDV-5 MT-M-500/05 h/A $92F2M015. WRt EL20W TO PIPE ItuRG-OdO3
.1 RESIDUAL HEAT REw Wat SYSTEM ,
1 C1.20 8-1/03 2HX-A-1 MT it 500/05 72 H $92H2M011 ERI ONE SIDED EXAR PtX TO-C-A. SHELL HEAD TO UPPER SHELL RtWG UT-H-400/ O 73-M s92H2CC01 N/A M CAL . COWFIGURAT!0sti UT EXAfd LIMITfD ASME- S92M2V095 NRI to 36% CCTERAGE. NT EXAM : S92520002 %//. UT CAL. L:PTED 10 801 CovERAM .
.592H20006. R1 CEORETRY SEE RR 3.1.1. -4 l592K2C004 h/A bi CAL : <
. Sv21420026 mR L
$9282C003 afA ' UT CAL :
592N20025 RI aEOME!RY L - v S72R2C005 N/A l 'UT CAL ^
- 592ri.1227 Rt ' GEOMET*Y ti C3.10- 8-1/03 2MX-A-35-1" 'MT H-500/05- W/A S92H2M3211 Nt
"?-C LOWEP.'ShELL R:NC SUPPGRT -
' AssE Q --
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( ' E.1. !MYCH UNIT 2.speluG 1992 EEFUElitG DJTAGE CLASS 2 CLMP0kENTS , 4 5!41 EXAM EXAM!hATID4 CAL EXAM / CAL SFCTIOW XI FIGtlRf 41 EXAH!N4 TION / AREA PROCEDURF, SLOCK CHEET N0a PESL*L T_5 REMAPES .
~
RESIDUAL REAT REMOVAL SYSTEM C2.21 B-1/03 2HX-B-I - MT-N-500/05 72-N s?2H2MG03 hRI CB INLEf W ILE TO RNR HX SMELL UT-H-4M/10 592H2COC2 N/A UT CAL ASME 592n2uC33 mi 592 PC007 uiA UT C(L S?2N2UO32 Ri CEOMETRT s92M2CC06 N/s UT CAL 592H20026 .41 EOMETRY s-101/02 N11-2RHz-58 TL-e-4 MT-H-500/05 m/A $92H2MU42 #RI P!PE TO VALVE
% ENYED 8-30/04 ?E11-2Asit-48-ext-3 MT-n-500/GS w/A $92h2Muos ht!
..--- Itsou To rLAwar AUGMGTLD e-49/G4 .2E11-2RNk-48-TS 8-1 MT-N-500/05 s/A . s92M2M045 ' tal BC 10 FiPE AUCMENTED~
t
.C5.11 E-19/03 2E11-2RH9-68-RW -2. MT-M-500/05 w/A s92n2M005 mRI, C-F PIPE TO ELBOW ASME
~
205.11 B-31/04 ' 2E11-2RHR-163-HWO-6 ' MT-R-500/05 N/A- . 292M2M010 TkRI-
- C4 . PIPE.TO ELBOW-
'ASME -.(T) -
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bth / (/ E.I.' HATCH TAIT 2 SPtikG 1992 WETUELING OUT4.GE U ~ CtAEt 2 COMPONENTS ASME EXAM EXAMikATIO't CAL EXAM / CAL SECTION X: FIGURE NO, EXA*ilwAfiops/AEEA PROCfDORE BLOCT $REET NO, ,PSSULT} REMPr$ N1510UAl. HEAT REMOVAL SYSTEM C5.11- s-30/04 2E11-2RHR-16a 4S-5 MT-H-500/05 592i;2*E s2s C-F PIPE TO TEE ASMR C3,23 B-39/04 2E11 2RHR-20-#1-2P.-1 THRu 4 MT-H-500iO5 592H2M041 NI CC DEVICE 2E11-Od-H314 ASME
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CS.21 B-46/02- 2E11-2RFI 248-BP-Y MT-H-500/05 139-H '92F2M016 N1 C-F P!PE TO P2PE UT N-400/10 C d2CD62 N/A UT CAL A*ME $92M2U130 Rt GECMETRY S92H20131 N/A Tel:CENESS C5.31 s-47/03 2E11-2RHR-243 n !-2BC/2E11- NT-R-500/05 N/A $9?H2M014 WR! . C-F 2ReiR-203-90-3 -- . ASME .P!PE TO BRANCH CO WECTION W T SPRAY $TSTEM B-98/02 2E21-2C$-3-krl 7 MT-H 500/05 N/A '577x2M012 ' hRI VALVE TO P!PE AUGMENTED
.C5.11 5-55/04' 2E21-2CS-103-TL-/. MT-N-500/05 N/A s?2H2M007 kRI C-F - PIPE TO FLANGE ASME B+59/05 2E21-2Cs 128-18C/2E21-2C5-3'4f L - MT-H-500/05 'N/A- -s92H2M047' . mRI PIPE TO SC
/.U6MENTED -
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E.1. PATCH UNIT 2 ENIL*G 1992 REFUElltC CtJfAGE , CLASS 2 COMPONENTS ASME EXAM EXAMINATION CAL EXAM / CAL
'SECTION XI FIGURE No. EXAMioTION/ AREA ' kOCEDUPE S'0CK SHEET NO. RESULTS RECRC CORE SPRAf SYSTEM C5.11 E-59/OS 2E21-2CS-129-5 MT-H-500/05 N/A $92H2S013 dRI
~C. VALVE TO P!PE
_ASME P!GH P2 ESSURE COOLANT INJECTION SYSTEM
. C5.21 - 8-68/04 2E41-2nPCI-10-D-27 MT-n-500/05 54-H 592H2M060 R1 'tlNEAR IND. LINEAR ICICATIONS RDCVED.
C-F - P!Pf TO ELBOW UT-H-400/10 592H2M061 mi PLANAR IwotCATIONS ARE ASME 592H2C136 N/A UT cat. ACCEPTABLE As I .- S92H20242- RI PLANAR 143. SEE IRF 192N2015 AND 192H2017. 59242C137 N/A UT CAL
$92H2*J244 RI PLAMAR IND.
$92H20243 N/A THI!JNESS
-C5.21 e-68/04 2E41-2HPCI-10-0 35A UT-H-400/10- 54-H $92H2CO69 4/A - UT CAL ONE-SIDED EJJut DUE 70 '
C-F P!FE TO VALVE $97,GJ130 NRI CONflOJRAT!0E. ASME. $92H2CU70 E/A .UT CAL MT EXAM PERFORPED BT CPC QC.
$92H2u140 . NRI
$92H2CO61 N/A UT CAL
$92N2U138 RI GECMCTRY
' $92H2U141 N/A THICaESS HICR PPESSORF C001. AN! IMJFCTION SYSTEM C5 21 B-70/04- ZE41-2MPCI 19-TL 4A MT-H-500/05 137-H S92M2M054 : .;; CNE-SIDfD EX9 DUE TO -
C-F P1PE TO VALVE UT*Ne400/10 $92H2C110 N/A . UT U L CONFIGUEATION.
.ASME $92N20190. 21 GEOMETRY 592x2C108 N/A 0; CAL
$92H2u188' sI S92M2C119 W/A : UT. CAL. _
$92H20205. It! CE0EiRT '
- $92N2U186 N/A : 'TNICKNES$.
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E.I. NATCH UW17 2 SP2thG 1992 REFUELING CLITAGE
)! ~ "
CLASS 2 CCHMAENTS - ASME EEAM EXAMIRA?!De CAL EXAM / CAL 5JJ;If04 XI
. flGURE ko. EXA*!NATIO4/ AREA PROCfDUPE BtCCX SHEET MO2 PESULTS REmu rs-HICH PRESSOCE CCOLARY !WJECTICW SYSTEM C3.21 8-70/04 2141-2HPC143-TL-SA MT-k-500/05 137-n s92n2M053 ~ MI cc.-sleE0 EXCE DUE TG C-F VALVE TO PIPE UT-h-400/iG $92H2C102 W/A UT CAL CCnF tGURATi(p.
ASME 592H2U178- El Gt(AEftY , S92H2C109 N/A UT CAL S92H20189 - WRI S92H2C120 ~ W/A UT CAL 392M2U206 ' ri GEcMETRY 592H2U185 E!A TNICK'vEss B-73A/02. .2E41-2Hoct 16-CS PT-N-600/03 si/A $92H2PG01 N1 ELBOW TO PIPE A!XTrEN TED C3.23 8-69/04 2541 2HPCI-20*TD-4PL-1 T3fRU 4, MT-H-500/05 N/A $91N2M009 NRI CC -CEVICE 2C41 HPCI-HL ASME-C3.20 s-69/04 2E41-2WPCI-JD-TD-f#L 1 THRt! 3- Mr-M-Sc0/05 W/A 592H2=003 Nat CC DEVICE 2E41-stPCI-420 ASME
-PEACTC9 CCRE ISot4Th* COOLIWC SYSTf4 89.11 A-338/01 2E51-2RCIC-4-D-39 ttT-M-500/05 142-H- 592H2M056 ' hi . 04E-SIDEC OtAM DUE To ,
B-J ' TEE TO P!PE iti-H-400/10 SC26C134 W/A UT CAL CONF:GRATIT. E4 S92M20239 wn!
. S92MZC' ) N/A UT CAL
_S92 Vu240 et - S92M2U241 M/A 'TMICoiESS
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E 1. HATCH trJIf 2 EPR1kG 1992 REFtELIEG OUTAGE CLASS 2 COMPCEENTS ASMC EXAM EXAMinA!!ON CAs. EXAM / CAL -9
}{ClJg XI FidJRE NO. [g XA X,MINATIDW/ AREA PQOCEDURE iROCK SWEEY WO. PMULT$ R NARR$ :7 i E2AC104 C05?E !!Ot.AT!04 C0CLIF1 SYSTEM 89.11 A 3Ss/01 2E51-2Rr!C-6-3-1 MT-H-500/M, 50-H $92H2MOS? NI CEE-$!DED EXaW9 Dt,t TO 5-J 2EDUCCP. TO P!PE UT-N-400/10 S92H2C113 m/A UT CAL CDNFIGt*AT10M.
.ASME :>92x2t!200 ERI 592h2C130 N/A UT CAL ,
592!!etP.25 WR1
$92H2U201 ti/A - E iD PROF!LE 592M2U202 N/A WLO PROFILE s92x2u203 N/A WELD P8EOFILE
$92H2LI204 M/A WELD PPCFILE 05.1T e 82/06 2E51-Zacic-!v-T3-2 ki-N-500/05 N/A $92N2M002 NRI
'C-F PIPE TO TEE
._. ASME f.5.Il B-82/06 2E51-2RCic-10-10-3 tit-e-500/05 k/A !?2H2M001 mRI
' 0*F - 1EE TO PIPE
.-ASME -
REACTOR WATER Ct.4NUP SYSTEM s B E1/04 2G31-2EWCU-4-2FW-33 UT-M-400/10 - 1&2-n s92H2CC65 - ' 5/A'- UT CAL' OgE-$1DED ExAFC DUE TO TEE TO P!PE $92H2U134 WRI CONFIGURATION.
~~
.: PetEG-0419 592w2C066 N/A UT CAL EXAM!kED WCLD A O .5" EASE.
$92ii2J135 - NRI METAL.
Mats st!Me Auxitgaar system-Cf.21' 'B 3/02 - 2W*1-2MSA-6A-$JAE*1 Pti-N-500/05 50-H $92H2M51 hRI- GME*S1(C EVJU4 DUE TO TF BR ANCN Cos;NECTIoW TO F:PE- UT-H-400/10 S92d20052 . W/A UT CAL' CONF 10URA PON.
-/ME
$92H20155 - WR1
$92H2CCB3 - k/A ' UT CAL
$92:42U156 s R1 - CFCNETRY .
s?2n2L1157 ' N/A. liitCrwEss
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SUMMARY
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CIASS 1, 2, AND 3 PRESSURE TESTS f 1 0 g.-
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-- . .. , - .~ - - - - .- . ~ . .- - .. ..
PRESSURE TESTING
- GENEBAL .
E This section=of the report provides a discussion-of the pressure tests u !sb which were performed during the 1992 Plant E.I. Hatch Unit 2 Fall Retuoling :
' Outage. These pressure tests.wero performed _for the purpose of incorvice= ~
inspection on Class 1, 2, and 3 components. The pressure tests and their-boundaries are identified in the inservice inspection plan ' documents prepared by Southern Nucin'ar Operating Company. All pressure tests were performad in accordance with ASME Section XI,1980 Edition with Addenda through Winter 1981. All tests were witnessed and/or reviewed by the resident ANII. The completed test reports are availablo for review in the Records Management Dept.rtment at Plant E.1. Hatch. CIIM __1 PRESSURE TERT;i One (1, class 1. Lcakage Test was perfrrned during the outage por ASME , Section XL paragraph IWA-5211(a). The test was . performed per GPC procedure, 42IT-TET-006-2S, ISI Pressure Tust of the Class 1 System. TEST RESCLTE Only minor lenkati e at nochanical joints was ' found during the VT-2 cxamination. Any _ component- which was disassembled prior to startup or to repair leakage, was re-examined during startup at nornal operating pressure (2005 psig) per GPC procedure, 421T-TFT-004-OS, Operating Pressure Testing A of Piping ahd Components. CIAS1_1 fREMURE TEET_1MitfNd. IbST I._p2 PRoqEDRB21 lpig_1gligf; 2B21-LT-1 421T-TET-006 'IS 2-92 ~3 6.5 5 CMSS 2_.EEMEURE TESTS One (1) Class 2 Hydrostatic Pressure Test waa performed during the outage _per ASME Section X1 paragraph IWA-5211(d). The test was perfomed in-accordance with GPC procedure, 42IT-SET-003-OS, Hydrostatic Pressure Testing of Piping and Components. Four (47 Class . 2 Hydrosthtic Pressure Tests were performed during - tho , outage per ASME'Section XI Code Caae M-498. The tests were performed in accordance with GPC procedure, 42IT-TET-004-OS, Operating Pressure Testing ' of Piping and Components. TEST RESULTS only minor leakage at mechanical joints was reported 'during the VT-2 4 examinations and all results were determined to be ~ acceptable or were repaired. ; s : l r
.l l
r , . _. , - - _ _ - . - .
.+
S. l.GT]h2O^S~UMMARY. TEST TiL PPocEDMER- tiHQ NUMBER Y3 2E41-HT-3 42IT-TET-003-OS 2-92-3636 4 2C41-HT-1*. 42IT-TET-Ou4-OS :Not Required a 2E41-HT-4* 42IT-TET-004-OS- Not~ Requited D 2E11-HT-5* 42IT-TET-004-OS Not. Required 2E11-HT-10* 421T-TET-004-OS Not Required .
- Pressure To.sts performed per ASME Section XI Code-Case N-498. :I CJASS 3 FRESSMER_IC'.LS ;
Four (4) Class 3 11y Jrostatic Pressure Tests were performed during -the- x , outage per ASME Sectioit XI, parag.'iaph IWA-5211(d) ,- in accordanco with GPC ' procedure, 4 2IT-TET-003-OS , - Hydrostatic Pressuro Testing of Piping and: 4 Components, : j i One (1) Class 2 Inservice Test was performed during the outage per ASME j
, Section XI, paragraph IWA-S211(c), in accordance. with GPC procedure, 42IT-TET 004-OS, Operating Pressure Tescing of Piping and Compcnents.
)
-TEST P&SULTS Onl.y minor mechanical leakage we.s reported during the VT-2 examinations andL ,
was determined to be acceptable or was repaired, , CIAES_.2_EEESRVFe TEST rum"Any TERT I,h PROCEDURE MNR_3JJ11ER 2P41-HT-24 4 2IT-TET -003 -OS 2-92-2788 i-2P41-HT-32 42IT-TET-003-OS 2-92-2788 2P41-HT-33 421T-TET-003-OS 2-92-2788 2 P4 L-HT-3 6 42IT-TET-003-OS 2-92-3604 2G41-IT-1 421T-TET-004-OS' Not Required ~ r i~ 1 L L l - L l t ( :. i L L64
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SUMMARY
OF-VISUAL EXAMINATIONS CLASS l', 2,;AND 3 id.,]j COMPONENT SUPPORTS i
~
r 5 i-i; v mv .w + e w a a - m -, . 65 . .
{ COMPONENI.RlP10RT EXAMINATIONE This section of the report provides a.d !"s Jalon of th'a visual exam 1*)ations
',s on : Hatch Unit: 1. Equipment
--[m 1. performed ' onfpipe selected component : supface listed on separate tables as part supports and supports inspected
"(") of this l section, - The subject ' examinations were - performed prior to and during the Refueling / Maintenance Outage. Exam.' 7tions were performed using:
SNC Procedure VT-H-730 (VT-3). The procedure and all examination data z sheets are available'for review-at the plant site.
- EEAminat19AG.
Pine Suonorts Class 1 Six (G) component supports from the B21, B31,. Ell, E21, E41 and E51 Systems were visually examined. No unacceptable indications were detected. Class 2 Thirteen (13) component supports from the C11, C41, Ell, E21,- E41, E51, GS1, Nil, and T48 systems were visually examined. One (1)' of these Class 2 component supports was found unacceptable.
.QJ ass 3 Fourteen (14) component supports from the B21, Ell, G41, P41, and P64 i systems were visually examined. Three (3) of these Class 3 component- , supports were found to be unteceptable.
, V Ecruipmgnt Sqnports Cla2E_l
-Four (4) equipment supports from the C41 and T47 system were visually examined. No unaccepttble indications were detected.
Elags 3 Six (6) equipment supports from the E11, ,P41, -and P64 systems were visually: examined. No unacceptable indications were detected. After maintenance and/or engineering evaluation, all of the unacceptable j component supports were determined to be-acceptable. Where' maintenance. vas involved, the component- supports were re-examined to confirm-acceptability. l , : (f)/ v l l L u 66-
e q .., [T . 7 y;
'( :i \.
( 1992 E.I. HAiCH U2if 2 PIPE SUPSC TS '- )
- ASME Ct.AS$ SUPPORT F! CURE NO kANGER TYPE- RESULTS REPORT NO. INF kO. MWO NO. RESULTS REPORT NO. REMARKS
'2- 2C41-A001-S01 '2C41-SK2 SUPPORT A S92H2v146
-2' ~ 2C41-C001A-S01 '2C41-SK3 SUPPORT A So2H2v147
- 3 2E11-C001A-S01 2E11-SK10 SUPNT A $92M2V148
-3 2E11-D002A-$01 2E11-SK11 SUPPORT A' $92P2V149 3 2P41-C001A-501 2P41-SE12 SUPPORT A S92H2V150
'3 2P41-C002-$01 2P41-SK13 SUPPORT' A $9262V151 3 2P41-D001A-$01 2P41-SK14 $UPPORT A $92M2V152'
. 3' 2P64-9006A-501 '2P64-SK15 $UPPORT A S92H2v153 2 ' 2747-8008A-S01 2T47-SK9 SUPPORT A $92H2V154 2 2T47-8009A-S01. 2T47-SK9 SUPPORT A- $92H2v155 1 2521-MS-H3 A-6/05 SPR1idG A' $92N2v013
~
1- 2821-RFW-N4. ~A-11/05 SPRING - A $92H2v010 1 ~ 2821-RrW-MS A-11/05 SPRING A S92H2V017
~
1- 2B31-HA2 A 17/04 SPRING A 592H2v012 1 2E11-RR-H367. A-20/04 HAPGER- A $92H2v026 " 1 2E11-RHR-H332 A-22/05'- ~ SPRING A $92H2V011
.2: 2N11-MS H14 'E-10/07! SPRING ~ A ~ $92N2v009
'2. .2E11-awe-H314 - B-39/04 SPaluG u 592x2v016 192N2008 2 92-5215- A S92N2v044 -WINOR CORROSION AND OE,BRIS.
2.. 2E21-CS R43 B-57/04 RESTRAINT.- A ' S92H2v006'
.2.' 2E21-CS-R47- ' B-57/04 RESTRAINT- z 'A S92M2v005 2 2E41-FPCI-RIO2. J8 66/05' RESTRAINT'- .A' S92N2 70A IN . .._ _
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ASME CLASS SUPPCRT FIGURE k0 #ANCER !TPE RESULTS REPotT me. INF NO. MWO NO. RESULTS REPCRT 40. 'REMdKS : 2' 2E41-NPCI-R104 B-66/05 RESTRA!wi A $92E2v003
- 2) 2E41-NPCI-H2$ B-70/04 SPRING- A $92H2v038 -
2 ZG51-TD-H1 e-76/1% - SPRING A $92M2v002 2 .2E51 RCIC-R71 9-%/03 RESTRAlkT A $92H2v003 3 2P41-SW-H92 C-17/02 HANGER A $92H2v007
- 3. 2E11-RNR-R84 C-108/03 RESTRAIN 1 U 592P2VUI4 192H2012 - 2-92-5301 A S92H2V040 3/16* L!kEAR INDICATION.
3 '2821-MSRV-M12 C-105/02 SPRING o $92H2v036 192M2011 2-92-5345 A S02H2V144 - 1.D. TAG'VIRED TO SPR!kG. 3 2321-PSRV-RS1 C 111/02 . RESTRAINT A $92H2V043 3 2B21-MSRV-815 c-111/02 SPRlWG -U $92H2V037 192H2011 2-92-5346 A '$92M2v145 1.D. TAG WIRED TO SPR1%G. SPRIWS CAN READING DJT Of TOLERANCE. 3 2821 MSRV-HS C-119/02- SPR!stG A S92H2V039 3 2B21-MSRV-H2O ..C-120/02 SPRING A $92H2v042 3- 2821-MSRV-H32 C-124/02 SPRING A $92H2v041 l 00
M :n O V' q, .- [ ""): ' 1M7 E.I. H.ATCH t%dT 2 EQU1PMENT SUPFGtTS
'ASME.
CLASS SUPPORT FIGURE NO HANGER TYPE RESULTS REPORT NO. INF NO. MWO NO. RESULTS REPORT No. REMARKS 2 2C41-A001-501 2C41-SK2 SUPPORT A S92N2Y146 2- 2C41-C001A-501 2C41-SK3 $UPPORT A $92H2V147
-3 2E11-C001A-S01 2E11-SK10 SUPPORT. A S92H2V148
-3 2E11-D002A-501 2E11-SK11 SUPPORT A $92H2V149
+ l 3 2P41-C001A-501 2P41-SK12 SijPPORT A $92H2V150 3 2P41-C002-501 2P41-SK13 SUPPORT A S92H2V151 [ t 3 2P41-0001A-501 2P41-SK14 $UPPORT A SY2H2V152 3 2P64-8006A-501 2P64-SK15 $UPPORT A 592H2V153 2 2T47-8008A-501 2T47-SL9 $UPPORT A S92H2V154 _ 2 2147-8009A-501 2T47-SK9 SUPPORT A S92H2V155
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SNUBBER SUPPORT EXAMINATIONS This section of the report provides a discussion of the visual examinations
= performed on snubber supports. -All safety . related snubbers were VT
['_Texaminedby-GPCQCpersonnelusing.GPCprocedure45QC-INS-012-OS (VT-3)..
'Y subject. examinations :were performed prior- to and during the,
- The Refueling /. Maintenance. Outage. The procedure and all- examination data sheets are available for review at the plant site.
Examinations Class _1 Eighty-two (82) snubbers from the B21, B31, Ell, E21, E41, E51, and G31 systems were visually examined. one indication was reported, but was evaluated as being acceptable hs-is. Class 2 One hundred fif ty- eight (158) snubbers from the Ell, E2'1, E41, E51, N11 and T48 systems were visually examined. Four indications were reported,:but were evaluated as being acceptable as-is. Class 3 Sixty-eight (68) snubbers from the B21, Ell, and G41 systems were visually examined. No unacceptable indications were detected.
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1992 E.1. HATCH UNIT 2 S E BERS ASME CLASS SUPPORT FIGURE NO HANGER TYPE RESULTS REPORT NO. INF NO. MWO NO. RESULYS REPORT NO. REMARKS 1 2831-SSA21 A-16/05 HYDRAULIC SNUBBER A N/A EXAMINED BY GPC QC 1 2831-SSA22 A-16/05 HYDRAULIC SNUB 8ER- A N/A . EXAMINED BY GPC QC 1 2831-SSAS A-16/05 HYDRAULIC SNUBBER A N/A EXAMINED BY GPC CC 1 2831-SSA7 A-16/05 HYDRAULIC SNUBBER A N/A EXAMINED BT GPC.OC 1 2831-SSA1 A-16/05 HYDRAULIC SNUBBER A N/A EXAMINED BY CPC OC 1 2831-SSA2 A-16/05 NYDRAULIC SNUBBER A N/A EXAMINED BY GPC QC 1 2831-SSA3 A-16/05 HYDRAULIC $ NUB 8ER A N/A EXAMINED BY GPC QC 1 2B31-SSA4 A-16/05 NYORAULIC SNUBBER A N/A EXAMINED BY CPC QC.. 1 2831-SSAS A-16/05 ' HYDRAULIC SNUBBER A N/A ~ EXAMINED BY CPC OC' 1 2831-SSA6 A-16/05 HYDRAULIC SNUSBER A N/A EXAMINED BY CPC QCl 1 2831-SSA14 A-17/4 HYDRAULIC SNUSBER A N/A EXAMINED BY CPC QC 1 2831-SSA17 A-17/4 NYDEAULIC SNUBBER A N/A ' EXAMINED'BY GPC CC 1 2831-SSA12 A-17/4 HYDRAULIC $NUBBER A N/A EXAMINED BY GPC QC. 1 2831-SSA13 A-17/4 HYDRAULIC SNUBBER A N/A EXAMINED BY CPC QC-1 2831-SSA20 A-17/4 H1DRAULIC SNUBBER A N/A ' EXAMINED BY CPC QC'. 1 2831-SSA19 A-17/4 HYDRAULIC SNUBBER. A. M/A EXAMINED BY GPC QC 1 2831-SSB21. A-18/05 HYDRAU'.IC SNUBSER. A- N/A EXAMINED BY CPC CC : 1 2831-SS822 A-18/05 . HYDRAULIC SNUBBER A N/A . EXAMINED BY'GPC OC' 1 2831-SsBS Ad8/05 HYDRAULIC SNUBBER A N/A EXAMINED BY GPC CC : 1 2831-S5B7 A+18/05' HYDRAULIC SNUBBER A~ N/A EXAMINED BY CPC QC _N . d
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.ASME;
-CLASS -SUPPCRT' ' FIGURE NO! - MANGER TYPE " PESULTS REPORT NO. INF NO. MWO No. RESULTS REPORT NO. REMARES'
; 2a31 S$si. 'A-18/05 MYDRAutic $NUBBER A N/A 2-92-5127 " EXAMINED 8Y CPC'OC.L
. REPLACED COTTER PIN.. -.
ACCEPTA8LE AS.lS
- 11 2831.SSB2 A-18/05 . HYDRAULIC SNLa8BER .-A N/A , EXMINED BY GPC QC
.1 2831 $5B3 A-18/05' MfDRAULIC SNURSER.- A N/A' EXAMINED SY GPC QC-
- 1 2831 S$84 .A-15/05 NYDRAULIC SNUBBER .A N/A- EXAMINED BY GPC QC/
-.1 2831-SSB5 A-18/05 HYDRAULIC SNUBBER A N/A EXAMINED SY GPC QC
,;m 1 M2531-S$86 .A-18/05 HYDRAULIC SNUB 8ER A N/A-. ' EXAMINED BY GPC OC.:..
!1 2831 S5s14 : M19/04 A N/A EXAMINED SY GPC OCI I HYDRAULIC ShUB8ER.
1 2831-sS817 A-19/04- ' HYDRAULIC SNUBBER A N/A EAAMINED,SY GPC OC 1 2331-SSB13- A-19/04 HYDRAOLIC $NU6SER' A N/A' L EXMINED BY GPC OC1
,1 2831-sSB12; A-19/04 HYDRAULIC SNUB 8ER 'A N/A ' EXAMINED BY.GPC OC' 1' ' '2531 S$820 J A-19/04 NYDRAUt!C sNuesER - Al N/A :ERAMINED BY GPC'OCt
- 1. . 2831-SSS19 .A-19/04- HYDRAULIC SNUBBER A. N/A EXAMINED BY.GPC OC)
L2- 2N11 Ms-R67 S-7/04 NYDRAULIC SNUB 8ER' A - N/A : EXMINED BY GPC OC". 2- - 2N11rMS-R71 .B-7/04 . . HYDRAULIC SNUBBER: AJ N/A' - EXMINED BY GPC OC ' L2 2W11 MS R72 lB-7/04 HYDRAul:C $8AJB8ER , A_ ' N/A - EXAMINED BY C7C OC:
- - 2 2N11-MS-R45 - .B-9/06, lNYDRAULICSNUSGER, i A .: N/A EXAMINED" 8Y _GPC QC ~
l22 '. 2N11-MS-R44. - 'B-9/061 HYDRAULIC SNUB 8ER.- -AJ 'N/A~ ~2-92 5005 - - EXAMINED BY GPC OC= BRtXEW t#IPER SEAL, ACCEPTASLE
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CLASS SUPPORT FIGtAE NO NAEGER TYPE RESULTS REPORT No. INF NO. MWO NO. RESULTS REPORT NO. REMARKS 2- 2N11 MS-R38 8-10/07 HYDRAULIC SNUBBER A N/A 2-92-5005 EXAMINED BY CPC OC'
.. RETORQUED LOOSE NUTS, ACCEP'ABLE AS IS m c 2-92-5823 2 2h11*MS R37 B-10/07' HYDRAULIC SNUBBER A N/A EXAMINED BY GPC OCH 2 2N11-MS*R93 B-10/07 HYDRAULIC SNUBBER A N/A EXAMINED SY.GPC OC' 2 2N11-MS-R41 8-10/07 HYDRAULIC $ NUB 8ER A N/A EXAMINED BY GPC OC-2 2N11-Hs-R42 B-10/07 HYDRAULIC SWOBSER A N/A t'XAMINED BY GPC QC 2 2N11-MS-R54 B-11/06 HYDRAUilC SNUSBER A N/A EXARINED BY GPC OC; 2 2N11-MS-R55 s-11/06 HvDR E11C SNUBBER' A N/A EXAMINED BY GPC CC 2 2N11-MS-R56 B-11/%
. HYDRAOLIC SNUB 8ER A N/A EXAMINED BY GPC CC - .
2 2N11-MS-R57 B-11/06 HYDRAULIC SNU8BER A N/A E*AMikED BY GPC QC 2 2W11 MS-R53 B-11/06 HYDRAULIC SNU8BER A. N/A 2-92-5005 EXAMINED BY GPC QC'
. OFF-CENTEP. SPHERICAL BEARING,
- ACCEPTABLE AS IS.
2 2N11-MS-259 8-11/06 HYDRAULIC SNUBBER A N/A 2-92-5005 EXAMINED BY GPC QC' OFF-CENTER SPHERICAL BEARIWG, ACCEPTABLE AS 15.. . 2 2N11-MS-R49 8-12/06 NYDRAltlC SNUBBER A N/A EXAMINED BY GPC QC 2 2N11-MS-R50 B-12/06 HYDRAULIC SNUPBER A N/A EXAMINED BY.GPC OC l Z' 2N11-MS-R51 B-12/06 NYDRAULIC SNUBBER A N/A EXAMINED BY GPC OC 2 2N11-MS-R91 B-12/06 HYDRAULIC SNUaBER A N/A - EXAMINED BY GPC CC 2 - 2N11-MS-R53 8-12/06 HYDRAULIC SaiUBBER ' A. N/A - EXAMINED BY GPC CC
- j. 2 . 2E11-RFR-RSS B-17/06 NYCRAOLIC M tSBER A'- N/A ' _ EXAMINED BY GPC QC'
! N 2~ 2E11-RNR-9901 -B-17/06_ HYDRAULIC $NUESER 'A N/A : EXAMtWED SY GPC QC e
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- 2 l
EXAMIEED BY GPC QC j 5-32/04 MYDRAuttC suussER A w/A 2 2E11-RNR-R378 ! EXMINED $Y GPC CC 6-32/u4 MCRAULIC SESBER A N/A 2 2E11-RkP-R377 h/A EXAM! SED BY GPC OC B-33/t% wrDRAu;1C SNUESEC A 2 2E11-RMR-RZ76 EM18thED BY GFC GC 8-33/04 N CRAULIC SMUBPER A N/A 2 2E11-Retr-R377 DAN;EED BY GPC QC ] 8-34/05 NYDRAULIC SutMeER A N/A 2 2E11-Rr!R-R86 EXAMINED BY GPC CC 5-34/05 MYDRAULIC s*J3BER A m/A l 2 2E11-RMR-R93 E7AMINED BY CPC 0C . 2E11-RNR-R231 s-35/04 MYDRAtAtt swJs&ER A a/A 2 EXMikED BY GPC QC 2E11-sNR-R241 s-36/06 MYDRAULIC suus&ER A s/A 2 EXAMIEED SY sPC EC s-37/04 uvDRAULIC sML68ER A N/a 2 2E11-RMR-R238 EXAMin e af GPC aC 8-38/04 NYDRAuttC sut M R A m/A 2 2E11-RHa-R245 EEAMIG SY CPC QC 2E11-RNR-R315 B-39/04 MYDRAULIC suuGBER A s/A 2 A w/A N :hED SY GFi DC 2 2E11-RNR-R252 2-40/04 NYDR4<JLIC SMJESER EXAM!WED BY GPC CC 6-4C/04 WYDRa9L C SNLSSER A t/A 2 2E11-RNR-R253 EXAMikED BY GM CC 8-43/03 >YDitAuLIC $wJEeER A ei/A 2 2E11-RMR-R223 EXAM!uED BY GPC cc NYDEAutIC seussIn A m/A 2 ZE11-RhR-4270 s-46/02 ERAMIEE0 SY CPC CC 8-46/02 NYDRAULIC $WJESER A S/A 2 ZE11-RNR-R271 EI MiwED BY GPC OC E-49/0/. RYDRAULic Sele.EER A N/A 2 2E11-RuR-R227
'XM: tid sY EPC cc s-56/07 NYDaAOLIC Sv.F,BER A N/A 2 2E21-Cs-R53 EXAMINED SY GPC QC -
B-59/05 hvDRAULIC swusGER A N/A 2 2E21-CS-R72 , U1 _ _ 4
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.Ct. ASS StPPORT 'F!CUEE hO MANOEt TYPE RESULTS REPORT WO. l#F 20. MWD PG. RESULTS REPCRi WC. REMAM S 2 2E21-CS-t E d-6cA103 aYDRAULIC SuuGBER A N/A EXAMIkG EY GPC CC
- 2. 2E21-CS-R80 s-60s/03 NfDRAULIC GFJRBER A N/A $xAM:5FC 4Y CPC CC 2 2E21-CS-n40 B-62/04 NYDRAULit SNUB 8ER A N/A EKA*!sEC BT GPC DC _
2~ 2E21-CS-R87 s-64/05 RTCRAULIC SNUB 5ER A N/A EXAM'4ED SY GPC C
.2 2T48-CruR-R50 .s-75/03 NTDRAULIC SNUEBER A W/A ETAM15ED sY CPC GC 2 -2T48-CPUR-R49 B-73/03 NYDEAdLIC SquBGER A N/A D&MINCD BY C4 Ci 2 2T48-CPUR-R15 s-80/03 NYDRAULIC SdJEisER A h/A EXAM 85 D BY GPC QC 2 2T45-CPUR-3t14 s-89/03 NYDRAutic SW BEER A N/A E'/Jt!5ED ST GPC CC 3 2E11-RSW-R15 ~ C-7/02 NYCRAutic SsfJBBER A N/A E m ;grD Ef GPC QC 3 2E11-RSu-R23 C-8/02 NYDR4JLtc SMUBBER A h/A EXananED BY @ C OC 3' 2G41-FPC-R114 C-105/2 MYDRAULIC EmuBBER A W/A EXAwfu s sY GPC 2C 1 2821-MS-R45 A-6/05 MECH S$JSEER A N/A EXAM 7C D BY CPC CC 1 2B21-MS-R46 A-6/05 MECM SWursBEe A E/A EvtJat%C5 3Y CDC QC 1 2321-MS-R47 A-6/05 MECH SWUliSER A N/A EIA?!ktD BY CPC QC 1 2821-MS-R48 A-6/05 NECri SNUB 3ER A N/A DAMINED BY CPC CC 1 2821-MS-R49 A-7/06 MECH $MLEEER - A N/A E14AIEQ B* GK CC 1 2B21-MS R53 A-7/00 P:E3 SNUFER A N/A EXAM!ufD BY CPC QC :
1 2321-MS-RS2' A-7/06 MECH SWUC8ER A */ A . EXAMitEC t? Crc w 1 2821-MS-R53 A-7/06T - mE3 SWJBSER /- EjA E%eMin59 SY GPC OC ' 1 2821-MS-R54 A-7/06- MECII SNL*.4!Et A N/A E3AMiWE9 97 GPC CC -
^ ' ! 1 2B21-MS-R53 A-7/06 MECE SaiUBBER A' W/A' EIAMikED SY CPC QC M
i v 1992 E.I. e.2TCd L*iti 2 Sat *sERS
'ASME REWALK3 IET 20. sr.O 2C. RESI.2TS mEPORT t.C.
SUPPORT FIGURE WG MAEGER TYPE REST 1TS REPORT wo. CLAE$ EXAn a !.CD $7 GPC CC A-8/07 M Cn Ew esER A 4/A 1 2821-N*-R38 EKAM!M G SY CPC QC A-3/07 MECM SudBSER A W/A 1 2821-MS-R39 l EXAM! SED BY GPC CC A-8/O' MECE SMSSER A N/A 1 2B21-MS-R41 Eves;sito Y cpC :- A-8/07 MECH SMU4sER A w/A 1 222!-MS-R43 ! EXAM;WED BY GPC CC l A a/07 MECW SWSBER A N/A 1 2E21-*S-RC2 l Er4MlWED BY CPC 9C 'l A-3/0? MEcs SwUe8ER A N/A l 1 2821-Ms-R44 l EXAMI 6 BY GPC QC A-9/06 MECM SWUBBER A. W/A 1 2B21 -r-RM l
- EXMIEED BY GPC CC A-9/06 MECM SNUSEER A t/A 1 2321-MS-R35 ERAM14ED ST CPC QC 1 2421 MS-R34 A-9/06 MECM SNUBsER A s/8 EXAH1kED BY F C OC A-9/06 MECW SwdB5ER A N/A I
1 2821-r-R37 EXAMIC BY CPC QC A-10/Os MECM SWJBBER A W/A 1 2821-RFW-R31 l ExM:=ED sv GPC CC 2B21-Rf4-R2": A-11/05 MECn swasER A s/A t EKAMikE-- BY GPC CC A-21/05 MECM SWEBE?. A iU4 l 1 2E11-RHR-R338 EIMlO SY GFC CC A-21/c5 MECW SNUSBER A N/A 1 2E1'e -E::9-R339 i EXAMIkED BY F QC A-21/05 MECM SwusaER A N/A 1 2E11-RNR .'K O l- JXAMI%ED SY GPC CC A-21/r3 MEC7 SNUESER A N/A l 1 2E11-RHR-R342 l EXAMtht:D SY CPC OC A-22/05 MECli SWESER A h/A 1 2E11-RNR-R353 E7Dt1EED BY GPC QC A-22/C5 MECM SWUSBER A N/A 1 2Eti-MMR-R354 L EJP. KED SY CPC CC A-22/C5 MECM $* S891 A N/A I - . . 1 2E11-RHR-R352 ) l EXAM 1=ED SY CPC cc A-22/05 MECW SWBsER A r/A l 1 2Ett-RHR-R351 ERAMikED SY CPC CC A-22/05 MECW SMUBBER A .E/A 1 2E11-anR-R355 N N _
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REACTOR: PRESSURE VESSEL - ( l I , INTERNAL INSPECTIONS l. 1
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1992 REACTOR PRESSURE VESSEL' INTERNALS This section of tho' report provides-a summary of the remote visual
-examinations performed by SFC and GE on selected EpV internals _and remoto.
/ UT of vessel shroud-support ledge access. covers at_ azimuth O degrees and -
180 degrees. The visual examinations were performed using SNC procedure
--VT-H-750 Rev.3. This procedure incorporates requirements for ASME Section XI, GE Se Vice Inforuation Letters and NUREG/CR-4523.
All visual examination tapes were reviewed-Dy SNC or GE certified level' II and/or III visual examincrs to determino the acceptability of the l Various RPV internal components. CORE STE]LLEPARGIE_.IJifTIST10"
'l Per the requirements of NURi .41-4523, the core spray spargers and nssociated pip 3ng were visuo .ty examined. Underwater video equipment recorded the examination results to the resolution of a .001 inch diameterL visual acuity stnndard. !
No reportable indications were found. I ETEAM D8yIF _IlmpfcqTLqt{ Remote viaval examinations were performed on various components of the l steam dryer which consisted of; support ring, stiffeners and stiffener._ l welds, vertical vano bank welds, support bracket weld 0 24,.146, 214, and j 326 day., and-the lifting eye and rod. ' Indications were found at various locations in the vessel and on the steam ; drycr. Plant personnel conducted an " Event Review" to determine the most likely causa in conjunction with GE engineering and SNC personnel. The indiwtions were attributed to an off-center lift of the steam dryer during i vessel disaasembly. , Indications were reported on vessel dryer support lug at azimuths 145,'216,: . and 325 degrees and the correspunding steam dryer ueismic brackets at azimuth 145 and 215 degroes. Two vessel dryer lugs .-(azimuth 2 45 and 1215; > degrees) -were repaired under MWO 2-92-5156. using GE developed _ remote ~ tooling. The azimuth 325 degrees lug and the steam dryer seismic brackets , were dispositioned for use "as is" by GE engineering. Indications also attributed to the off-center steam dryer lift were detected on.the Steam. Dryor upper _ bank at azimuth 130 degrees and an upper guidec rod bracket attachment weld. These were dispositioned acceptable "as ie" for continued operation. Indications that were not attributed to lifting the staan dryor - were detected on steam dryer plate material adjacent to dryer bank weld numbers - 12, 27 and 32. All were accepted for continued.uperation "as is" Mith future monitoring requested. No other reportable indications were found.- l P
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- Accoso Cover Holds at azimuth 0 and 180 degrees. UT examinations utilized -l GE developed = equipment and procedures. Two non-geomotric planar '
indications woro discovorod on the 180 degroo cover. An analysin performed by GE Nuclear Energy resulted in a disposition to continue operation "su- , is". No recordable indications woro found on the azimuth 0 degrno cover wold. No recordablo indications woro found visually,at either location. EEEREBT.CH_H2RGER INSPECTION l ,- Remote visual examination was performed on the foodwater spargora and , sparger bracket attachmont volda at 45, 135, 222,--and 315 degroes. Dobris was dincovered in a aparger nozzle and slight damage to another nozzle at l , azimuth 45 dagroco. The debris was removed and analysis performed to -t i determino material. The damago was dispositioned aa acceptable as is'for
- continued operation. In addition a damaged tack weld on a feedwater sparger bracket nut wac detected. This was accepted as in with futuro
- monitoring requested. ,
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IGEAIRs _ AnD REPIAcrMt201 GPC procedure 42EN-ENG-014-OS provides guidelines for determining the ASME Section XI, Repair / Replacement requirements at E.I. Hatch Nuclear ( Plant. The site Repair / Replacement Coordinator maintains an itemized listing of Class 1 and 2 Repair ieplacement activities for each cycle. The following tables provide an temized list of those components which were included in the ASME Sect.,3n XI Repair and Replacement Prograra. (Class 3 items included for information only) Copies of the individual Repair / Replacement Evaluation Sheets are filed with the MWO Packages and are availabic for review at the sito. V 94
REPAIR AND REPLACEMENT PAGE:1
'Ay,) UNIT 2 OUTAGE 1992 MWO 2-92-80 REV. 1 HPL 2P41-C0010 ASME CLASS:III COMPONENT: SERVICE WATER PUMP ASME SECTION Y1 CLASS III PROBLEM: COMPONENTS OF PUHP TO BE REPLACED DUE TO~PUNP PERFORMANCE NOT' RELATED TO R/R REQUIREHENTS.
DC NUMBER:2-92-03 EVALUATION:LIEE IN EIND REPLACEMENT WITil ORIGINAL VENDOR SUPPLIED PARTS HEETS REPAIR / REPLACEMENT CRITERIA.
\/ CODE NDE:N/A PRESSURE TEST:N/A MWO:2-93-3338 HPL:2P41-C001B-ASHE CLASS:III COMPONENT: SERVICE WATER PUNP ASHE SECTION XI CLASS:III PROBLEH:5YR. PH ON SUBJECT PUHP AND HOTOR WILL RENEW Tile PUMP BOWL
. ASSEMBLY.
DC-NUMBER:N/A EVALUATION: REPLACEMENT OF T11E BOWL ASSEMBLY AND COLUMN SHAFTING IS
.gsSUITABLE. FACTORY PARTS OF CODE MATERIALS ARE BEING UTILIZED IN ACCORDANCE WITH IIXISTING PLANT PROCEDURES.
CODE NDE:N/A PRESSURE TEST:N/A 95; }
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'PAGE 2 HWO 2-92-0676 MPL:2E11-F031D:
ASHE CLASS:II COMPONENT: VALVE-ASME SECTION XI CLASS:II PROBLEM: REPLACE DISC. DC NIMBER 2-92-0685 EVALUATION: DISC IS REPLACEMENT IN EIND.BEING REPLACED USING THE' PROPER __ PROCEDURES FOR TilIS TYPE MAINTENANCE. CAUSE OF FAILURE IS UNKNOWN AT THIS: !. TIME. CODE NDE:N/A PRESSURE TEST N/A'
\
HWO:2-92-6301 HPL:2E11-RHR-R84 ASME CLASS:III- COMPONENT RESTRAINT-ASME SECTION XI CLASS:III PROBLEM: REMOVAL OF-- INDICATION FOUND .ON LUG TO PIPE ATTACHMENT WELD-FOUND DURING. ISI INSPECTION.-REMOVAL TO BE-PERFORMED BY CHIPPING, GRINDING? OR BUFFING. DC NUMBER:2-92-3282 EVALUATION TAKE' OUT DEFECT BY CHIPPING OR GRINDING. CAUSED AT THE END
.0F THE WELDING PASS OF LUG TP PIPE. APPEARS TO-BE' CRATER. CRACK.
h CODE NDE:VT-3 PRESSURE TEST:N/A> COMMENT: BUFFING ONLY-REQUIRED TO REMOVE' INDICATION. 5 c . _ s96)
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~'T MWO: 2-92-5346 HPL:2B21-MSRV H-15 PAGE 3.
ASHE CLASS:III COMPONENT: SPRING CAN HANGER ASHE SECTION XI CLASS:III PROBLEM: SPRING CAN RANGER IS OUT OF TOLERANCE. ADJUST TO PROPER SETTINO. DC NUMBER;2-92-3312 EVALUATION: SPRING CAN liANGERS ARE ADJUSTED PERIODICALLY. DUE TO PIPE-HOVEMENT TilEY SOMETIMES GET OUT OF TOLERANCE SETTINGS. TIIIS IS AN ACCEPTED HETilOD OF BRINGING Tile CAN BACK INTO TOLERANCE. FINDINGS OF Tills TYPd ARE , TO DE EXPECTED FROH TIME TO TIME. NO RESETTING WAS REQUIRED (ENG. EVAL) CN I g CODE NDE:VT-4 PRESSURE TEST:N/A HWO:2-92-4406 HPL:2T46 ASHE CLASS:III COMPONENT: PIPING ASME SECTION XI CLASS:III PROBLEM: INSTALL A 20" BY 20" BY 18" TEE IN THE SDGT TRAIN DISCl!ARGE TO T}{E STACK PIPING BETWEEN 2T46-F002A AND Tile MAIN STACE. DC NUMBER:N/A EVALUATION:TIIIS TEE IS BEING INSTALLED BY DCR 2}l89-282 - l AND ITS SUSITABLITY WILL BE EVALUATED BY TilAT DCR. PRESSURE TEST OPERATING-PRESSURE g'( j/ CODE NDE:HT 97
m i
\s) PAGE: 4 MWO:2-92-3613 HPL:2P41-F321 ASME CLASS III COMPONENT: CHECK VALVE ASME SECTION XI CLASS:III PROBLEM: DISC STUD ON DISC IS WORN.
DC NUMBER:2-92-3340 EVALUATION: REPLACEMENT OF VALVE DISC IS AN APPROPRIATE REPLACEMENT. WEAR IS NORMAL FOR SERVICE WATER SYSTEM. CON NDE:N/A PRESSURE TEST:HWO FUNTIONAL f R a
'v) MWO:2-92-4538 HPL:2C41-C001A ASME CLASS:II COMPONENT:PUNP ASHE SECTION XI CLASS:II PROBLEM: VALVE DISC COMPONENT OF SBLC .PUHP IS WORN' AND- NEEDS REPLACING.
DC NUMBER:2-92-2567 EVALUATION: REPLACEMENT OF WORN DISC IS SUITABLE : CORRECTIVE. ACTION. PART WEAR APPEARS TO BE DUE.TO NORMAL USAGE. CODE NDE:N/A PRESSURE TEST:N/A a .
- . .~
. . 9.8
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HWO:2-92-04015 HPL 2E11-RilRSW-F209B ASHE CLASS:III COMPONENT: AIR RELEASE VALVE ASHE SECTION XI CLASS III PROBLEH: REPLACE JoltNSTON AIR RELEAFE VALVE WITH CRISPIN HULTIPLEX AIR RELEASE VLAVE PER DCR 21189-238. DC NUMBER:2-92-2141 EVALUATION: REPLACEMENT VALVE IS AN UPGRADE OF THE SYSTEH. JOllNSTON-VALVES IIAVE A llISTORY OF FAILURE. CRISPIN IS A HORE RELIABLE VALVE FOR TiiIS TYPE SERVICE. CO.E NDE:N/A PRESSURE-TEST:N/A \ HWO:2-91-4794 HPL:2E11-F209A ASME CLASS:III COMPONENT: AIR RELEASE VAbid ASHE SECTION XI CLASS:III PROBLEN: AIR RELEASE VALVE DOES NOT SEAT OFF CLOSED WilEN: OPERATING- 2A OR 2C RHRSW PUMPS. DC NUHBER:2-91-4721 EVALUATION: FAILURE IS 'DUE TO NORMAL COMPONENT WEAR. REPLACEMENT IS WITil EXACT REPLACEMENT PARTS. s CODE NDE:N/A. PRESSURE TEST:HWO FUNCTIONAL. k 99
3 I PAGEt6 ; ( HWO:2-92-1611 HPL 2E11-RSW-R702 l ASHE CLASS:III COMPONENTtPIPE SUPPORT ASME SECTION XI CLASS:III PROBLEM INSTALL NEW SUPPORT ON THE RHRSW HIN. FLOW LINE BETWEEN PUNP-2E11-C001A AND THE HIN FLOW CONTROL VALVE 2E11-F207A. DC NUMBER:N/A EVALUATION:THIS WORE IS BEING PERFORHED UNDER DCR 2H89-146 AND THE SUITABb1TY OF THE REPLACEMENT WILL BE EVALUATED BY THAT DCR. CODE NDE:VT-3 PRESSURE TEST:N/A
/N ,
' Q) HWO:2-92-1611 HPL:2E11-RSW-R705-ASME CLASS:III COMPONENT: PIPE SUPPORT ASHE SECTION XI CLASS:III PROBLEM INSTALL NEW SUPPORT ON THE RHRSW HIN FLOW LINE DETWEEN PUMP 2E11-C001D AND THE HIN FLOW CONTROL VALVE 2E11-F207D. DC NUMBER:N/A EVALUATION:THIS WORE IS BEING PERFORHED UNDER DCR 2H89-146 AND THE , SUITABLITY OF THE REPLACEMENT WILL BE EVALUATED BY THAT DCR.
-CODE NDE:VT-3 G
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, '~' i x_ PAGE 8 DC NUMBER:2-91-4599,2-92-0854,2-91-4689 EVALUATION: STEAM CUT SURFACES ON SEAT WILL BE REMOVED BY'DEXTERING THE SURFACE AREA. ST*LLITE 6 ON DISC WIL BE REMOVED. STAINLESS STEEL AND STELLITE 21 WILL BE APPLIED PER APPROVED DCR 89-400. CODE NDE:N/A PRESSURE TEST LEAEAGE TEST HWO:2-92-5493 HPL:2E11-F122B ASME CLASS:1- COMPONENT: VALVE ASME SECTION XI CLASS:I PROBLEM: REPLACE SEATS, DISC AND STEM ON REFERENCED VALVE. DC NUMBER:2-92-3498 EVALUATION:REPLACEHENT OF SEATS, DISC AND STEM ETC. IS A SUITABLE HETHOD OF REPAIR TO BRING VALVE TO DESIGN REQUIREHENTS. APPROVED PROCEDURES AND PROCUREMENT PROCEDURES ARE BEING FOLLOWED. CAUSE OF FAILURE APPEARS TO BE NORMAL FOR SYSTEM SERVICE. CODE NDE:N/A PRESSURE TEST: TEST DURING VESSEL PRESSURE TEST. V 10 2
~ _ _ , er ,
-g PAGE 9 HWO:2-92-198 HPL 2B21-F016 ASHE s, LASS:I COMPONENT: MAIN STEAM LINE DRAIN ASME LECTION XI CLASS:I PROBLEM: WEDGE FOR VALVE HAS CRACK ACROSS STELLITE AT 12:00. WEDGE TO DE REPLACED.
DC NUMBER:N/A EVALUATION: WEDGE USED FOR REPLACEMENT IS A CLASS I PART PROCURED FOR CLAOS 1 AND IS FOR THE nBOVE MENTIONED VALVE. CODE NDE:N/A FdESSURE TEST: TEST DUP.ING VESSEL
) PRESSURE TEST. -) .
HWO:2-92-3940 MPL:2E11-D002A,B AD003A&B ASHE CLASS:III COMPONENT: STRAINERS ASME SECTION XI CLASS:III PROBLEM: MACHINE COVER AND BODv. DC NUMBER:2-92-1625 EVALUATION:PER DESIGN ENGINEERING, REMOVAL OF HETAL BY MACHINING IS A SUITABLE REPAIR. CAUSE OF FAILURE IS EXTENDED EXPOSURE TO HARSH RIVER WATER i ,'2NVI RONM E NT . 2E11 D003A AND B DELETED FROM WORE SCOPE. CODE NDE:N/A PRESSURE TEST:N/A E-_ __ 10 3 J
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, _ . .g WWO:2-92-5105 MPL:2P41-F088E ASME CLASS:III -COMPONENT: VALVE 4 "b 79 ASME SECTION XI CLASS:III- .
;, 1- s PROBLEM:THE- WEDGE HAS LIGHT PITTING ANDcIS TOIBE MACHINED TO REMOVEf IT. STEM IS ERRODED IN PACKING AREA AND!WILL BE MACHINEDO BONNET NUTS $AND J.
. BOLTS ARE. CORRODED--AND ARE TO DE REPLACED.-
DC NUMBER:2-92-3345 l t REPAIRS' ADVERSELY ; AFFECT; THE' _ PRESSURE-EVALUATION:NONE' OF THE BOUNDARY. THE- ERkODED STEM. AT THE STUFFING: BOX AREA-AND CORRODED > BONNET I - e Q ARE DUE . TO ' AN APPARENT PACKING : LEAK. LAPPING. OF- WEDGE WILL R d g. JOLTS SEATING CAPABLITY. (NO REPAIR WAS-PERFORMED PER ENGINEERING EVALUATION) ] CODF NDE:N/A PRSSSURE TEST:N/A: c MWO:2-91-2205 .MPLi2B211 r ASME CLASS:III COMPONENT: SUPPORT H-8' ASME SECTION XI CLASS:III -
-PROBLEM: SPRING-CAN FOR THIS SUPPORT IS DAMAGED.-R'EPLACE.
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- DC NUMBER
- 2-91-2029-EVALUATION: SPRING CAN.AND ROD WILL BE REPLACED LIKE IN KIND.-CAUSE OF- ,
DAMAMGE WAS DUE TO' SEVERE ARC STRIKE ON SPRING COIL. - y - CODE NDE: VT-3~ PRESSURE TEST:N/A , gt 105
- m. . . . .. . . . . _ . :
,- y PAGE:12 HWO 2-92-4176 REV. 1- MPL:2P41-F006A-
. . 1 ASME CLASS:III ~ COMPONENT: VALVE ASME SECTION XI CLASS:III PROBLEM: VALVE DISC HAS SEPARATED FROM' -STEMLAND IS CORRODED BEYOND-USE. REPLACE DISC.
DC NUMBER:2-92-2267
~
EVALUATION: DISC IS A CLASS III PROCURED COMPONENT BEING REPLACED USING: APPROVED PROCEDURE. TIIIS IS A SUITABLE HETHOD OF REPLACEMENT. FAILURE IS' DUE TO EXPOSURE TO A HARSH ENVIRONMENT (RIVER WATER) CODE NDE:N/A PRESSURE TEST:MWO FUNCTIONAL.-
)
o MWO:2-92-5156 -MPL:2B11 ASME CLASS:I COMPONENT:RPV DRYER-SUPPORT LUGS. ASME SECTION XI CLASS:I P510BLEM : BLEND RAISED METAL ON THE TOP OF DRYER-SUPPORT LUGS AT 146-DEGREES AND 214 DEGREE AZIMUTH. GRIND RAISED METAL FLUSH WITH TOP SURFACE: OF LUG. DC NUMBER:2-92-3106 EVALUATION: GRINDING RAISED METAL FLUSH WITH SURROUNDING SURFACE WILL ( ALLOW STEAM DRYER TO SEAT PROPERLY. STRUCTURAL INTEGRITY OF DRYER /RPV NOT
-AFFECTED.
CODE NDE:VT-3 PRESSURE TEST:N/A 10 6:
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1 4 ("~*}l ,' X) PAGE:13-MWO:2-92-3611 MPL:2C41-F033B ,l 4 ASME CLASS:II COMPONENT: VALVE' ASME SECTION XI CLASS:II PROBLEM REPLACE EXISTING VALVE W)TH, IDENTICAL NEW VALVE.~
-m DC NUMBER:N/A EVALUATION:TllE VALVE IS BEING HEPLACED=BECAUSE ITS IINSPECTION PLUG CAN:
~
NOT BE REMOVED. INDENTICAL REPLACEMENT IS EXPECTED TO_llAVE NO OPERATIONAL. 7-- IMPACT ON THE SYSTEM,BUT SHOULD ALLOW-FOR FUTURE INSPECTIONS.
\ ) CODE NDE: SURFACE PRESSURE TEST; HYDROSTATIC' _
MWO:2-92-5258 MPL:2B21-F010B ASME CLASS:I- COMPONENT: VALVE ASME SECTION XI CLASS:I-r PROBLEM: REPLACE DISC IN 2B21-F010B, DC NUMBER:2-92-3237 EVALUATION: REPLACEMENT OF DISC IS A' NORMAL METH6D'dF REPAIR-TO RETURN-VALVE TO DESIGN CRITERIA. CAUSE OF FAYLURE IS TO'BE EXPECTED ON'LLRT, TYPE VALVES DUE TO T11E RIDGE REQUIREMENTS FOR LEAKAGE AND THE SERVICE THESE-TYPE'
~ .\jVALVESSEEDURINGOPERATION.
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- ASME CLASS:III; : COMPONENT:PIPINO: 4 ASME SECTION-XI CLASS;III PP.OBLEM: REPLACE . PIPING AS REQUIRED TO'ASSUREiPIPING IS WITHIN$ CODED-
- LIMITS FOR WALL' THICKNESS AND REMOVE LEAKING : PIPE. - , r DC NUMBER:2-92 1407-EVALUATION: REPLACEMENT OF PIPING IS-BEING PERFORMED-lUNDER CONTROLLED-WELDING AND PROCUREMENT . PROCEDURES. THIS' IS A SUITABLE- HETHOD..'OF' REPLACEMENT FOR THIS--PROBLEM. CAUSE OF FAILURE 4IS EXTENDED USE IN1A!HARSN) P RIVER WATER.ENVIHONMENT. 1 CODE NDE: VISUAL PRESSURE-TEST: HYDROSTATIC 4: a. L r MWO:2-92-5373 MPL:2T23-X20~,X61B,X229,X232: ASME CLASS:III NE -COMPONENT: PENETRATIONS:- ASME SECTION=XI CLASS: MC [ p PROBLEM:THE EXISTING -PENETRATION CAPS DO NOT NEET~THEeREQUIRED ASME? CODE. l. I, DC' NUMBER N/A
-. EVALUATION:TO CONFIRM THE REQUIRED ASME CODE PER PLANT DESIGN. NO-1 1
l INSERVICE PROBLEM INVOLVED. f;['- - CODE NDE: SURFACE AND VT-2 PRESSURE TEST: SNOOP.DURING ILRT. IL L .. . . , _ l.O8 L
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. SERVICE INDUCED FROBLEM INVOLVED.
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p ; <- 1: HWO:2-92-4130 ~MPL:2T23-X222A , . t ASME CLASS:III,NE- COMPONENT $PENETRATIbN-~ f a ASME SECTION-XI CLASS:MC h PROBLEM: INSTALL.ASME~ QUALIFIED SEALLON PENETRATION.- ni DC NUMBER:N/A l P T EVALUATION: SEAL. IS NOTL.' AN -APPROVED SEAL. NEW SEAL WILL1BEiAPPROVEDJ ASME: SEAL. NO FAILURE: INVOLVED ~EXCEPT ADMINISTRATIVEJFAILURE TO" INSTALL:
-CORRECT SEAL DURINGLCONSTRUCTION.
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' CODE NDE: SURFACE AND VT-2 h .
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4 1 _ .;-x ( v f / PAGE:165 MWO:2-92-5376 MPL:2T23-X107A ASME CLASS:III NE COMPONENT: PENETRATION' ASME SECTION XI CLASS:MC PROBLEH:THE EXISTING PENETRATION CAP DOES NOT MEET Tile - REQUIRED ASME CODE. DC NUMBER:N/A EVALUATION:TO CONFIRH Tile REQUIRED ASHE CODE PER - PLANT DESIGN.
. NO IUSERVICE FAILURE INVOLVED.
CODE NDE: SURFACE AND VT-2 PRESSURE TEST: SNOOP DURING ILRT. + (
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HWO:2-92-6375 MPL:2T23-I36: ASME CODE:III NE COMPONENT: PENETRATION ASHE SECTION.XI CODE: HC i PROBLEM :TIIE EXISTING PENETRATION CAP DOES NOT MEET Tile - REQUIRED ASME CODE. DC NUMBER:N/A EVALUATION:TO CONFIRM TIIE REQUIRED ASME CODE PER PLANT DESIGN. CODE NDE: SURFACE AND VT-2 PHESSURE TEST:SNDOP DURING'ILRT p s N
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ASHE CLASS III NE COMPONENT: PENETRATION-ASME SECTION XI CLASS: HC PROBLEM:THE EXISTING PENETRATION CAP DOES NOT HEET -ASME.. CODE REQUIREMENTS. DC NUMRER:N/A EVALUATION:TO CONFIRM THE REQUIRED ASHE CODE PER PLANT DESIGN. NO INSERVICE FAILURE INVOLVED. , CODE NDE: SURFACE AND VT-2 . PRESSURE TEST: SNOOP DURING ILRTL 7-~y w. i-HWO:2-92-5379 MPL:2T23-X206E,X65,X206G,X217D-227A
-ASME CLASS:III NE COMPONENT: PENETRATION:
ASME SECTION XI CLASS: HC e PROBLEH:THE EXISTING PENETRATION . CAPS DO 'NOT MEET ASHE CODE REQUIREMENTS. DC NUMBER:N/A EVALUATION:TO CONFIRH THE REQUIRED ASHE CODE PER P~ ANT DESIGN. NO-
; .(INSER"ICC F,*.ILURE INVOLVED.
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(s_- ) .PAGE 18 MWO:2-92-2172 HPhi2P41-F002A ASME CLASS:III COMPONENT: VALVE. ASME SFCTION XI CLASS: III PROBLEM: VALVE LEAES BY SEAT.
. 1 DC NUMBER: 2-91-1925 EVALUATION: REPLACE BONNET ASSEMBLY ~WITH DONNET FROH' NEW COMPLETE VALVE. DAMAGE INCURRED FROM NORMAL OPERATION OF IIARSU -RIVER WATER..
ENVIRONMENT. PRESSURE TEST:MWO FUNCTIONAL: ("'N) CODE NDE*N/A
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MWO:2-91-2172 HPL;2P41-F042A ASME CLASS:III COMPONENT: VALVE ASMF SECTION XI CLASS:III PROBLEM: VALVE LEAKS BY SEAT. Tile LIP IN THE VALVE' BODY THAT SUPPORTS TIIE SEAT HAS BEEN ERODED IN SOME PARTS BY TIIE SILT CONTAINED IN Tile-PLANT SERVICE WATSR. l DC NUMBER:2-91-1985 EVALUATION: VALVE LIP.IN THE VALVE BODY,TRAT SUPPORTS Tile SEAT HAS BEEN
'ERODEL AT THE VALVE INLET BY TIIE SILT IN THE PSW. WELDING OF.THE-ERODED-WITH A HARDER CHROME-MOLY ALLOY AND THEN MACHINING IS A SUITABLE
-[']PART
'% - REPAIR.
CODE NDE:N/A PRESSURE TEST:N/A l
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x, / MWO:2-91-2340 MPL:2P41-F003A. ASME CLASS:III COMPONENT: VALVE ASME SECTION XI CLASS:III PROBLEM: VALVE IS LEAEING BY SEAT WHEN CLOSED.. DC NIMBER:2-91-2195 i EVALUATION:HACHINE THE BONNET AND SKIM CUT THE: BACKSEAT TO REDUCE SEALING (GASEET) SURFACE. CODE NDE:N/A PRESSURE TEST:MWO FUNCTIONAL
- N /
MWO:2-90-2386 MPL:2T49-F009B ASME CLASS:Il COMPONENT: VALVE ASME SECTION XI CLASS:II PROBLEM: REPLACE BODY. HOLE IN BODY. DC NUMBER:2-86-627 EVALUATION: DEFECT NOT SERVICE INDUCED / CASTING FLAW. CODE NDE: SURFACE -PRESSURE TEST:MWO FUNCTIONAll.
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\~" .PAGE:20 MWO:2-92-3617 HPL:2P41-F098 ASHE CLASS:III COMPONENT: VALVE AS!!E SECTION XI CLASS:III PROBLEM: REPLACE INTERNALS OF VALVE AS SHOWN ON HWO.
DC NUMBER:N/A EVALUATION: REPLACEMENT- OF VALVE INTERNALS IS A NORMAL-HAINTENANCE~ 7 ACTIVITY TO BE PERFORHD BY HAINTENANCE UNDER APPROVED PROCEDURES. CAUSE OF FAILURE IS EXTENDED EXPOSURE TO HARSH RIVER WATER ENVIRONMENT. s CODE NDE:N/A PRESSURE TEST: VISUAL LEAE CHECE AT SYSTEM PRESSURE, NORMAL FUNCTIONAL TEST.- - HWO:2-92-5311 HPL:2E11-RHR-R352A ASME CLASS:II COMPONENT:SNUBDER s ASME SECTION XI CLASS:II PROBLEM: REPLACE LOCKED UP PSA SNUBBER WITil ANOTHER UNIT. DC NUMBER:2-92-3305 EVALUATION: REPLACEMENT SNUBBER IS ' IDENTICAL TO UNIT BEING: REPLACED. CAUSE OF FAILURE WAS BAAED GREASE. , fS PRESSURE TEST:N/A
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PAGE:21 HWO:2-92-5181 HPL:2L35/2E11-RHR-R285A,R50A ASME CLASS:II AND.2N11-MS-3 ASME SECTION XI CLASS:II COMPONENT: SNUBBER PROBLEM: SNUBBER 2E11 RHR R285A FAILED FUNCTIONAL TEST. REPLACE'WITH NEW OR REBUILT SNUBBER. DC NUMBER:2-92-3592 AND 2-92-3691 EVALUATION: REPLACEMENT OF SNUBBERS IS THE NOT4AL METHOD OF REPAIR FOR = Ns _jtHIS TYPE FAILURE. FAILUME OF SNUBBERS IS EXPECTED FROM TIME TO TIME AS A RESULT OF SYSTEM HOVEMENT DURING OPERATION. CODE NDE:VT-3 AND 4 PRESSURE TEST:N/A. HWO:2-92-5343 REV. 1 MPL:P,B21/2L35 ASME CLASS:I COMPONENT: SPRING CANS ASME SECTION XI CLASS:1 PROBLEM: STRAIGHTEN SPRING CAN SUPPORT RODS AFD RESET. d DC NUMBER:2-92 'i297 _yA-EVALUATION: STRAIGHTENING OF SUPPORT RODS IS AN ACCEPTABLE ~ ME7iiCD "OW I
\s / REPAIR- FOR THESE DEVICES.-CAUSE OF FAILURE APPEARS TO BECAUSED BY SNUBBERS J LOCKED'UP ON THE LINE BEING SUPPORTED BY THE SPRING CANS.
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NWO:2-92-5286 HPL:2P41-F065' , ASHE-CLASS:III ' COMPONENT:CilECK VALVE e ASME SECTION XI CLASS:III , f l PROBLEM: VALVE IS TO BE REVELDED,PER PLANT PROCEDURE,IN HBCiPIPE VALVE WAS INSPECTED 'AND WILL BE RETURNED TO SERVICE.: NO REPAIR OR REPLACEMENTi MADE.
- 4 DC NUMBER:2-92-3370 EVALUATION:UT EXAH WAS PERFORMED ON- VALVE BODY AND FOUND PRbSSURE
;f G DETAINING BOUNDARY ACCEPTABLE. VALVE WILL BE LEFT INSERVICE ONE MORN FUEL
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j3 ( ) 'PAGE 24 MWO:2-92-5237 HPL;2E11-F050B ASHE CLASS:I COMPONENT: VALVE ASME SECTION XI CLASS:I PROBLEM REPLACE DISC ON CHECE VAINE4 VALVE WILL NOT PASS LLRT. .+ DC NUMBER:N/A EVALUATION: REPLACEMENT OF DISC WITH EXACT IN EIND IS AN ACCEPTABLE-METHOD OF RENEWING VALVE TO DESIGN REQUIREMENTS. CAUSE OF FAILURE-IS NORMAL WEAR FOR SYSTEM USE.
""A CODE NDE:VT-3 PRESSURE TEST: TEST.DURING. VESSEL- 's- PRESSURE TEST.
MWO: 2-92-5237 MPL:2E11-F050B ASME CLASS:I COMPONENT: VALVE ASME SECTION XI CLASS:I PROBLEM: REPLACE THE HINGE PIN COVERS DUE TO WEAR ON EXISTING COVERS.- DC NUMBER:2-92-3198 EVALUATION: REPLACEMENT. OF PARTS FOR THE ABOVE VALVE IS A SUITABLE METHOD OF REPAIR. CAUSE OF VAILURE IS DUE TO THE SERVICE TIIE VALVE SEES IN ["sOPERATION.
\- CODE NDE:VT-3 PRESSURE TEST: TEST'DURING VESSEL PRESSURE TEST.
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HWO: 2-92-4807 HPL:2B21 F019-- ASME CLASS:I COMPONENT: VALVE ASME SECTION XI CLASS:I PROBLEM: REPLACE DISC. ' t' DC NUMBER:N/A EVALUATION:THE NEW DISC IS IDENTICAL TO THE REPLACED OLD WEDGET CAUSE"
. OF-FAILURE IS NOT KNOWN AT THIS TIME.
m -> CODE NDE:N/A PRESSURE TEST: TEST DUIRNG~VESSEli 4 LPRESSURE TEST.- ; MWO:2-92-5149 [HPLd2B21-F077B ASME CLASS:I COMPONENT: VALVE ASME SECTION XI CLASS:I-4 s PROBLEM: NUT IS FROZEN ON BONNET STUD. NEED TO MEPLACE STUD.
'DC NUMBER:.2-92-3104 EVALUATION: FAILURE APP.ARS- TO BE DUE TO MAINTENANCE EFFORTS AND'NOT,
_ g DESIGN / MANUFACTURING OR SERVICE RELATED. REPLACEMENT IS A SUITABLE REPAIR.- -' f CODE NDE:VT-1 & VT-3 PRESSURE TEST: TEST DURING VESSEL-7 PRESSURE TEST. !n wy e
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HWO:2-92-3808 MPL:2N33-F001: ASME. CLASS:OE SUPPLIED COMPONENT: RELIEF VALVE ASME SECTION XI CLASS:II 4 PROBLEM: STEM SCORED AND PITTED, STEM PLUG IS STEAM CUT, BODY SEAT IS' STEAM CUT. DC NUMBER:N/A , EVALUATION:REPLACEHENT OF VALVE ' INTERNALS IS ACCEPTABLE.: REPAIR METHOD. CAUSE OF FAILURE IS NORMAL SERVICE INDUCED DAMAGE,
'~S CODE NDE:N/A PRESSURE TEST:N/A A_>
MWO:2-92-3749 MPL:2N33-F004 ASME CLASS:II COMPONENT: VALVE-ASME SECTION XI CLASS:II PROBLEM: REPLACE DISC AND STEM. DISC STEAM CUT TO BADLY TO REPAIR. . l: DC NUMBER:N/A I EVALUATION: DISC AND STEM WERE REPLACED WITH APPROVED PROCURED PARTS i PER PLANT PROCEDURES. CAUSE OF FAILURE IS DUE TO SERVICE SEEN BY THIS VALVE' DURING OPERATION.
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HWO;2-92-3616 REV. 1 HPL : 2 E41- F04 6 '- e ASME CLASS:11 COMPONENT: VALVE' ASME SECTION XI CLASS:11 PROBLEM: REPLACE DISC DUE TO INABLITY TO CLEANUP. DAMAGED SEATING. AREA.= , DC NUMBER:2-92-355C OF' DISC IS 'AN ACCEPTABLE METHOD- OFK EVALUATION: REPLACEMENT REPAIR. CAUSE OF FAILURE IS EXPECThD DUE TO THE TYPE OF SERVICE THIS - VALVE.--: , SEES IN SERVICE. THIS TYPE FAILURE IS TO BE EXPECTED. PRESSURE TEST:MWO: FUNCTIONAL g j- CODE NDE:N/A ' ( Ns m s MWO:2-92-5248 REV. 2 MPL:2P41-F024A' b ASME CLASS:III COMPONENT:CHECE VALVE ASME SECTTON XI CLASS:III ,
< PROBLEM: REPLACE VALVE. INBODY-- GUIDE IS SEVERI.Y ' WORN, PLUG WILL NOT OPERATE PROPERLY. 1 i
DC NUMBER:2-92-3371 EVALUATION: VALVE IS IN AN UNREPAIRABLE CONDITTON.-EXACT REPLACEMENT IS A SUITABLE REPAIR. ADRASIVE NATURE OF WATER HAS CEGRADED VALVE INTERNALS g-iUNDER NORHAL OPERATION. , I } PRESSURE TEST: HYDROSTATIC
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[q -;3 . , j ~., - N=s ' CODE CAT.3_QUMMARY FOP,JATCHl2, . l'ALk,_'92 OUTAGE CODE' CASE l{QS TITLE Case N-98 Ultrasonic Examination - Calibration Block Tolerances,; Section XI Case N-460' Alternative Examination Coverage for Class-1 and Class. 2 Wolds, Section XI, Division-l' Case N-461 Alternativo Rules- for Piping- Calibration . Block-Thickness, Section XI,_ Division 1 C9se N-498 Alternative Rules for 10-Year Hydrostatic; Pressure ~ Testing for Class 1 and 2-Systems, Sectiot. _ XI,- Division 1 p '%_ 122}}