ML20090B786
| ML20090B786 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/26/1992 |
| From: | Howard C GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20090B784 | List: |
| References | |
| NUDOCS 9203040065 | |
| Download: ML20090B786 (109) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l l O OW11ER'S DATA REPORT FOR I!!S E R V I C E I !1S P E C T 1 011 EDWI!1 1. !!ATCl! 11UCLEAR PLAllT UllIT I SEPTE!4BER 1991 - 110VEMBER 1991 PREPARED BY: O b~ s i~ 7 t* ! '"
- O 1 9203040065 920226 PDR ADDCK 05000321 0 PDR
TABLE OF CollTEllTS PAGES , 1 I. ASME lilS-1 FORM AllD SUPPLEMENTARY IliFORMATIoli 1-6 5
- 11. . ABSTRACT 7-14 III. EXAMIliATIOlt
SUMMARY
A. CLASS 1 EXAMIllATIolis 16-57 B. CLASS 2 E*'.5MIllATIollS 58 : C. PRESSURE TESTIllG 67-69 D. COMPONEllT SUPPORTS 70-79 E. AUGMENTED EXAMIliATIolls 80-82 i F. REACTOR PRESSURE VESSEL INTERNALS 83-92 G. REPAIRS AND REPLACEMENTS 93-104 O , I l l t 11 u- ,y- . . .c.-.c -..ge-, ,-s.,,._%,4, . - ,.-_ -
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9 110TE: Company issued report! Portions of this report are compiled from Southern lluclear Operating "liondestructive Examination Of Selected Class 1, 2, and 3 Components", for the Fall 1991 Refueling Cutage at E.I. !!atch liuclear Plant, - Unit 1. This report is available for review in the Records Management Department at the plant site. O 0 111 1 i
l C LIST OF ABBHEVIATIONS ANI/ANII Authorized Nuclear Inspector / Authorized Nuclear Inservico Inspector ASME American Society of Mechanical Engincorn ASNT American Society for Hondestructivo Testing , BC Branch Connection 6 DWR Boiling Water Reactor Cl! Closuro lload 4 CONT Containment CPI Containment Purgo and Inerting System CRD Control Rod Drive System CS Core Spray System , CU Clean-up C&L cramer and Lindoll Engineers DCR Design Chango Roquest ECCS Emergency Coro Cooling Systems ET Eddy Current Examination EPRI Electric Power Research Instituto , , FB Flango Bolting FPC Fuel Pool-Cooling-System , FW Foodwator System GE Gonoral Electric GPC Georgia Power Company o O- IIL IIPCI llanger Lug liigh Prossure Coolant Injection System > INF- Indication Notification Form i IGSCC Intorgranular Stross Corrosion Cracking ISI Inservico Inspection : LD Longitudinal Soam Wold Extending Downstream
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LD-I - Longitudinal Wold Downstream on Insido of Elbow LD-O Longitudinal Wold Downstream on Outside of Elbow Lo- Zero Reference Location LMT Lambert, MacGill, Thomas, Inc. LPCI Low Pressure Coolant Injection i LU -Longitudinal Seam Wold Extending Upstream LU-I Longitudinal Wold Upstream on Insido of Elbow 1 LU-O Longitudinal Wold Upstream on Outside of Elbow MSIV Main Steam Isolation Valvo MS Main Steam System MSA Main Steam Auxiliary System MT Magnetic Particle Examination - MWO Maintenance Work Order ; NDE Nondestructivo Examination ' NI No Indication NRC- - Nuclear Regulatory Commission NRI No Recordablo Indication OL Overlay iv
O. Abbreviations - cont. PL Pipo Lug PLT Plant PR. Pipo Rostraint PROD Product PS Pipo Support-PSW Plant Servico Water System PT Liquid Ponotrant Examination QC Georgia Power Company Quality control RC Reactor Rocirculation System RCIC Reactor Core Isolation Cooling System RHR Residual '8 eat Removal System RllRSW Residual ticat Removal Servico Water System RI Recordablo Indication RINTSA- Recirculation Inlot Nozzlo Thermal Sloovo Attachment Wolds i' RL Refracted' Longitudinal RL Rostraint Lug RPV Reactor Pressuro Vessel-RX Reactor RWCU -Roactor Water Cleanup System SBLC_ . Standby Liquid Control System SIAI Structural Integrity Associates, Inc. SER Servico ! SRV Safety Relief Valvo i SNC Southern Nuclear Operating Company TDP Torus Drainage and Purification System
-TSB Turbine Steam Bypass System UT Ultrasonic Examination VLV Valve ,
VT Visual Examination , This list is comprised of standard abbreviations used in Inservico Inspection Documentation. All of these abbreviations may not appear in this report. O v 1 l l
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- - - . . . . - - . - . - . ~ . . - - . . - . _ - . . - . -
TOTAL NUMBER OF SHEETS LO4 FORM NIS-1 FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE ~ INSPECTIONS
-As Required Dy the Provisions Of The ASME-Codes Rules
-1. Owner: Georcia Pqwer ComDbay. 333_ Piedmont. Ave.. NL P.O. Box 4 54 5,_
Atlanta. Georcitt 3030R
- 2. Plant: Edwin I . Hatch Nuclear Plant, Rollte 1, Box 278, Baxlev. GA 3}fAL1
- 3. Plant Unit 1 4. Owner Certificate of Suthorization (if req.) H4h
- 5. Commercial Service Date J2431/7Q 6. M tional Board No. for Unit I!46
- 7. Components Inspected:
component or Manufacturer State or Appurtenance Manufacturer or Installer Province National or System or Installer Ser 1 No. Number Board No. Rx. Presfqure 'LpEggl Combustion Enc. 67105 ._N/A 20769 Rx. Pressure Vessel Combustion Eng2 67205 JUA 20769 1B21 Main Steam Pullman Power Prod.
- Eft _ . J U A_.
1B21 Feedwater Pullman Power Proh
- N/A N/A 1831 Rx. Recirc Pullman Power Prod.
- JJ/A N/A 1C11 CRD P_ ullman Power Prod
- _N/A N/A iC41 SBLC Pullman Power Prod.
- N/A Ji/h_
1E11 RHR Pullman Power Prod 2
- N/A N/A 1E21 Cgr_c Sprav PJll.m_qn Power Prod.
- IUA N/A O 1E41 HPCI 1E51 RCIC Pullman Power Prod.
Pp11 man Power Prod. J!/A.,. J146_ JI/JL. N/A N/A l
-1G31 RWCU Pullman Power Prod.
- EA_
1G41 FPC & CU PylJapn Power PJ_gd.i.
- J1/A JI4/L.
'1N11 M S Auxillaty_ Epilman Power Prod
- N/A_ N/A 1P41 Plt Serv Water Pullman Power Prod.
- N/A N/A i Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. x 11 in., (2) information in items-1 through _6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets are recorded at
.the top of this forn. **
f l l * - 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.
** Exception taken to note 2.
O 1
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, FORM NIS-1 (Eack)
- 8. Examination Dates 06/05/90 to 11/29/91.
- 9. Inspection Interval from 01/86 to 01/96.
- 10. Abstract of Examinations. Include a list of examinations 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 statements made in this report are correct and
-the examinations and corrective measures taken conform to the r'21es of.the ASME Code, Section XI.
Date N6 *
- 19 % Signed Georola Power Company ByDM __ _ D Owner Certificate of Authorization No.(if applicable) UZA Expiration Date H/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the
. National Board of Boilri and Pressure Vessel Inspectors and/or the State or Province of E6 and employed by **** of Hartford, CT have inspected the components described in this Owners' Data Report during the period 09/91 to 11/91 and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this owners' Data Report in accordance'with the requirements of the ASME Code, Section XI.
l By signing this certificate neither the Inspector nor his employer makes_any warranty,-expressed or 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 damage or a loss o.' any kind arising from or connected with this inspection. Date h' 19 N
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Commissions Georcia-GA00115 g Inspector's Signature National Board, State, Province,& No. l:
*** The following NIS-1 Form supplementary information and report includes'the responses to NIS questions #10, #11, and #12.
L **** Hartford Steam Boiler Inspection and Insurance Company.
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NIS-1 Form Supplementary Information Owner's Data Report Inservice nspection Date: February 4, 1992 Owner tipme & Address: Georgia Power Company 333 Piedmont Avenue, N.E. P.O. Box 4545 Atlanta, Georgia 30302 Name & Address of Nuclear Generatina Plant: Edwir T. Hatch Nuclear Plant Routi- t, Box 278 Baxley, Georgia 31513 [Layle Assioned to Nuplear Plant _ Sla.lioD: Edwin I. Hatch Nuclear Plant Unit 1 Commercial Service Date: December 31, 1975 Gross GeneratinJ Cap 3pjli_y: t 2436 MWt, 813 MWe S_ tate. Province, or Municipality Assioned NumbeE: N/A National Board Number AssLgned b_y Maqufacturer: N/A O 3
system PrespyrplLeg}ingfA. 'Lepig SysteEl ClfLqn O Reactor Pressure Vessel and Associated Class 1 Piping and Components 1 Test Reauired 1 Leakage SBLC (IC41) 1 1 Hydrostatic RHR (IEll) 2 2 Hydrostatic RHRSW (IEll) 3 1 Inservice Core Spray (1E21) 2 1 Functional HPCI (1E41) 2 1 Functional RCIC (1E51) 2 1 Functional FPC (1G41) 3 1 Inservice PSW (1P41) 3 2 Hydrostatic PSW (IP41) 3 1 Inservice Pine Suncort & Hancer EyKaninittion 93_aSJL_1 ' Main Steam System Residual Heat Removal System Feedwater System Reactor Recirculation System ; Reactor Water Cleanup System Claas_2 High Pressure Coolant Injection System Residual Heat Removal System Reactst Core Isolation Cooling System Main Steam Auxiliary System Control Rod Drive System Class 3 Plant Service Water System O 4 I
v Namo &' Address of Manufacturer of Components:
- 1. Reactor Pressure Vessel and closure Head; Combustion Engineering, Inc.
'O Chattanooga, TN
- 2. Piping-(Classes 1, 2,-and 3)
- a. Pullman Power Products Division of Pullman-Kellogg Williamsport, PA
- b. General Electric Company San Jose, CA Note: Piping purchased by General Electric and Pullman and installed by Pullman. Material certifications and manufacturer informatien are available for review in the Records Management Department at the Hatch Plant Site.
- 3. Piping _ Supports and Hangers (Classes le 2, and 3)
- a. Bergen-Paterson Pipe Support Corporation Laconia, NH
- b. ITT Grinnell Corporation Providence, Rhode Island
- c. Pacific Scientific Anaheim, CA
- 4. Valves, Pumps, and. Heat Exchangers
- a. Crane New' York, NY
- b. Wm. Powell Company Cincinnati, OH
- c. General Electric San Jose, CA
- d. Target Rock Corporation East Farmingdale,_NY Date of Inservice Insnection:
September 1991 - November 1991 l l l (/ 5 I l r - ,c--
i ggnpletion Date of Inservice Insnection: I November 29, 1991 'O Name of Inspector: Donald R..Laakso.(ANI/ANII) Name & Maillna Address of Inspector's-Employer: i The Hartford Steam Boiler Inspection and Insurance Company-200 Ashford Center - North Suite 300 Atlanta, Georgia 30338 l 1 i l: l ) 4 . O 6
i I ABSTRACT An Inservice Inspection of selected Class 1, 2 and-3 components at Georgia ' Power Company's Edwin I. Hatch Nuclear Plant Unit 1 was performed during O the Fall 1991 Maintenance / Refueling Outage. The components'were examined in accordance with the applicable ISI outage Plan, including any changes
-made during the outage as approved by GPC.
Edwin I.' Hatch Unit 1 is currently in the second period of the second 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 contractors; LMT, GE , Seimens, and-Ebasco performed NDE of the selected welds and components. In addition, GE assisted SNC personnel with VT examination of selected RPV internal components. SNC, GE, or GPC NDE procedures were utilized for all ASME Section-XI Examinations. LMT, Ebasco,_ and Seimens personnel were qualified to the applicable SNC procedures. EPRI qualified inspectors were utilized for all examinations involving IGSCC. susceptible materials. SNC and GE procedures were used for mechanized ultrasonic examination and exams-were_ performed by SNC, Seimens, Ebasco, and GE inspectors. SNC-and C&L personnel performed eddy current examinations of 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 component internal surfaces.and O visual examination of pipe supports and hangers were also performed. Third 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 L Nuclear Power Plant Components," 1980 Edition with Addenda through b Winter 1981. United _ States Nuclear Regulat'ry Commission, Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" which invokes much of NUREG 0313, hovision 2, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping". United States Nuclear Regulatory Commission, Generic-Letter 81-11,-which L modifies and invokes NUREG 0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking". United States'Naclear Regulatory Commission, I&E Bulletin 80-13 Visual Examination of Core Spray Spargers. SNC " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant, l Unit 1 1991 Fall Refueling Outage, Revision 1." SNC "Second Ten-Year Examination Plan, Edwin I. Hatch Nuclear Plant Unit 1."
- United States Nuclear Regulatory Commission NUREG 0803, " Generic Safety O Evaluation Report Regarding Integrity of BWR-SCRAM System Piping."
7
l l Rnprosentative samples'of the following systems, comprised of selected Class 1, 2,-and 3 components, were examined using variotn NDE techniques, in accordance with the above documents-
'T )
- s_) :- Class-1 l Reactor Pressure Vessel (1B11) l Main. Steam System (1B21) 1 Feedwater System (1B21) Reactor Recirculation System (1B31) Control Rod Drive System (1Cll) Standby Liquid Control System (1C41) Residual Heat Removal System (IEll) Core Spray System (1E21) High Pressure Coolant Injection System (1E41) > Reactor Core Isolation Cooling System (1E51) Reactor Water Cleanup System (1G31) Valve Internals Valve Bolting Class 2 Standby Liquid Control System (1C 41) Residual Heat Removal System (IEll) Core Spray System-(1E21) High Pressure Coolant Injection System (1E41) Reactor Water Cleanup System (1G31) Reactor Core Isolation Cooling System (1ES1) Main Steam Auxiliary System (IN11) Class 3 RHR Service Water System (1E11)
%/ Fuel Pool Cooling System (1G41)
Plant Service Water. System (1P41) Other - Augmented (Non ASME Section XI)
-Eddy-current examinations were performed on the following components:
Unit 1 Feedwater Heaters SA, SB, 7A, 7B, 8A, 8B, 10A, 10B, and Emergency Diesel Generator 1A and 1C Jacket Water Coolers, Lube Oil Coolers, Air Coolers and the Motor Generator "A" Air Cooler. UT thickness measurements were performed on selected components in the Extraction Steam and Condensate Feedwater Piping Systems. A portion of these components were selected due-to their similarity in design and
. operating conditions to components involved with the "Surry pipe break incident".
Eight. (8) Non-Safety RWCU System welds were examined using ultrasonic examinations techniques (UT) due to commitments made by GPC. These augmented exams are not required - by the ASME Section XI Code but were performed due_to commitments to GL 88-01. O 8
CIASS 1 EXAMLHATIOUS EUREG 0313 GPC is committed to the performance of surf ace and volumetric examinations on IGSCC susceptible welds in accordanco with HUREG 0313. This commitment is formalized ir GPC response to NRC Generic Letter 88-01. The below listed summary gives the total number of exams performed by outage end. A detailed report on flaw evaluation and overlay design was submitted to the NRC by letter HL-2000 dated January 21, 1992. g3tegory A Twenty-five (25) of these Thirty-nine (39) Category A welds were examined. welds were examined using UT and PT techniques and the remaining fourteen (14) were examined using UT techniques only. No rejectable indications were found. Catenorv C (14) Category C wolds. A The original examination scope included fourteenwold being found unacceptable scope expansion was required due to one (1) for continued operation and was overlay repaired, resulting in a total of twenty-eight (28) Category C welds being examined. Fourteen (14) of these welds were examined using UT and PT techniques and the remaining fourteen (14) welds were examined using UT techniques only. The Category C weld which was overlay repaired was ID31-1RC-28D-2. Although weld 1E11-1RHR-20B-D-5 did not contain any identified flaws, a weld overlay was applied to improve the inspectability of the location. The classification of these welds is now Category E per NUREG-0313 and will be examined as such in future outages. Catenory D No rejectable indications were Twelve (12) Category D welds were examined.of these welds were examined using UT and PT detected. Five (5) and the remaining seven (7) were examined using UT techniques only. Six (6) RINTSA welds were examined by UT and no rejectable indications were detected. Cateaorv E The original examination scope included twenty-five (25) of the total forty-six (46) Category E (overlayed) welds. UT examinations revealed new IGSCC indications and some original cracks with allnew growth(46) forty-six which warranted Category E examination scope expansion. By outage end, All results for new welds had been examined by UT NDEevaluated techniques. by Structural Integrity indications or crack growth were Associates, Inc. and found to be acceptable for continued service. 9
Note that-six (6) new overlays were added during_this outage which results in a total of fifty-two (52) Category E overlays. Preservice examinations were performed on each of these six (6) new overlays. No -rejectable indications were found. See sections: on Category C and Category F O examinations for the additional overlay wold numbers. Cateaory F All Category F' welds require examination each refueling outage. All four (4) of these welds were examined during the outage and a change in indications or apparent crack growth was detected in all four (4) of these welds which were unacceptable for continued service. All four (4) welds were overlay repaired and will be examined as Category E welds in future outages. -Listed below are the Category F welds which were overlay repaired: 1B31-1RC-12BR-A-4 1B31-1RC-12BR-E-4
'1B31-1RC-12AR-G-4 1E11-1RHR-208-D-4 A preservice baseline examination was performed on all welds which were overlay repaired during the outage.
- Other Class 1 Examinations Two-hundred-eighteen (218) ASME Section XI component examinations were performed utilizing UT, MT, PT and VT as applicable. These examinations included; RPV welds, piping welds, valve internals, and valve bolting materials.
Per I&E Bulletin 80-13, the core spray sparger and associated piping were VT examined. No reportable indications were detected.
'Per ASME Section XI, selected-RPV internals were examined. These examinations included portions of the vessel interior, interior attachments beyond the belt line region and the RPV internal components. See the Invessel Inspection section of this report for more detailed information.
Four.(4) Class 1 valves were disassembled for maintenance / inspection during the outage. The internals of these valves were VT inspected.by GPC Q.C. personnel. None of the valves exhibited any _ unacceptable ,- -conditions relevant to the visual examination. l" Twenty (20) CRD's vere replaced during the outage which facilitated visual examination (VT-1) of the colts, studs, and nuts. Per SIL 462, one Shroud Support Access Hole Coverplate was examined. Class II Examinations Forty-seven (47) welds were examined using surface and/or volumetric NDE techniques as applicable. Two (2) of these welds were examined per NUREG 0619 (UT only), eleven (11) examinations were for the GPC augmented examination commitments, and the remaining thirty-four (34) examinations were per ASME Section XI requirements. Unacceptable linear indications were found in three (3) welds and were removed by controlled grinding. 10
1 Pressure Testina l One (1) Class 1 hydrostatic test, two (2) Class 2 hydrostatic tests, three C (3)~ Class 2 functional tests, two-(2) Class 3 hydrostatic tests, three (3) ( Class 3 inservice tests,-and the Class 1 System Leakage Test were all performed- satis f actorily. See Pressure Test section of Report for specific
~ test--identifications-and details.
Auamented Examinations Eight (8) welds in the non-safety 3 portion of the RWCU System were examined -- by UT por a- GPC commitment to the NRC for NUPEG - 0313 Rev. 2 augmented requirements. No reportable indications wLre detected. C_pJpoDODt_Aupport_Examinat19.Ds _LClass,_.1, - 2 and 3' One hundred and forty-nine (149) component supports were VT examined Oct. the requirements-of ASME Section XI during the outage. Seventeen (17) produced unacceptable results. After maintenance and/or eng .neering i evaluation, all of the unacceptable component supports were detcrmined to be acceptable._ Where maintenance was required, the component supports were re-examined to confirm acceptability. Benairs and Replacements (Class 1 and 21 Numerous repair / replacement activities were performed prior to and during the outage. Major repair / replacement activities-included weld overlay of six (6) Reactor Recirc. welds. 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 were reported with indications or were considered unacceptable. All of these items were _ either- repaired and/or evaluated and then determined to-be acceptable. 11
Summary 91 Indications Identification Indjcatio.D Corrective A9119D O Steam Dryer Rub marks, Acceptable as is per Upper and Lower displaced metal GPC and GE engineering Guides Upper Support Bracket .3" linear indication Indication removed, IE11-2HX-A-USC-2 area re-welded MWO 1-91-5805 Upper Support Bracket .6" and .4" linear Indication removed, 1E11-2HX-A-USC-3 indications area re-Welded MWO 1-91-6395 Weld Spot indication Acceptable as is 1B31-1RC-12BR-D-3 per GPC Engineering Weld overlay 6 interbead lack of Acceptable as is 1B31-1RC-28A-7 fusion indications per SIAI Weld overlay .3" linear indication Acceptable as is IB31-1RC-28B-15 per SIAI Weld overlay 7 interbead lack of Acceptable as is 1E11-1RHR-24B-R-12 fusion indications per SIAI O Weld 1B31-1RC-28B-2
.5", .42", and .25" linear indications Weld overlay MWO 1-91-4832 Wold 3.5" linear MT Indication removed, 1E11-2RHR-20A-D-4 indication area re-welded MWO 1-91-6265 Weld 2.5" linear MT Indication removed, 1E11-1RHR-24B-R-7 indication area re-welded MWO 1-91-6264 Wold UT indication Weld overlay 1831-1RC-12BR-A-4 MWO 1-91-4832 Wold UT indication Weld overlay 1B31-1RC-12BR-E-4 MWO 1-91-4832 Weld UT indication Weld overlay 1B31-1RC-12AR-G-4 MWO 1-91-4832 Weld UT indication Weld overlay 1E11-1RHR-20B-D-4 MWO 1-91-4832 Support Broken fillet Acceptable as is 1B21-FDH-5 welds per Bechtel letter Support Bent paddle, Replaced paddle, 1821-FDH-10 slipped bearing reset bearing MWO 1-91-6468 12
1
)
.ldEDtification. .lDdicatiGD- ' Corrective Action Support' Dent rod Acceptable as is 1C11-SK1-H3 per Bechtel letter V(( Support No load on support Roadjusted rod 1C11-SK1-H5 MWO 1-91-6504 Support- Light load on support Readjusted rod 1C11-SK1-H6 . *MWO 1-91-6570 .
Support Bent rod Acceptable as is
-1C11-SK1-H14 per Dechtel letter Support No load on clevis Readjusted rod 1C11-SK2-H24 *MWO 1-91-6570 Support- No load on clevis, leadjusted-rod,-
1C11-SK2-H26 loose nut tightened loose nut
<MWO 1-91-6570-Support- Slipped bearing Reset bearing
-1E11-RHRH-407 MWO 1-91-6129
' Support Slipped bearing Reset bearing 1E11-RHRH-407A MWO 1-91-6129 Support Restricted movement Acceptable as is 1E11-SM-1 of paddle por Bechtel letter
. (M
'\-[ Support Improper spring can ' Reset spring can 1P41-SDGH-4 setting MWO 1-91-5455 Support Improper spring can Reset cpring can 1P41-SDGH-7 setting MWO 1-91-5455 Support- Bent rod Repaired rod 1P41-SWH-19 MWO 1-91-5456 Support .
Bent paddle, Replaced paddle, 1P41-ISH-33 slipped bearing bearing acceptable as is per Bechtel letter MWO 1-91-5454 Support Slipped bearing Roset bearing 1E11-RHRH-60 MWO 1-91-5457' support Improper spring can Reset spring can 11E41-HPSEH-78 setting *MWO 1-91-5458 Weld 3.8" and 1.3" Acceptable as is 1B31-1RC-12AR-H-3 linear _ indications per SIAI p G
-13
Identification Indication Corrective ActiQD , Wold 1.3" linear indication Acceptable as is 1B31-1RC-12AR-J-3 per SIAI Wold .4", .15", .25", .6", Acceptable as is 1E11-1RHR-24D-R-13 .6" and .3" linear per SIAI indications
- These MWos did not require initial / final ANII review.
O O 14
The following sections of this NIS-1 Report contain the summary of the-NDE Examinations performed, provides_ additional information and gives results of those examinations.
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-Visual Examination of-Class 1 CRD Bolting i
(bolts, studs-O ASME_Section XI requires and nuts)-whenever examination of the housings--are_ the CRD housings disassembled. Twenty (20) CRDs-were-replaced during the outage whichl facilitated-visual examination-(VT-1) of-the: bolts,_ studs and nuts. The subject _ examinations were performed by
.GPC Q.C.-personnel'in conjunction with the_CRD maintenance / replacement-activities. Listed below are the CRDs which were_ examined. All of these -
-CRDs_were replaced per MWO 1-91-3668, 26-03 38-27 30-03 34-35 '
34-15 46-35 18-19 34-39 46+19 22-43 50 -19 26-43 . 14-23 34-43 22-23 38 34-23 42-43 06-27 42-47
- O 1
0 17
E.I. HATCH UNIT 1 FALL 1991 REFUELING OUTAGE V CLASS 1 COPtPONENTS
~ASME EXAM EXAM!kATION CAL EXAM / CAL 'SECTION WI FfCURE NO. EXAMINATION / AREA . PPOCEO. vE BLOCK SHEET NO. RESULTS RE"AR($
RPV EXAMINATIONS 88.10 A-1A/02 C-6 (120-270) MT-H-500/05 61-M S91HIM044 NRI N/A B-H SUPPORT SK!RT-N2D UT-H-410/04 $91MIC106' N/A UT CAL ASME (120 DEGREE) TO N2H 591H10157 NRI (270 DEGREE) C.W. B15.10 - CLASS 1 (PT) VT-H-720/03 N/A SEE F# ESSURE TEST SECTION B-P PRESSURE RETAIN!bG OF THIS REPORT. ASME BOUNDARY LEAKAGE TEST 87.80 --- FLANGE SOLTING 450C-INF- N/A EXAM DERF 0c"ED BY GPC OC DEPT. B-G-2 CRD NOUSING 012-OS ASME N2A (RINTSA) UT-M-415/05 125-N $91H1C169 N/A UT CAL N/A RINTSA WELD $91H1U231 ket NUREG-03130 B3.100 A-1/04 N2B (IR) UT-N-450/04 61-M $91H1C104 N/A UT CAL EXAM LIMITATION DUE TO ='tLDED B-D 8 LOOP RECIRCULATION 591H1U155 NRI PAD, 93% COVERAGE. ASME INLET N0ZZLE AT 60 DEGREES
-i 83.90 A-1/04 N2B (N-SH) UT-H-410/04 61-H $91H1C115 N/A UT CAL ONE-SIDED EXAM DUE TO NOZZLE .B-0 B LOOP REC!ntCULATION $91M1U167 WRI CONFIGURATION.
ASME INLET N0ZZ TO SHELL $91H1C118 N/A UT CAL S91H1U171 NRI S91K1C121 N/A UT CAL
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RPV EYAMINATIONS N28 (RINTSA) UT-H-415/05 125-H 591M1C170 N/A UT CAL N/A 4 RINTSA WELD $91H1U232 NRI NUREG-03130 N2C (RINTSA) UT-N-415/05 125-H . 591NIC171 N/A UT CAL N/A RIhTSA WELD $91N10233 kRI NUREG-03130 t B3.100 A-1/04 N2D (IR) UT*H-480/04 61-N $91H1C105 N/A UT CAL 93% COVERAGE DUE TO 4" inELDED B-D B LOOP RECIRCULATION $91N1U156 het PAD. ASME INLET N02ZLE tR r 83.90 A-1/04 N2D (N-SM) UT-N-410/04 61-H 591 HIC 116 N/A UT CAL ONE-SIDED EXAM DUE TO N0ZZLE B-D 8 LOOP RECIRCULATION 591M1U168 NRI CONFIGURATION. ASME INLET N0ZZ TO SHELL 591M1C119 W/A UT CAL
$91M1U172 NRI
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591M1C122 N/A UT CAL 59141U176 hR1 i N2D (RINTSA) UT-H-415/05 125-H 591M1C172 N/A UT CAL N/A RINTSA WELD 591H1u234 NRI NUREG-0313D 83.100 A-1/04 N2E (!R) UT-M-480/04 61-M $91M1C103 N/A UT CAL EXA* LIMITATION DUE TO WELDED
. B-D B LOOP RECIRCULATION $91M1U154 hel PAD, 93% COVERAGE. .
ASME INLET NOZZLE AT 150 DEGREES 1 - t
E.1. MATCH UNIT 1 FALL 1991 REFMLING OUTAGE CLASS 1 COMPONENTS i ASME EXAM ? EXAMINATION CAL EXAM / CAL
-'SECTION XI FIGURE NO. ' EXAMINATION / AREA FROCfDURE BLOCK SPEET No. RESULTS REPAprS RPV EXAMINATIONS i
B3.9C A-1/G4 N2E (N-SH) UT-H-410/04 61-H 591H1C117 N/A UT CAL ONE-SIDED EXAM DUE TO N0ZZLE 8-D . -B LOOP RECIRCULATION $91H1U169 NRI CONFIGURATION. ASME INLET N0ZZ TO SHELL S91H1C120 N/A UT CAL 591H10173 NRI S91H1C123 N/A UT CAL S91H10177 NRI 1 N2E (R!NTSA) UT-H-415/05 125-H S91H1.173 N/A UT CAL N/A RINTSA WELD S91H1U235 NRI NUREG-0313D J M2G (RINTSA) UT-H-415/05 125-H $91H1C174 N/A UT CAL N/A RINTSA WELD $91H1U236 NRt NUREG-03130 A-1/04 N4A (CYL BORE) UT-H-481/01 61-H $91H1C016 N/A UT CAL N/A I -- STRAIGHT CYLINDRICAL $91H1UO43 WRt NUREG-0619 BORE SECTION S?1H10017 N/A UT CAL T S91H1UO44 NR1 591H1CO30 N/A UT CAL 591H10058 NRI B3.100 A-1/04 N4A (!R) UT-H-480/04 61-N $91H1CO26 N/A U1 CAL EXAM LIMITATION DUE'TO' B-D A-A LOOP FEEDVATER 591H1UO54 WRI N0ZZLE N12A INTERFERENCE, NUREG-0619 INLET N0ZZLE IR 90% COVERAGE A-1/04 N4A SPARGERS VTa M-755/02 N/A $91H1V203 SAT N/A A- A LOOP *EEDWATER NUREG-0619 1NLET NOZZLE [hd) O
( .. ( E.1. MATCH UNIT 1 FALL 1991 REFUELIRG DJTAGE. CLASS 1 COMPONENTS ASME EXAM EXAMINAT!ON CAL . EXAM / CAL
-SECTION XI FICORE NO. EXAMINATION / AREA PROCEDURE' BLOCE SWEET NO. RESULYS PEMatts RPV EXAMINATIONS A-1/04 N48 (CYL-BORE) UT-N-481/01 61-H $91H1C018 N/A UT CAL ZONE *A" EXAM LIMITATION DUE STRAIGHT CYLINDRICAL .$91H10045 NRI TO THERMOCOUPLES WELDED TO NUREG-0619 BORE SECTION $91H1C019 N/A UT CAL BARPEL, 95% COVE # AGE.
S9131U046 NRI-
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$91H1UO59 NRI B3.100 A-1/04 N48 (!R) UT-H-480/04 61-H $91H1CO27 N/A U1 CAL N/A B-D A-B LOOP FEEDWATER $91H1UO55 NRI NUPEG-0619 INLET NOZZLE IR i
-- A-1104 N48 SPARGERS VT-H-755/02 N/A S91MTV203 SAT N/A A-B LOOP-.FEEDWATER NUREG-0619 INLET N0ZZLE l
A-1/04 44C (CYL BORE) UT-H-481/01. 61-H S91H1C020 N/A UT CAL N/A
-STRAIGHT CYLINDRICAL $91H1UO47 NRI
! NUREG-0619 BORE SECTION S91H1CO32 N/A UT CAL 591H1UO60 NRI S91H1CO21 N/A UT CAL 591N10065 NRI l B3.100 A-1/04 N4C (IR) UT-H-480/04 61-M $91H1CO28 N/A UT CAL EXAM LIMITATION DUE TO j B-D B-C LOOP FEEDWATER 591H10056 WRI N0ZILE N128 INTERFERENCE,. ! NUREG-0619 INLET WO22LE 1R 90% COVERAGE. l l A-1/04 N4C SPARGERS VT-H-755/02 N/A $91H1V203 SAT N/A B-C LOOP FEEDWATER 1 NUREG-0619 INLET N0ZZLE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___. __.___.________._____.m__________. _ _ . _ _ . _ . =
7m -- A A E.I. HATCH UNIT.1 FALL'1991 REFL1ELING OUTAGE CLASS 1 COMPONENTS ASME ' EXAM EXAMINATION- CAL EXAM / CAL SfCTION XI FIGURE NO. EXAMINATION / AREA PROCrDURE BLOCK SPEET Wo. RESULTS PFMARKS , i RPV EXAMINATIONS A-1/04 N4D (CTL BOGE) UT-H-481/01 61-H 591H1C033 N/A UT CAL ZONE "A" EXAM LIMITATION DUE STRAIGHT CYLINDRICAL $91H1UO61 N41 TO WELDED THERMOCOUPLES. NUREG-0619 BORE SECTION S91H1CO37 N/A UT CAL . 95% COVERAGE..
$91H1UO66 NRI S91H1CO36 N/A UT CAL .
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,NUREG-0619 8-D LOOP FEEDWATER 591H10057 NR1 INLET N0Z2LE !R l
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A-1/04 NSA VT-H-755/02 N/A 591MTV199 SAT N/A A LOOP CORE SPRAY IEB 80-13 INLEY N0Z2LE-A-1/04 NSB vi-H-755/02 N/A 591N1V199 SAT N/A 2 -- B LOOP CORE SPRAY i IEB 80-13 !NLET N0ZZLE B3.100 A-2/03 N6A (IR) UT-H-480/04 64-H $91H1C047 N/A UT CAL N/A t B-D A LOOP RER HEAD $91H10082 NRI ASME SPRAY NO22LE IR i ! po *
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ASME EXAM EXAMIN/.T!ON CAL EXAM / CAL SECTION XI, FIGURE NO. . EXAMINATION / AREA PROCEDOGE. BLOCK SPEET 40. RESULTS REMAPKS PESIDUAL HEAT REMOVAL SYSTEM
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CLASS 1, 2, AND 3' PRESSURE TESTS i l s a a f a t k e . t 67
--..:._.:..._-..._.__._,...~_____________.-~_.._._-
PRESSURE TESTING GENERAL This section _ of the report provides a discussion of the pressure tests which were performed during the 1991 Plant E.I. Hatch Unit _1 Fall Refueling Outage. These pressure tests were performed-for the purpose of inservice 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 Nuclear Operating Company.
All pressure tests were performed in accordance with ASME Section XI, 1980 Edition with Addenda through Winter 1981. All tests were witnensed and/or reviewed by the resident ANII. The completed- test reports are available for review in the Records Management Department at Plant E.I. Hatch. CLASS 1 PRESSURE TESTS One (1) Class 1 Leakage Test was performed during the outage per ASME Section XI, paragraph IWA-5211(a) . The test was performed per GPC procodure 42IT-TET-006-1S, ISI Pressure Test of the Class 1 System. One (1) Class 1 Hydrostatic Pressure Test was performeA during the outage per ASME Section XI, paragraph IWA-5211(d). The test wcr performed in accordance with GPC procedure 42IT-TET-003-OS, Hydrostatic Pressure Testing of Piping and Components. TEST RESULTS minor 1eaxeee et mechenica1 soines was found durine the vT-2 O On1y examinations. Any component which was disassembled prior to startup or to repair leakage, was re-examined during startup at normal operating pressure (1005 psig) per GPC procedure 42IT-TET-004-OS, Operating Pressure Testing of Piping and Components. CLASS 1 PRESSURE TEST
SUMMARY
PROCEDURE MWO NUMBER TEST I.D. 42IT-TET-006-1S 1-91-3191 1B21-LT-1 1-91-3192 1C41-HT-2 42IT-TET-003-OS CLASS 2 PRESSURE TESTS Two (2) Class 2 Hydrostatic Pressuie Tests were performed during the outage per ASME Section XI paragraph IWA-5211(d). The tests were performed in accordance with GPC procedure 42IT-TET-003-OS, Hydrostatic Pressure Testing of Piping and Components. Three (3) Class 2 Functional Tests were performa.d per ASME Section XI I paragraph IWA-5211(b). The tests were performed in accordance with GPC of Piping and procedure 42IT-TET-004-OS, Operating Pressure Testing
- Components.
O TEST RESUtTS Only minor leakage at mechanical joints was reported during the VT-2 i ) examination and all results were determined to be acceptable or was L repaired. 68
.. - . . - - _.-... - . .-_,. - _ ~ - - . - . - . - - - ~ . . . - - .
CLASS 2
SUMMARY
TEST I.D. PROCEDURE MWO NUMBER O V1E11-HT-1 421T-TET-003-0S 1-91-3193
- 1E11-HT-11 42IT-TET-003-0S 1-91-3194
'1E21-FT-1 4 21T 'tET-004-0S None Required 1E41-FT-1 421T-TET-004-0S None Required 1E51-FT-1 42IT-TET-004-OS None Required CLASS 3 PRESSURE TESTS Two (2) Class 3 Hydrostatic Pressure Tests were performed during the outage per ASME Section XI, paragraph'IWA-5211(d). The tests were performed in accordance with GPC procedure 42IT-TET-003-OS, Hydrostatic Pressure Testing of Piping and Components.
Three (3) Class 3 Inservice Tests were performed during this outage per ASME Section XI, paragraph IWA-5211(c). The tests were performed in acccrdance with GPC procedure 42IT-TET-004-0S, Operating Pressure Testing of~ Piping and. Components. TEST RESJLTS only minor mechanical leakage was reported during the VT-2 examinations except during test 1P41-HT-6B, one (1) thru-wall leak was reported on a reducing bushing. MWO 1-91-5655 replaced the weld and an operating pressure test was performed to demonstrate precsure boundary integrity. CLASS'- PRESSURE TEST
SUMMARY
TEST I.D. PROCEDURE MWO NUMBER 1P41-HT-6A 42IT-TET-003-OS 1-91-3644 1P41-HT-6B 42IT-TET-003-OS 1-91-5645
.1E11-IT-1 42IT-TET-004-OS None Required
-1G41-IT-1 42IT-TET-004-OS None Required 1P41-IT-1 42IT-TET-004-OS None Required i
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OF VISUAL EXAMINATIONS CLASS 1, 2, AND 3 9 COMPONENT SUPPORTS s 9-4 1 9 i
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_ _ . - _ ~ _ _ _ . _ _ _ _ _ _ - . _ -_. COMPONENT SUPPORT EXAMINATIONS This section of tne report provides a discussion of the visual examinations performed on selected component. supports .on Hatch Unit l '. The subject , examinations were performed prior to and during the Refueling / Maintenance A . ( f Outage. Examinations were performed using SNC Procedure VT-H-730 (VT-3 and i VT-4).- .The procedure and all examination data sheets are available-for review at the; plant site. l Examinations l Class 1 Twenty-eight (28) component supports from the B21, B31, Ell,.and G31 i systems were visually examined. Three (3) unacceptable-indications were detected.
-Class 2 Ninety-four (94) component supports from the C11, Ell, E41, E51, and Nil, systems were visually examined. Ten (10) of these Class 2 component supports were found unacceptable.
Class 3 Twenty-seven (27) component supports from the P41 system were visually examined. Four (4) of these-Class 3 component supports were-found to be unacceptable. After maintenance _and/or engineering evaluation, all of the unacceptable (' component supports were dispositioned per ASME Section XI and subsequently found to be acceptable. _ Where maintenance was involved, the component supports were re-examined to confirm acceptability. l L t-LO u 71
% I.-
1991 E.I. HATCH UNIT 1 P!PC SUPPORTS ( E ASME. CLASS SUPPORT FIGURE NO HANGER TYPE RESULTS REPORT NO. INF NO. MWO NO. RESULTS REPORT NO. . REMARKS 1 1B21 TORSION & LATERAL- H-16807 'S!MPLE A $91H1V229 N/A - 1 18.21-SS36 A-7/05 HYDRAULIC SNUBBER A S91H1V105 N/A 1 1821-SS37 A-7/05 HYDRAULIC SNUBBER A~ $91H1V107 N/A .. 1 1821 FDH-8 A-8/07 ' SPRING A $91H1V189 N/A 1 '1821-FDH-10 A-8/07- RESTRAINT U $91H1Y190' 191H1019 1-91-6468 A $91H1V238. . BENT PADDLE, SLIPPED BEARikG 1 1821-FDH-12 A-8/07 [ HYDRAULIC SNUBBER A S91HIV213 -N/A 1 1821-FDH-9 A-9/06 RESTRAIN'T A S91H1V106 N/A 1 1821-FDH-11 A-9/06 HYDRAULIC SNUBBER A S91n1V077 N/A
- '1 1821*FDH-1 A-11/04 SPRING A $91H1V187 N/A 1 1821-FDH-2 A-11/04 SPRING A $91H1V188 N/A 1 1821-FDH-13 A-11/04 ' MECH SNUBBER A S91H1V119 N/A'-
1 1821 rDH-13 A-11/04 MECH SNUSSER A S91H1V186 N/A 1 1821-FDH-19 A-11/04 HYDRAULIC SNUBBER A S91H1V120 N/A 1 1821-FDH-5 A-12/04 SPRING U $91H1V182 191H1019 N/A BROKEN TACE WELDS
' ACCEPTABLE AS IS PER GPC ENGINEERING.
1 1821-FDH-14 A-12/04 MECH SNUBBER A $91H1V118 N/A 1 1821-FDH-14 A-12/04 MECM $NUBBER A 591H1V185 N/A 1 1821-FDH-17 A-12/04 HYDRAULIC SNUBBER A $91H1V117 N/A 1 1821-rDH-17 A-12/04 HYDRAULIC SNUBBER - A 591H1V184 N/A 1 1821-FDH-18 A-12/04 HYDRAULIC SNUSSER A S91H1V116 N/A 1 1821-FDH-18 A-12/04 HYDRAULIC SNUBBER .A S91H1Y183 , N/A N N
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} Q ; 1991 E.I. HATCM UWlT 1 PIPE SUPPORTS ASME. CLASS. SUPPORT FIGURE NO HANGER TYPE RESULTS REPORT NO. INF NO. MWO NO. RESULT S REl T NO. REMARitS : 5-1 1821-FDH-20 A-12/04' MECH SNC BER A $91H1V115 N/A 1 1831+SSAT A-14/04 ' MECH SNUBBER A S91H1V114 N/A l
'1 1831-SSA13 A-148/01 ' HYDRAULIC SNUBBER A S91H1V124 N/A i
1 1831-5587 A-15/04 HTDRAULIC SNUBBER A S91H1V123 N/A 1 1631-55812 A-158/01' HYDRAULIC SNUSCER A S91H1V122 N/A 1 1831-55813 A-15S/01 HYDRAULIC SNUBBER A 591H1V121 N/A 1 1831-SSB14 A-158/01 HYDRAULIC SNUBBER A $91H1V149 N/A 1 1E11-SM-1 A-22/04 HYDRAULIC SNUBBER U $91H1V148 191H1016 N/A PADOLF IS BOUNO. ACCEPTABLE AS'- IS PER GPC ENGINEERING. 1 1E11-SM-1 A-22/04 HYDRAUt!C SNUB 5ER 'A S91H1V180 N/A' 1 1E11-SM-2 A-22/04 HYDRAULIC SNUBBER A S91H1V147 N/A , 1 1E11-UI A-22/04 ANCHOR A S91H1V094 N/A 1 1G31 RWCuti-2 A 32/04 RESTRAINT A S91H1v102 N/A
)
1 1G31-RWCUH-3 'A-32/04 SPRING' A $91H1V103 'N/A 2 1E41-HPSEH-29 B-18/04 SIMPLE A $91H1V135 N/A 2 1E41-PPSEH-30 8-18/04 SIMPLE A $91H1V054 N/A 2 1E11-RRRM-311 8-34/03 S]MPLE A S91H1V233 N/A 2 1E11-RHRH-312 6-34/03 MECH SNUBBER A $91H1V074 N/A 2 1E11-RHRH-313 8-34/03 MECH SNUBBER A $91H1V073 N/A , 2 1E11-RHRH-317 8-34/03 SIMPLE A $91H1V232 N/A t 2 1E11-RHRN-350 B-34/03 SIMPLE A $91H1V231 N/A N U r
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L u OT b"'{ l 1991 E.I. HATCH LEIT 1 PIPE StPPORTS [. ASME ! CLASS SUPPORT FIGURE NO ' HANGER TYPE RESULTS REPOR' NO. INF NO. MWO NO. RESULTS REPORT NO. PEMARits
- 2 1E11-RHRH B-35/03 SPRING A $91H1V035 .N/A
~
j 2 1E11-RRRM-314 B-37/03 $!MPLE 'A $91H1V034 N/A 2 1E11-RHRH-315 B-37/03 SIMPLE 'A: S91N1V165 N/A 2 1E11-RHRM-354 6-38A/01 SIMPLE A $91H1V039 N/A : 2 1E11-RHRH-197 B-40/03 SIMPLE' 'A S91H1V057 N/A 2 1E11-RHRH-198 B-40/03 ' SIMPLE A S91H1V056 N/A 2 1E11-RHRH-199 B-40/03 MECH SNUBBER A $91HIV055 N/A , 2 1E11-RHRH-713 B-42/04 MECH SNUBBER A S91HIV024 N/A
'2 1E11-RHRH-38 B-45/0/. SIMPLE A S91H1v083 N/%
. 2 1E11-RMRH-231 B-45/04 MECH SNUBBER A $91H1V038 N/A 1 2- 1E11-RHRI:-232 6-45/04 HYDRAULIC SiguB8tR A $91H1V075 N/A i 2 1E11-RHRH-367 B-45A/01 SIMPLE A $91H1VG08 N/A 2 1E11-RHRP-60 B-48/05 SIMPLE U $91H1V021 191H1002 1-91-5457 A $91H1V145 SLIPPED BEARING DISPLACED BEARING RACE 2 1E11-RHRN-61 B-48/05 SIMPLE A 591H1V022 N/A 2 1E11-RHRH-62 B-48/05 SIMPLE A S91H1v023 N/A 2 1E11-RHRH-63 B-48/05 $1MPLE A $91H1V052 N/A i 2 1E11-RHRH-64 8-48/05 SIMPLE A S91H1V053 N/A 2 1E11-RNR-H179 B-49A/00 SIMPLE A $91H1V069 N/A i 2 1E11-RHR-H180 B-49A/00 SIMPLE A S91H1V078 W/A l i 2 1E11-RNRM-81 B-51/04 SIMPLE A S91H1V015 N/A
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1991 E.I. H/.TCH 121T.1 PIPE'SUPPCRTS O ) ASME-CLASS SUPPORT- flGURE NO ; HANGER TYPE RESULTS- ' REPORT NO. INF NO. MWO NO. .RESULTS REPORT NO.' REMARKS.l 2, .1E41-HPSEH-39 -B-67/04 ' SIMPLE- 'A S91H1V133 - N/A 2 '- 1E41-NPSEH-41 B-67/04 SIMPLE A $91HIV132 'N/A
- 2, 1E41-HPSEH-63 B-67/04- HYDRAULIC SNUBBER' A. S91HIV072 N/A 2 1E41-HPSEH-63 B 67/04 . HYDRAULIC SNUBBER A- $91H1V131 N/A 2- 1E41-NPSEH-64 B-67/04 SIMPLE A $91N1V046' 'N/A
'2 1E11-RHRH-261' B-70A/00 SIMPLE A $91H1V101 N/A 2 1E11-RHRH-203 B-72/05 SIMPLE A S'21H1V144 N/A 2 1E11-RNRH-318 B-72/05 SIMPLE- A S91H1V089 N/A 2 1E11-RHRH-407 'B-72/05 SIMPLE U $91H1V091 191H1008 1-91-6129 A N/A SLIPPED BEARING' RE-EXAM BT GPC QC
> 2 1E11-RHRH-407A B-72/05 SIMPLE U 591H1V090 191H1008 l-91-6129 A N/A SLIPPED BEARING RE-ERAM Bf CPC CC 2 1E11-RHRH-409 B-72/05 ; ANCHOR A 591H1V064 N/A 2 1E41 HPSEH-78 B 73/05 SPRING 'U $9141V004 191H1003 1-91-5458 A $91H1V088 . IMPROPER SPRING CAN SETTING 2 1E41-HPSEH-724 B-73/05' MECH $NUBBER .A $91H1V002 N/A 2 1E41-HPSEH-735 B-73/05 MECH SNUBBER .A 591H1Y003 N/A ' 2 1N11-MSH-38 B-74/05 HYDRAULIC SNUBBER- A 591H1V068 N/A 2 1N11-MSH-22 B-74/05 SIMPLE A S91H1V066' N/A
'2 1N11-MSH-23 B-74/05 HYDRAULIC SMUBBER A S91H1YO65 N/A 2 1N11 MSH-25 B-74/05 SIMPLE A $91H1V067 N/A s
2 1C11-SK2-H17 B-84/02 SIMPLE A $91H1V193 N/A 5 2 1C11-SK2-H18 B-84/02 SIMPLE- A S91H1V220 N/A
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V v.. 1991 E.I. HATCH UNIT'1 PIPE SUPPC2TS ASME
- CLASS SUPPORT FIGURE NO HANGER TYPE. RESULTS REPORT No. INF NO. . PWO NO. RESULTS REPORT.NO. REMAPES i'
2' 1C11-SK1-H13 B-85/04 SIMPLE A '591H1V099' N/A . 2' 1C11-SK1-H14 B-85/04 SIMPLE U 591H1V225 191H1023 N/A SENT ROD ACCEPTABLE AS IS PER GPC ENGIkEERING.' ! 2 1C11-SK1-H7 B-85/04 SIMPLE' 'A $91H1V227 N/A
'2 1E51-RCICH-16 B-88/03 SIMPLE A 591H1V070 N/A 2 1E11-RHRH-118 B-8SC/00 SIMPLE' A 591H1V044. 'N/A 2 '1E11-RHRH-119 8-88C/00 SIMPLE A S91N1V042 N/A 2 1E11-RHRH-269 B-8SC/00 SIMPLE A $91H1V045 N/A 2 1E11-RHRM-272 8 88C/00 SIMPLE A 591H1V043 N/A 3 IP41-ISH 25 C-8/00 ' SIMPLE A S91H1V012 N/A 3 1P41-ISH-33 C-8/00 $1MPLE U 591H1VG11 191H1001 1-91-5454 A $9141V095 BENT PADDLE SLIPPED BEARING 3 1P41-ISH-29 C-9/00 SIMPLE A $91H1V010 N/A i 3 1P41-!SH-30 C-9/00 SIMPLE A $91H1V013 N/A 3 .1P41*SDGM-4 C-18/00 SPRING U $91H1V027 191H1001 1-91-5455 A $91H1V087 1MPROPER SPRING T'.N SETTING 3 Wi. M OGH 5 C-18/00 SIMPLE A $91H1VG26 N/A 3 1941-SDcw-7 C-18/00 SPRING U S91H1V025 191H1001 1-91-5455 A 591H1V093 IMPROPER SPRING CAN SETT!kG 3- 1941-SDGH-1 C-19/00 SIMPLE A $91H1V081 N/A
, 3 1P41-SDGH-2 C-19/00 . SIMPLE A $91H1V080 N/A 3 1P41-SDGH-3 C-19/00 S!MPLE. ;A 591H1V079 W/A f 3 1P41-SVH-18 C-21/01 ' SIMPLE A' $91M1V905' 'N/A N 00
1991 E.1. MATCH UNIT 1 PIPE SUPPORTS ASME REPORT NO. REMARKS INF NO. MWO NO. RESULTS SUPPORT FIGURE NO MANCER TYPE RESULTS REPORT NO. CLASS 1-91-5456 A 591H1V146 SENT F00 SIMPLE U 59141V006 191H1001 3 1P41-SWH-19 C-21/01 SIMPLE A 591H1V029 N/A 3 1P41-SVH-200 C-22/01 A 591H1VOO7 N/A 3 1P41-SWH-27 C-23/00 SIMPLE SIMPLE A S91N1V030 N/A 3 1P41-102H-802 C-24/01 SIMPLE A S91NiV031 N/A 3 1P41-SWM-223 C-24/01 SIMPLE A $91N1V033 N/A 3 1941-SWH-245 C-24/01 SIMPLE A 591H1V032 N/A 3 1P41-SWH-203 C-25/01 SIMPLE A 591H1V164 N/A 3 1941-SWM-180 C-36/01 SIMPLE A 591H1V150 N/A 3 1P41-SwH-B6 C-52/00 A 591N1V020 N/A 3 1P41-SWH-10 0-73/01 SIMPLE SIMPLE A $91H1VC10 N/A 3 1P41-SWH-11 C-73/01 C-73/01 S!MPLE A S91H1V018 h/A 3 1P41-SWH-12 SIMPLE A $91H1V017 N/A 3 iP41-SWH-13 C-73/01 SIMPLE A 591H1v041 N/A 3 1P41-SWH-148 C-73/01 SIMPLE A 591H1V036 N/A 3 1P41-SWH-15 C-73/01 SIMPLE A S91H1V040 N/A 3 TP41-SVH-16 C-73/01 l ~*s)
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SUMMARY
OF -{ NON-SAFETY NUREG-0313, REV. 2-INSPECTIONS
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O G J E.I. HATCH UNIT 1 FFLL 1991 REFUELIEG OUTAGE AUGMENTED EXAMINATIONS ASME EXAM EXAMINATION . CAL EXAM / CAL SECTION XI FIGURE NO. EXAMINATION / AREA ' PROCEDURE BLOCK SHEET NO. RESULTS PEMARKS-REACTOR WATER CLEAN-UP SfSTEM C-115/00 1G31-3RWCU-4-0-10 UT-H-400/10 145-H $91H1COS4 N/A UT CAL N/A, ELBOW TO PIPE S91H10092 NRI NUREG-0313S $91H1C050 N/A UT CAL
$91H1UO88 WRI S91H1UO93 N/A THICKNESS C-115/00 1G31-3RWCU-4 D-14 UT-H-400/10 145-H S91 HIC 055 N/A UT CAL N/A ELBOW TO PIPE S91H1UO94 NRI RUREG-03135 591H1C051 N/A UT CAL
$91H1UO89 N?!
591H1UO95 E/A THICKNESS C-111/00 1G31-3EWCU-4-HX-6 UT-H-400/10 145-M $91H10056 N/A UT CAL N/A PIPE TO ELBOW S91H10096 NRI RUREG-0313S 591H1C052 N/A UT CAL S91H1UO90 NRI S91H1UO97 N/A THICKNESS l C-116/00 1 G31 -3RWCU-4-R-5 UT-H-400/10 145-H $91H1C057 N/A UT CAL N/A PIFE TO ELBOW $91H10098 hRI NUREG-0313S S91H1C053 N/A UT CAL S91HlV091 NRI S91H1UO99 N/A THICKNESS l C-117/00 1 G31-3RWCU-4-R-34 UT-H-400/10 145-M $91H1C268 N/A UT CAL N/A l P!PE TO ELBOW $91H1U367 NRt l NUREG-03135 S91H1C177 N/A UT CAL
$91H10239 NRI S91M1C178 W/A UT CAL l
591H1U240 RI GEOMETRY
$91H10368 N/A THICKNESS l ()()
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i E.I. HATCH UNIT 1 FALL 1991 REFUELING OUTAGE AUGMENTED EXAMINATIONS ASME. ~ EXAM' EXAM! NATION CAL EXAM / CAL SECTION XI FIGURE NO. EXAMINATION / AREA PROCEDUPE . BLOCK SHEET NO. RESULTS REMARKS ' PEACTOR WATER CLEAN-UP SYSTEM C-108/00 1G31-3RWCU-6-D-2 UT-H-400/10 133-H $91H1C071 N/A UT CAL EXAM LIMITATION DLT TO WHIP-PIPE-TO ELBOW S91H1U113 .. NR I RESTRAINT, 94% COVERAGE.--- NUREG-0313S $91H1C082 N/A UT CAL
$91H1U131.. . NR I S91H10115 N/A THICKNESS C-108/00 1G31-3RWCU-6-D-3 UT-H-400/10 133-H $91H1C072 N/A UT CAL. EXAM LIMITATION DUE TO WHIP-ELBOW TO PIPE S91H10114 NRI RESTRAINT, 94% COVERAGE.
NUREG-0313S $91H1C081' N/A UT CAL
$91H1U132 RI GEOMERTY
$91H10116 N/A THICKNESS C-108/00 1G31-3RWCU-6-D-7 'UT-H-400/10 133-H S91H1C074 N/A UT CAL N/A ELBOW TO PIPE $91H1U117 ' NRI NUREG-03135 $91H1C075' N/A UT CAL i
S91H10118 NI
$91H1U119 N/A THICKNESS i
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SUMMARY
OF 1-l REACTOR PRESSURE VESSEL INTERNAL INSPECTIONS 1 4 g' 4 k s. 1 . . ,
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a- - y --. _ l i -83 se r J 6n +b--=_.v.----, . . _ _ _ _ mm..__ ____ _ ______._ _ _ ___.____ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ . . _ _ _ _ _ _m__ ._.____
1991 REACTOR PRESSURE VESSEL INTERNALS
~
-This section of the report provides a summary of the remote visual
("N examinations performed'by SNC and GE on selected RPV_ internals. The (_) visual examinations-were performed using SNC procedure VT-H-755 Rev.2. This procedure incorporates requirements for ASME Section XI, GE Service Information Letters where applicable and NRC IEB 80-13. All visual examination tapes were reviewed by SNC or GE certified level ', II and/or - III visual examiners to determine the acceptability of the various RPV internal components. CORE SPRAY SPARGER INSPECTION Per the requirements of NRC IEB 80-13, the core spray spargers and I associated piping were visually examined. Underwater video equipment recorded the examination results to the resolution of a .001-inch diameter visual acuity standard. No reportable indications were found. RPV INSPECTION Two _(2) RPV Clad Specimens designated during preservice inspection as ad patch #2 _0 135*, and #6 0 315' wera visually examined. The remrir...g internal ~ components selected for examination were the shroud support manway covers 0 0* and 180*; Surveillance Specimen Assemblies 0 30*, 120*, and 300*; six (6) shroud vertical welds; four (4) shroud circ. welds; and ten (10) fuel cell top guides, i No reportable indications were found. l
~ STEAM DRYER INSPECTION Remote visual examinations were performed on various components of the steam dryer which consisted of: support ring, vertical vane bank welds, lifting _ eye assembly, guide brackets and guide rod assembly 0 0* and 180*.
Rub marks and metal displacement were reported on the guide rod brackets. GE Engineering determined that the indications were acceptable for continued operation. No other reportable ir.dicatit.m were found. JET PUMP INSPECTIONS Remote visual examinations were performed on 10 jet pump inlet mixers in the throat area. The inspections of the inlet mixer throat area detected evidence of erosion.- A review of the 1990 IVVI tapes revealed the erosion
.was present during-those examinations. GE Engineering reviewed the tapes and determined that the inlet mixers were acceptable for continued operation.
No other reportable. indications were found. O 84
IdQ1STURE SEP2 BAT 9ElXAliU3ATIO!33 Remote visual examinations were performed on various components of the moisture separators consisting of lifting eye assembly 0 20*, 90' and O 270', guide brachet at O', and gtido rod assembly 0 0* and 180'.
!!o reportable indications were found.
ELIDHATER JPARGER A visual examination of the feedwater sparger 0 45', 135', 225', and 315'. consisting of the sparger arms flow nozzles and wolds, sparger tee flow nozzles and welris, sparger brackets, sparger brachet attachment weld was performed. !!o reportable indications were recorded. A11II review of the tapes was performed for the above listed examinations. The following pages contain a copy of the RPV internal inspection tape log which is an itemized list of all components and areas visually examined during the 1991 refueling octage. This log, along with the video tapes, is maintained by the onsite document control department. O e O a5 l
GE Nuclear Energy O E.1. IIATCII UNIT 1 INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Pace 1 of7 TAPE TAPE COhlPONENT DESCillPTION EXAh11NER NUhlllER COUNTS INITIALS Ellil-91 1 00000 01713 180' hianway Cover (labeled as 0* Cover) SPF
' Ellll 911 01713 02224 0' hianway Cover SPF 41111 91 1 02224 02946 Pre decon 350' Core Spray Spa ger Tee Box Bracket SPF 1",3",5", and 7" camera screen sizing S 70 5 Ellil 91 1 02946 03211 Ellil 91 1 93211 03313 .001" Camera Resolution 101191,0900 hours S 795 Ellil 91 1 03313 04821 Drain pipe #4 S7#5 S 70 5 Ellil 91 1 04821 05406 Vertic il Bank Weld #31 Ellil 91 1 05406 10512 Drain Channel #7, Right Side S7#S Ellil-91-1 10512 13753 Drala Channel #7,left Side Mv$
Ellil 91-1 13753 14459 Drain Channel #7, Top Side M#W Ellil 91-1 14459-20111 Vertical Bank Weld #32 Mv$ EII11-91 1 20111-21517 Vertical Bank Weld #33 5795 Ellil-91-1 21517 21629 Horizontal Weld between Vertical Bank Weld #32 & 33 S?#5 Ellil 91 1 21629 22837 Vertical Bank Weld #34 57#S Ellil 91 1 22837 23519 Vertical Bank Weld #35 S7vS Ellil 91-1 23519 24346 325' Lifting Eye Assembly 57#S l ElH191 1 24346 25823 Vertical Bank Weld #36 57vS Ellil 91-1 25823 30325 Vertical Bank Weld #37 5795 O Ellil 91 1 30325 31516 Vertical Bank Weld #38 5795 Ellil-91-1 31516-34141 Drain Channel #8, Right Side Mv$ LPlV91/19
GE Nuclear Energy O E.I. HA TCH UNIT 1 INVESSEL VISi]AL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 2 of 7 TAl'E TAl'E COhll'ONENT DESCitli' TION EXAhllNER NUhlllElt COUNTS INITIALS Ellil 91 1 34141 41229 Drain Channel #8, Left Side 77#W Ellil 91 1 41229-42057 Drain Channel #8, Top Side PfvW ElH191 1 42057 42340 .001" Camera Resolution 1012 91,0800 hours SN { E1111912 00000-01143 Vertical Bank Weld #39 SN Ellil 912 01143 02029 Vertical Bank Weld #39, (previously found indications) EN Ellll 912 , 02029 02825 Vertical Bank Weld #40 SN ElH1-91-2 02825 03436 Vertical Bank Weld #1 SN EIH1-91-2 03436-03716 Horizontal Weld between Vertical Bank Weld #1 & 40 SN ElH191-2 03716 04628 0' Upper Guide SN ElH1912 04628 05203 0* Skirt Vertical Weld SPF EIH1912 05203 10205 0* Lower Guide Lf5 ElH1-912 10205 10736 Vertical Bank Weld #2 AfS ElHl 912 10736 11738 Vertical Bank Weld #3 Af5 EIH1912 11738 12747 Vertical Bank Weld #4 & the adjacent Horizontal weld Lf5 ElH191-2 12747 13630 Vertical Bank Weld #5 & the adjacent Horizontal weld LfS EIH1-91-2 13630 14830 Drain Channel #1, Right Side LfS ElH1-912 14830-20017 Drain Channel #1, Left Side Lf5 ElH191-3 00000-00308 Drain Channel #1, Top Side SN ElH1-91-3 00308 01457 Vertical Bank Weld #6 SPF ElH1-91-3 01457-03049 Vertical Bank Weld #7 SPF 87
O V GE Nucicar Energy O E.I. HATCII UNIT 1 INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 3 of 7 TAPE TAPE COh1PONENT DESCRIPTION EXAh11NER NUMilER COUNTS INITIALS Ellil 91-3 03040-04300 35' Lifting Eye Assembly 6PF Ellll-91-3 04300 05340 Vertical Bank Weld #8 SPF Ellil 91-3 05340-05526 11orizontal Weld between Vertical Bank Weld #8 & 9 SPF Ellil 913 05525 10910 Drain Channel #2, Right Side SPF Ellil 913 10910 11135 Drain Channel #2, Top Side SPF Ellil 913 11135 12033 Vertical Bank Weld #9 %d5 g v %d5 Ellil 913 12033 12733 Vertical Bank Weld #10 Ellil 91-3 12733 14502 Drain Pipe #1 %d5 Ellil 913 14502 15325 Drain Channel #2, Left Side 545 Ellil-91-4 00000-00100 .001" Camera Resolution 10-13-91,0900 hours SPF Ellil 91-4 00100 02050 Vertical Bank Weld #19, (Previously found Indications) %d5 Ellil 914 02050 04320 Vertical Bank Weld #22, (Previously found Indications) %d5 { Ellil 914 04320-04408 .001" Camera Resolution 1014-91,0845 hours 6PF Ellil 91-4 04408 05055 180' Upper Guide 6#8 ! EI!11914 05055-05441 180* Skirt Vertical Weld 6M
' Ellil-91-4 05441 -10819 180* Lower Guide sPF
= - -
Ellil-91-4 10819-12125 Upper Support Ring , (Previously found Indications) 6PF O' Ellil-91-4 12125 12308 Tie Bar #7 6PF Separator,90' Lifting Eye Assembly SPF Ellil-91-4 12308 12927 Separator,20' Lifting Eye Assembly SPF , EII11-914 12927 13517 88
GE Nuclear Energy 0 E.1. HA TCH UNIT 1 INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 4 of 7 TAPE COh1PONENT DESCRIPTION EXAh11NER TAPE COUNTS INITIALS NUh111ER Ellil 914 13517 13836 Separator, O' Guide 6P6 Ellil 914 13836 14330 Separator,270* Lifting Eye Assembly 6FF ElH1-91-4 14330 14400 .001" Camera Resolution 10-14 91,1300 hours SPF l Ellil 91-5 ~ 00000 00050 .001" Camera Resolution 1017 91,1940 hours SPF l E!Ill-915 00050-02030 0' Guide Rod Assembly WS 180* Guide Rod Assembly "N A S Ellil 91-5 02030 03549 WS O Eiiil-915 03549 03640 Ciaddin8 eatch ai ElH1 91 5 03460-03740 Cladding Patch #6 WS ElH1-915 03470-04100 120' Surveillance Specimen Assembly WS EIH1915 04100 04440 300* Surveillance Specimen Assembly WS EIH1-915 04440 10500 45' Feedwater Sparger M l EIH1-915 10500 12840 135' Feedwater Sparger M
- ElH1-915 12840 14900 225' Feedwater Sparger MS EIH1-915 14900 20315 315' Feedwater Sparger WS EIH1916 00137 01019 315* Feedwater Sparger WS EIH191-6 01019 10635 Core Spray Internal Piping 10' to 170*
M l EIH1-916 10635 10800 .001" Camera Reso'ution 10-18-91,0715 hours M core Spray Internal Piping 190* to 330' DS7 I O ElH1916 10800 20331 DS'7 ElH1917 00000-00049 .001" Camera Resolution 10-18-91,1000 hours Core Spray Internal Piping 330' to 350* DS7 EIH1-91-7 00049-02500 j l 89 --
l l 9 GE Nuclear Energy O E.1. IIATCII UNIT 1 INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 5 of 7 TAl'E TAPE COMi'ONENT DESCRIPTION EXAMINER NUMBER COUNTS INITIALS Ellil 917 02500 12210 Core Spray Spargers 90* 180* 270' Sparger & NorrJes 64 Ellil 917 12210 20343 Core Spray Spargers 90'- 0*- 270* Sparger & NozzJes DS7 Ellil-918 00000 01425 Core Spray Spargers 90* 0* 270' Sparger & NozrJes DS7 Ellil-918 01425-10340 Core Spray Spargers 90*- 0'. 270' Brackets & welds iM 10340-14027 Core Spray Spargers 90*-180' 270' Brackets & welds 'KdS Ellil 918 , Ellll 918 14027 14500 .001" Carnera Resolution 1018 91,2200 hours WS ElH191-8 14500 15225 0' Guide Rod (Upper 2') MM O Ellil 918 15225 20114 180' Guide Rod (Upper 2') VM ElH1 91-9 00000 02228 Shroud cire, weld #SHR C 5 (outside surface) MM Shroud vertical weld #SHR V-6 & 7 (outside surfacc)
'KdS ElH1919 02228 03309 Shroud vertical weld #SHR V 9 (outside surface) 'KdS ElH1 91-9 03309 03528 Ellil-919 03528-03558 .001" Camera Resolution 1019 91,0545 hours MM Ellil 91-9 03558 03729 Shroud vertical weld #SHR-V-4 (outside surface)
MM Ellil 91-9 03729 03859 Shroud vertical weld #SHB V-5 (outside surface) MM ElH191-9 03859 04156 Shroud vertical weld #SHR V-7 (inside surface) MM ElH1919 04156-04337 Shroud vertical weld #SHR V 6 (inside surface) FM
' ElH191-9 04337 04456 Shroud vertical weld #SHR V 8 (inside surface)
MM
.001" Camera Resolution 10 20 91,2315 hours MM ElH1 91-9 0-1456 04540 A WS V ElHl 91-9 04540-13602 Shroud cire, weld #SHR-C-5 (inside surface)
Shroud cire, weld #SHR-V 9 (inside surface) Lf6 ElH1-91 9 13602-14321 Tspe labeled as #SHR-V-5 90
GE Nuclear Energy 0 E.I. IIA TCII UNIT 1 INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 6 of 7 TAPE COh1PONENT l'ESCRIPTION EXAh11NER TAPE NUhlllElt COUNTS INITIALS Ellil 919 14321 14436 Shroud vertical weld #SliR V-5 (inside surface) %d5 Ellil 919 14456 20026 Shroud cire, weld #SilR C 4 (inside surface) MM Ellil 91 10 00000-01628 Shroud cire, weld #SilR C 4 (inside surface) MM Ellil 91 10 01628 04024 Shroud cire. weld #SliR C 4 (outside surface) DS7 Ellil 91 10 04024 04234 Shroud vertical weld #S11R V-8 (outside surface) DS7 Tape labeled as #SilR C-4 Ellil 91 10 04234 04401 Shroud vertical weld #SilR V-4 (inside surface) DS7 O Ellil 91 10 04401 04602 Shroud vertical weld #SliR V-4 (outside surface) DS7 . Ellil 91 10 04602 04741 .001" Camera Resolution 10-21-91,1030 hours DS7 ' Ellil 91 10 04741 04920 Jet Pump #1 Sensing line 6M Ellil 91 10 04920-05204 30' Surveillance Specimen Brackets EFF Ellll 91-10 05204 05502 Jet Pump #1 hiixer Area and Riser to Riser Weld 6PF Ellil 91 10 05502 05800 Jet Pump #2 Mixer Area and Riser to Riser Weld 6PF t Ellil 91 10 05800 10135 Jet Pump #3 Mixer Area and Riser to Riser Weld 6PF Ellil-91 10 10135 10420 Jet Pump #4 Mixer Area and Riser to Riser Weld $N E1H1-91 10 10420 10900 Jet Pump #5 Mixer Area and Riser to Riser Weld 6PF ElH1-91-10 10900 11135 Jet Pump #6 Mixer Area and Riser to Riser Weld 6PF EIH1-91-10 11135 11444 Jet Pump #7 Mixer Area and Riser to Riser Weld 6PF l ElH191 10 11444 11700 Jet Pump #8 Mixer Area and Riser to Riser Weld 6PF Ellil 91 10 11700 11935 Jet Pump #9 Mixer Area and Riser to Riser Weld  l Jet Pump #10 Mixer Area and Riser to Riser Weld SPF l ElH191-10 11935-12219 l 9l
9 GE Nuclear Energy E.I. HATCH UNIT 1
\
INVESSEL VISUAL (IVVI) TAPE LOG REFUELING OUTAGE #13 - OCTOBER,1991 Page 7 of 7 TAPE COMPONENT DESCRIPTION EXAMINER ; TAPE COUNTS INITIALS NUMBER E;c1r ; Ellll 91 10 12219 12420 Jet Pump #10 Sensing line Ellil 91 10 12420 12915 Relook @ 45' Feedwater Nozzle Inner Radius Area 6Pii Ellll 91 10 12915 13046 .001" Camera Resolution 10-2191,1345 hours 6Pii N/A Ellll 91 11 N/A NOTE: TAPE LADELED AS Ellil 91-TG 1 Top Guide Cell # 06-27 WE Ellil 91 11- 00000 00537 WE Ellil 91 li 00537 00845 Top Guide Cell # 10 39 O EL"I-91 11 00845 01356 Top Guide Cell # 1015 WE WE Ellil 91 11 01356 01845 Top Guide Cell # 22 23 01845 02452 Top Guide Cell # 22-31 WE Ellll 91-11 . Top Guide Cell # 30 31 WE Ellil 91-11 02452-02851 02851 03327 Top Guide Cell # 30 23 WE , ElH191-11
.001" Camera Resolution 10-23 91,2345 hours WE ElH191 11 03327 03436 Shroud Vertical Welds # SliR V 9 Relock WE ElH191 11 03436 04111 Shroud Vertical Welds # SliR V 8 Relook WE/EF1r EII11-91 11 04111 04902 Control Rod Blade Cell #39-02 WE Ellil 91-11 04902-10615
, ElH191-11 Top Guide Cell # 42-15 WE 10615 11110 WS Elhi 91 ll 11110 11711 Top Guide Cell # 42 39 M8 O
EIH1-91 11 11711-12059 Top Guide Cell # 46 27 92
i: j-i
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SUMMARY
i- [ OF CIASS 1 AND 2 l REPAIRS AND REPLACEMENTS a ] i d
?
i-. i-t' i-l ': 5: 93 l~
l l IREPAIRS AND R12iACEME11TS 1 GPC procedure 42EN-ENG-014-OS provides guidelines for determining the ASME Section XI, repair / replacement requirements at E.I. Hatch Nuclear O Plant. The site Repair / Replacement Coordinator maintains an itemized listing of class 1 and 2 repair / replacement activities for each cyclo. The following tables provido an itemized list of those components which were included in the ASME Section XI Ropair and Replacement Program. (Class 3 items included for information only) Copios of the individual Repair /Roplacement ovaluation shoots are filed with tho.MWO Pac}; ages and are available for review at the sito. l O 1 i L O 94' __ _ - - . _ - . . - . _ _ _ ._ _ _ . _ . . _ _ . _ _ - . _ , _ . . - _ . _ - - , . _ _ _ _ . _ . . . ~ _ . _ _ _ _ . . - . . _ _ . . .
[ REPAlR AND kiPLAtlMlWI fitts UN11 1 1971 COMPONtNI DISCRIPil0N ft$1 RIMARA$ kWO 189 4690 O **tuPPOR15 1821 MODif Y $UPPDRi$ 1821 f 6 H002, f 4 H001, f H H10 AND FD H11 10 COMPLY W11H THE REQUIRIMthi$ VI 3 EVALUAllON (DR ACCtPTAbilltf WA8 fthf0RMID AS PARI of DislGN CHANGC PACLAGt $1 0$8. Of it 8
- T9 14
*
- MJO i 89 4 770 iP42- M00lFY $UPPOR18 iP42 CCW H117, VT 3 (VALUA110N fot ACCEPTABILl1Y WAS
$UPPORI$ H118 AND N116A Pit THE f'tRf 0kMID Al PART Of DillGN CHANCC Rt0VIRIMENil Of itB 7914, rACKAGE 81 058.
** MWo 1 89 5053 itti F050s BONNt1 CA$tti LLAttD DUR!NC f t$1 DURING VIs$tt PRits.1151 OLD 00khti CA$tti WilL 6t RtPAlRED WlIN ,
CHICK VALVE - HYDRO f t$1, REPL ACC BONWil APPROVCD CA$tti 104 THl$ VALVI. j CA$tti. ANilCIPAf tD f AILURE FDR THIS TYPt VALVE. REPAlR WAS LI$1tp IN LAST NIS*1 RtPORT BUT N01 UNDfR RtPAlt AND ktPLAttMINI.
** MWo 189 5057 1821 70108 VALVE HAS PRit$URt $t AL Lt AK, NDRMAL PR($$URE It$1 THt$t TYPE REPAIR $ ARE ANTICIPATID DUE CHICK VALVE RIPA!R f'tR MAIN 1LNANCE 10 $tRVICE $lth BY INI$t TYPE VALVES.
PROCfDURE $1GM MN1023 05. IROCtDURE IS APPROVID FOR THIS AtilVl1Y. REPAlR WAS Li$1tD ON LA$1 NIS 1 FORM, BUT N01 UNDER R/R. ,
** MWO 1 89 5059 l iP42 MODif Y $UPPOR18 f tR llD 7914 VT 3 (VALUA110N 10R ACCT >1ABILl1Y WAS i SUPPORTS PERFORMED A5 FART Of 1HE DillGN CHANGE CCWH+113 AND PACKAGE.
119
** MWO 1 89 5060 1P42 . M00!ff $UPPORit 1P42 CCW H115, vi 3 (VALUA110N FOR ACCtP(ABILl1Y WAS *
$UPPOR15 H1154, H116 AND M700 10 COMPLY PERIORMto A$ PAR 1 Of INE Dis!GN CHANct -
Wl1H IIB 79 14 PACKAGE 81 058.
'** MWO 1 89 6010 1t11 f 0559 REPLACE DISC, DISC HAS SURFAtt RELitt VALVE list 42sv SUV 004 REPL ACING THE DISC is A NORMAL Mt1H00 0F IRRtGULAtl11t$ AND WILL NOT Rif AIR. NORMAL WE AR IDR TH15 TYPt PASS l!AK AGE 1[$1 $tRVitt. DISC REPL ACEMENT WAS Litt IN KIND RtPLACIMIN1. I
** MWO 1 89 6158--
$U0POR16 MOD!fy Pitt $UPPORTS itti RHR- VT 3 -N/A
-H182, H380 AND H381 10 COMPLY W11H IIB 79 14 l
~** MWo 1 89 6874 it11 MODIFY SUPPORi$ 1E11 RNR H V1 3 fvALUA110N FOR ACCEPTABIL11Y WA5 *
$UPPORi$ - 344,345 AhD 70810 COMPLY V!1H PERFORMED AS PART OF THC DEslGN CHANGE IfB 79 14 PACKAnt 81 058. -
I
** MWO 1 89 6902 PIPlkG REMOVE AND RISTORE $tcil0N$ OF HYDRO N/A PLAN 1 5tRVitt WAt[R PIPING 10 DR1WELL COOLERS 147 8007A/B, 147 8000A/B AND 147 6009A/B 10 FACIL11ATC REPLACEMENT Of DRYVELL COOLING CO!LS.
** MWO 1 90 0097 it21-$UPPORT MODITY $UPPORI 10 COMPLY W11H VI 3 IVALUAllON f0k ACCEPTABIL11Y PCRfDRMED CSH 60 IEB 79 14 AS PART OF THE DESIGN CHAhCE PACKAGE.
** MWO 1 90 0570 litt $UPPORT M00!f f $UPPORY 10 COMPLY W11H VT 3 [VALUAlloN FOR ACCEPTA$lLl1Y WAS RHR H 304 THE REQUIREMINTS OF IIB 79 14 PERFORMED AS PART OF DE$1GN CHANGC 4 ** MWO 1 90 0572 l .SUPPOR1 MODiff $UPPORT 1C41.F1 H002 10 NONE RioVIRED [VALUA110N WAS PERFORMED AS l
COMPLY Wl1H llB 79 14 PART OF THE DCR PACKAGE T 95
REPAlR AND REPL AEEMENT flLE$ UN11 1 1971 COMPONE NT DESCRIPil0N TE$i REKAkK$
** MWc 1 90 0$T3 O- SUPPORTS (VARIOUS)
MODIFT $UPPOR1$ 1821 MVVH 700, H 701, H 702,1821 $$ 3, $, NONE EVALUA110N FOR INESE SUPPORi$ PROVIDED W11H DCR 81 058. 14, 29, 10 COMPLY W11H IEB 79-14.
** MJO t 90 0$73 1921 M001FY SVPPORis 1921 MVVM 700, VI 3 EVALUA110N FOR ACCEPTABiliff WA$
SUPPORi$ 701, 702, 1921 $$ 3, 5, 14 AND PERf0RMED As PART OF DESIGN CHANGE 29 PER THE REDVIREMEN15 0F IES PACKACE 81 0$8. 79 14. ,
*
- MWO 1 90 1584 1921 M51V VALVE FAILED LLRt. REPA!R At TE$1 DURING VEstEl PRESS.1EST THit i$ ANilClPATED FAILURE FOR THi$ ;
F022C NECE$$ARV, 1YPE VALVE UNDER THESE $ERVICE CONDlfl0N$. PROCEDURE $2CM 921 001 0$ 15 APPROVED FOR THit REPAIR. REPAIR WA$ LlSTED lW LA51 NIS*1 REPDRI BUT N01 UNDER R/R.
** MWO 1*90 20$6 1148- FABRICATE AND IN$1ALL PlPE VT 3 EVALVA110N FOR ACCEPTABillif WAS j i
$UPPORTS CP* $UPPORi$ PER DES!CN CHANGE PERFORMED AS PART OF DESIGN CHANCE 704 AND 707 PACKAGE 88 267 PACKAGE,
** MWO 190 2648
$UPPDRT MD0lFY $UPPORT 10 COMPLY Wl1H kONE EVALUAll0N WAS PROVIDCD As PART OF THE 1821+H820 IEB 19 14 DCR (81 058)
** MWo 1 90 3236 2P41 F050 REPLACE DISC W11H NEW DISC NONE N/A VALVE FROM WAREHOUSE STOCK. VALVE l$
IN WAREHOUSE AS $ PARE. i
** MWO 190 3888 1821 F020 REPLACE WORN DISC AND N/A REPLACEMENT OF PARI $ l$ BEING PERf DRMED
&F038- ASSOCI ATED VALVE INTERNALS UNDER AN APPROVED MAINTENANCE AND INSPECTION PROCEDURE. PARI $ U$ED WILL BE PROCURED UNDER APPROVED PROCUREMENT PROGRAM.CAUSE OF FAILURE WORMAL WEAR.
** MWO 1 90 7476 blESEL clt . PLANI $ERVICE WATER TUBE LEAKS F1 PER PROCEDUR[ TUBE PLUGG!NG lt AN ACCEPTABLE METHOD OF CDOLER 1P41 HAVE BEEN DETECTED ON 1R43 ALLEVIAllNG LEAKAGE. THE CAUSE OF B003 AND B005A TUBES WILL BE LE AKAGE /IUBE FAILURE 15 DUE 10 LEND 1Hf
- PLUGCED PER INSTRUCT 10N! FROM SERVICE IN A MAR $H P$W PlVER WATER A/E (NVIRONMENT.
** MWO 1 91 0020 REV 1 1E41*F050 VALVE WILL NOT.$ EAT PROPERLY, REll!F VALVE FUNC110NAL TEST. PISC 18 BEING REPLACED UNDER AN APPROVED REllEF VALVE REPLACE Ditt. MAINTENANCE PREVENTAllVE MAINTENANCE PROCEDURE. SKILL OF CRAFT, NORMAL WEAR.
EXPEC1ED FAILURE.
** MWO 1 91 0634 ~
1E11 F082A REPLACE WEDGE IN VALVE. WEDGE CHECK FOR LEAK $ AT FRESSURE WEDGE WAS REPLACED UNDER A CONTROLLED VALVE. WILL NOT SEAT Off. MAINTENANCE PROGRAM, PARY WAS PRDCURED UNDER AN APPROVED PRDCUREMENT PROGRAM. CAUSE OF FAILURE is NORMAL bTAR FDR COND1110NS.
** MWO 1+91+1783 P 41- REPLACE CARDON $1 EEL BOLi$ N0kE BOLi$ WERE REPLACED DUE 10 HICH C001, A,B,C,D W11H ST AINLESS $f EEL Bott$. CORR 0510N PROBLEM IN MOISTURE LADEN ENV!kONMENI. INTAKE STRUCTURE
** MWO 1 91 2038 R/R1 1E11 F055A NO DAMAGE EXPERIENCED ON CHECK FOR LEAKS AT PRESSURE N02ZLE 10 BE REPLACED Wi1H IDENilCAL NO22LE N0ZZLE TO BE REPLACED. ?!ME NO22LE IN ACCORDANCE WITH APPLICABLE s RESTRAlkit REQUIRE NEW N0ZZLE CODES AND PROCEDURES.
10 BE PUI IN DUE TO INABILITY 10 MACHINE OLD N0ZZLE IN A a ifMELY MANNER. 96
1 RIPAlR AND REPLAtlMiki flLEl l UN11 1 1991 l COMPONENT DE$CRIP110N TE$1 RE MAR KS
" MW3 1 91 + 2038 h/R2 1E11 F055A DISC 10 BE RIPL ACID HAS SMALL CHECK IDR Lt AL$ Al PRESSURE REPLACEMENT OF DISC WILL BE IN VALVE DISC INDICA 110NS WHICH ARE ACCol! DANCE WITH ALL APPLICABLE CODES AND UNACCEPIABLE. DISC CANNOT BE PLANT FROCEDURES. CAUSE OF F AILURE il MACHlWED AND MUST BE REPLACED. DUI 10 NORMAL WE AR.
" MWO 1 91 2D41 1E11 7091A REPLACE VALVI $ FEM AND PLUG CHECK f0R r- 7 AT PRESSURE $1tM REPLACEMtWT 18 DUE 10 Plit IN VALVE -Al$EMBLY. VAR 10VS LOCA110N$. PLUG REPLACEMINT l$
DUE 1D PREVIOUS MACHINE WORK. NEW PAR 18 ARE $U11ABLE FOR PROPER RLPAIR.
" MWO 1+91+2D43 1E11 714DA REPL Att VALVE WEDGE. CRACK IN TEST A1 $Y$ TEM PREt$URE CAUSE OF FAILURE is UNKNOWN A1 INil VALVE WEDGE. 11ME. REPLAttkENT WILL BE UNDtR AN APPROVED PROCUkEME68f AND REPLACIMENT PROGRAM.
" MWO 1*91 2D44 R/R1 IE1141400 REPLACE WEDGE AND sitM. CHICK FOR LEAKS At PRES $URE $1tM REPLACEMENT 15 DUE 10 6 AGATE UN$Atl6FACTORf RUNOUT CHECK. WIDGE VALVE. REPLACEMINT l$ DUE 10 UNACCEPTABLE fli IN SEAT AREA. CAU$E OF lA! LURE APPEAR $
10 EXE NORMAL WEAR.
" MWO 1 91+2044 R/R2 1E11+F14DB BONNET $1UD$/NU15 ARE BEING CHECK FOR LEAKS Al PRE $$URE $fUD$ DAMAGED DURING MAINTENANCE. NOT AN 6"CATE VALVE REPLAtt0 DUE 10 DAMAGE CAU$tD INSERVICE FAILURE. IXACT REPLACIMENT IN
- DURING REMOVAL. KIND MATERIALS.
" MWO 1 91 3164 iP41 C0018 REPLActMENT OF CARBON STEEL CONFlRM PUMP OPERABillif. N/A PUMP BUWL PUMP BOWL WITH STAINLESS $ FEEL l PUMP ' +II.AND AS$0CIAffD i , BOL60 PER DCR'85 D49.
" MWO 1 91 3182 1P41 PIPING REPLACE PORT 10N OF $ERVICE OrERAllNG PRES $URL TEST PlPlNG WAS RlPLACED DUE 10 $EVERE WALL I WATER MINIMUM FLOW LINE FROM DIGRADAll0N DUE TO 1HE CORRoslVE kA10RE THE PSW PUMP 1P41 C001A 0F 1HE !ZRVICE WAttR AND INE HlGH FLUlD DISCHARGE HE ADER TO THE flR$1 VELOC11Y IN THE PIPE.
FLANGE AND IROM THE 3 x2.5 REDUCER TO 1HE INLET OF 1P41 F091A.
" MWO 1*91 3163 1P41 PIPING REPLACE PSW PlPlkG MINIMUM $URFACE AND OPERATING PRES $ uke PIPlNG WAS REPLACED WlfH LIKE IN KlWD FLOW FROM THE P5W PUMP MAftRIAL UstkG APPROVED PROCEDURES.
Ol& CHARGE HEADER TO THE INLET CAUSE OF FAILURE !$ Ex1 ENDED SERVICE IN OF VALVE $ 1P41 F2DBC AND A HIGH VELOC11Y AND CORROSIVE fB91C. ENVIRONMENT. RIVER WATER.
" MWO 1*91 3184 -
1P41 PlPING REPL ACE THE PSW MINIMUS' FLOW SURFACE PIPING 1$ BEING REPLACED UNDER A CON 1ROL PIPING FROM THE P$W PUMP OPERATING PRESSURE PROCEDURE AND PROCURIMENT PROGRAM. CAU$E DISCHARGE HEADER TO THE INLET OF FAILURE l$ PIPE DEGRADAil0N DUE 10 0F VAlvis 1P41 F2D8D AND iP41- THE CORRoslVE NATURE OF THE SYSTEM AND f891D, AND ASSOCIATED TUBING HICH FLUID VELOC11Y. AND FlitikCS DOWNSTREAM OF iP41 F891D.
" MWo 1 91 3165 -- ..
1P41 PIP!NG REPLACE 16E P$W MINIMUM FLOW $L'R F ACE PIPING REPLACED UNDER APPROVED PIPING FROM THE PSW PUMP OPER AflNG PRESSURE . PROCEDURES AND PROCURIMENT PROGRAM DISCHARGE HEADtR 10 THE INLET FAILUkE DUE 10 CORROSIVE kATURE OF OF VALVES 1P4142D88 AND 1P41' SYSTEM AND HIGd FLUlD VELOCITT. F8918. AND AS$0CIATED TUBING AND F11 TINGS DOWNSTREAM OF 1P41 F8918.
** MWO 1+91 3518 R1 1E21 F036B ikBODY SEAT AND DISC WERE VISUAL AND $URIACE $E AT AND DISC WERE MACHINED TO REMOVE CHECK VALVE TOUND 10 BE P!11ED AND !NDICATIONS. NORMAL WEAR FOR CONDifl0NS.
$CARRED, MACHINE SEAT AND DISC TO RIMOVE INDICA 110NS.
97
EfFAIR AND RtPLAttPINT litt$ UNil i 1991 l COMPONENT DESCRIPilDN TE$f RtMAtt$
** MW3 1 91 3522 R/R1 1P41 F$$2A CHECK VALVE IW1(RNALS Att WORN CHICK FOR LE AK$ Al FRES$URE VALVC WA$ REPLAtt0 WifH A CDHMERCIAL CHtCK VALVE AND DEf tRIDRAf tD. REPL Att Vlf H UPGRADED VAlvt UNDER AN AftROVED UPGRADt AN APPROVID VALVI. PROGRAM. CAUSE OF F AILUkt l$ NDRMAL IDR THE HAk$H CONDill0NS SitN BY THE VALVI.
(RIVER WAltR)
** MWO 1 91 3$?2 R/R2 iP41 f552A CatCK VALVt INitRhAL$ WtRt $URFAtt AND OPERATING PRCs5URE REPAIR $ 10 VALVE BODY AND $tAL AttA WILL CHICK VALVE FOUND WORN AND Dtitt!DRAf tD. Bt PEkFORMED UNDER CON 1ROLttD WILDikG NO NEW VALVI l$ AVAILABLE $0 PR00tDURES AND MACHINED. CAU$t OF VALVE $tAL MUST $1. SUlti UP ( AILURt l$ Of(RAll0N IN A HAR$H AND MACH!ktp. (NVIRONMENT. (RIV[R WAl[R)
** MWO 1 91 3$49 1141 80034 NtLSON STUD $ THAT ilGHi&N THE CHtCK f0R LIAKS Al PRC$$UR! $10D$ WtRE REPL ACID Wlf H NCW $1UD$,
HEAT C00Ltt HEAD TO THE FLANGt WtRt USING AN APPROVtD WILDlWG PROC!DURt. EXCHANGtt f0VND 10 BE DritRIORAl[D. CAUSE OF FAILURt l$ Ek1 ENDED USE IN , RtPLACE SY $1UD WELDING. HAR$H INVlRDNMfNI.
'** MWO 1 91-35$0 1141 60038 NELSON STUD $ ON HEAT EXCHANGER CHECK FOR LIAK$ At FkES$URE. NFW $1U05 WCRt WELDED DN WliH AN HEAT ARE DEltR10 RAT [D. WELD NEW APPROVID VfLDING PROCtDURE. $TUD$ Att ,
EKCHANGER STUD $ DW. NOT Rt0UlktD 10 BE ASMC MAffRIAL.
** MWO 1 91 3553 ii41 8005A kit $0N stud $ AfflXtD 10 C00 Lit CHECK FOR LEAKAGE DURING OPER. STUDS WERE RtPLAftD WiiH $AMC APPROVID COOLER TUBt $Htti$ HAvt (R00fD AND STUD WILDING PROCEDURE AND MATERIALS. ,
FALLEN OFF IN SOME CA$t$. CAU$t Of f AILURE l$ HAR$H ENVIRDNMtW1 REPLACE $1UD$. OPtRAll0N (RIVER WAf[R)
** MWO 1 91 3554 1141 80058 Ntt$0W $1UD$ Af fixtD TO CDOLEP CHECK FOR LEAK $ DURlNG DPCR. $1UD$ ARE BElkG R!PLACED WifH APPRDVfD C00Ltk TUDE $Hiti$ HAVI (R00tD AND IN A$ME $1UD WELDING PROCEDURE AND
/ $0ME CA$ES TALLEN OFF. REPLACE M4ltRIAL. CAU$t Of FA! LUKE l$ DUE TO STUD $. [KPOSURE 10 HAR$H [NVIRDNMENT (RIVER WAl[R)
** MWO 1 91 3668 1011 0146 REPLACE CRD FLANGE BOLT $ WHICH IN$PECT DURING VI$$EL P.T. BOLi$ AR[ [ XACT REPL ACEMtNT lN KlND.
CONTROL ROD VERT 70VND 10 HAVE RCJECTABLE INDICATIONS ON BOLilNG l$ EXPECitD. NOT DRIVi$ INDICAfl0NS, WITH NEW COLTS. ALL BOLTS HAD INDICA 110N$.
** HJO 1914227 1E11 f068A REPLACE VALVE WITH NEW ONE ~$URFACE. HYDRO, PRES $URI itST REPLACEMENT DUE 10 INABillif 10 PROVIDE VALVE EXACT kEPLAttMINT IN KIND (VALVE b0 LONGER MANUFACTURED) VALVE HA$ STEN
$UBJECT[D 10 HlCH VlBRAll0N AND CORRO$10N OVER THC Llit OF THE VALVI.
s
** MWO 1 91 4311 1111 F0688 RtPLACE P!P!NG AND VALVE WlTH HYDRO AND OPERATING FRES$URE VALVE HAS BitN $UBJEtit010 HICH VALVI NtW MATERI ALS. DCR1 H90126 VIBRATION AND CORROSION OVER A PERIDD OF TEAR $. EXACT IN KIND REPLACEMENT NOT AVAILABLE. VALVE AND PIPING WERE IN$iALLED UNDER AN APPROVED DCR.
- ** NWO 1 91 4472 1E11 F0039 REPLACE-STAT RING IN VALVE. CHECK FOR LEAKS AT PRESSURE SEAT RING WAS REPLACED UNDER AN APPROVID 16a GATE.. MAINTfhANCE PROCEDURE. CAU$E OF FAILURt VALVE l$ NORMAL WEAR, EXPECTED OVER A PERIOD Of 11ME.
** RWO 1 91 4713 1P41 $VH- MODIFY PLANT SERVICE WAftR $URFACE CuPPORT WAS MODIFIED PER DCR 1H 90 007 281A $UPPORT SUPPDRT PER DCR 1H00 007.
MWO 1914799 1821 MSRV MODIFY PlPE SUPPORTS TO $URfACI A/t $UPPLitD DE$1GN !N ACCORDANCE WITH O ** PIPE
' $UPPDRi$
SAilSFY ASME CODE REQUIREMENT $ A$ME SECil0N ll! hf 98
REPAIR AND REPLACtMENT filt$ UNii 1 1991 COMPOWENT DESCRIP110N It$i REMARA$
** MJO 1 91 4832 1831 41t11 DVERLAY WELDS #0VND Bf l$l A$ $t$11M ttAKAct TE$1 At $/U REPAlR$ ARE BEING MADE IN ACCDRDANCE PIPlNG REQUIRED. OVERLAYS ARE f 04 W11H NURtG D313 REV. 2 AND GENERIC l i
$1RUCTURAL INTEGRiff 0F PIPING L(iftR 68 01. DVERLAYS APE Not CODE FOUND 10 CONTAIN IG$CC. R[PAlR$ BUT PERf0RMID UNDER WRC CONCURRtNCt. CAUSE OF FAILURt(IGSCC)
** MWO 1 91 4894 1P41 F1246 REPLACE VALVES WITH CLA$$ 3 CHECK FOR Lt AK$ AT PRE $$URE VALVES ARE BEING REPLACED A$ A RE$b i of REGULAllNG VALYts. $DR 1 90 290. UPGRADING Of VALVES is ALL VALVE THAT ll BElkG DONE. NO SERVICE INDutt0 FAILURE INVOLVED
** MWO 1 91489$
1P41*f1248 RIPLACf VALVE $ WITH CLAS$ CHECK FOR ttAKAGE At FRt$$URt VALVES ARE BEING REPLAttD A$ A RCSULT OF REGULAllNG VALVt$. CURRENT VALvt$ ARE $0R-1 90 290 AND ARE 8tlNG UPGRADED Ptk VAtVE S 831.1. PLANT PROCEDURIS AND PROCUREMENT PRDGRAM. NO $tRVICE INDUCED FAILURE
-INVOLVED.
I
** MJO 1 91 4961 1E41 f008 DRILL Ntw GUIDE PIN HDLt$ 2" N/A METHDD OF kiPAIR !$ APPROVED Bf VENDOR.
VALVE AWAY TROM EXI$11NG HDLt$ GulDE PIN HOLES HAVE WORN OVER A PERIOD , PROVIDED. THE NtW HOLES ARE Of flMt. DRILLED ON SAME CENTER LINE At EXI$11NG Holt $. .
** MW3 1 91 5187 1P41 PIPlNG REPLACE THE $EVEN EXI$11NG OftRATING PRE $50RE ft$f. THE EXISTING C4]flCE PLAf t$ ARE TO THIN ORiflCES LOCAf tD IN THE 6" PSW FOR TPE INi[NDLD FUNCil0N. THE
$UPPLY LINES TO DlESCL RCPLAttMtW1$ ARE THICKER AND WILL GENERATOR $ 1(A,B,C,) WifH PERFORM THE IWlENDID FUNCTION. WORK THICKER ORiflCE PLAft$. FERFORMfD UNDER AN APPROVID DCR 1H 90- i 098
** F.C 1 91 $188 1P41 PIPikG REPLACE THE SEVEN EXISTING OrtRA11NG PRt$$URE ft$f. (VALUAtlON $HOWCD THAT THE EXISTING ORif!CE PLATES LOCAf tD IN THE ORiflCE PLATES WERE TO 1HIN FOR THEIR 6" PSW LINE THAT $UPPLIES INTENDED FUNCil0N. CHANGES WERE MADE COOLING WATER TO THE DIE $EL$ UNDER AN APPROVED DCR.
1(A,8,C,) W!ih THICKER ORiflCE PLATES. DCr 1H90 098
** MWo 1 91 5129. R/R1 iP41 PIPING REPLACE THE EXISTING 6" CARBON $URfACE, HYDRO THE EXi$11NG CARBON $1((L FLANGES ARE
$1Ett FLANGES THAT INTERFACE WELDED 10 $$ PlPE THAT COULD POTENTI ALLY WITH THE BACKWA$H N0ZZLES ON CAUSE GALVANIC CORRO$10N. REPLACING W11H THE P$W $1kAINER$ D103ASD, $$ FL ANGES WOULD ELIMINATE THl$ CONCERN. t W11N 6"$1AINLES$ $1 EEL FLANGES IN ORDER 10 ELIMINA1E i Di$$1MILAR WELDS W11H $$.
** Hwo 1 91 5189-R/R2 i 1P41 PIPING REPLACE THE EXl$11NG CARBON SURFACE AND HYDRO THE CARBON CittL TLANGES ARE WELDED 10
$ FEEL FLANGES WITH STAINLE$$ $1AINLES$ $1 EEL THAT COULD P0ftNilALLY STEEL. THE$f FLANGES INTERFACE CAU$E GALVANIC CORRO$l0N. REPLACING W11H WITH THE BACKWASH N0ZZLES ON $$ WILL EllMINATE THis CONCERN.
THE PSW STRAINER $ D103AAB. PURPO$E is GET RIO OF Dl6SIMllAR WELDS.
** MWo 1 91 5190 iP41 PlPE REPLACE THE EXI$11NG 6" $URfACE- iPC EXI$ TING C.$. FLANGES ARE WELDED 10 FLANGES THAT INTERFACE WlfH OPERA 11NG PRISSURE THE S.S.PlPING THAT COULD POTENilALLY THE BACKWA$H N0ZZLE$ ON PSW CAU$E GALVANIC CORRO$10N. ikE
$1RAINER$ 0103A&B WifH REPL ACEMENT $.$.f LANGES ARE MORE
$1AlWLES$ $f tEL FLANGES IN $UliABLE AND RELIABLE DECAU$E THET OFCER TO ELIMINATE DIS $1MILAR ELIMINATE THis CONCERN.
WELD $ WITH ThE ADJACENT-
$.S. PIPE.
l l l' 99
ktPA!R AND (tPLAttMtNT Filt$ Uht! 1 1991 COMPDNINT Dt$CRIPflDN It$f RIMARK$
~
** MJO 1 91 5233 iP41 PIPING JuMPtR CONNECilDNS ARI BllWG $URFACE AND MfDRO, kiPLACEMENT OF ERisTING PlPlWG WlfH CODE INSTALLED 10 (ACIL11 ATE OVAllfit0 P! PING AND MAI!Rj ALS l$
BfPA$$1NG $ Aft 1T RILAltD HEAT ACCEPTABLE. CAUSE OF Dt1ERIDRA110N Of EXCHANGER $ DURING CHIMICAL EKl$1]WG PlPING ll DUE TO LONG StRVICE CLE ANING OF PSW PlPING. IN RIVER WAttR (NylRONMENT.
** MJo 1 91 $3D4 if21 CS.H57 REPLAct $NUBBTR. lktTAtttD V13/4 REPLAttD $NUBBtR. CAU$t of FLUID tt AKAGE
$NUBBit $NUBBER lt LEAKING f LUID. l$ UNKNOWN AT 1Hi$ flMt.
** HJO 1 91*$327-it11+RNR* IN$1AtttD $=UBBER lt LOW Of V14 REBUILDlWG AND lbsfALLATIDW OF $ NUB 6tR$
H2$1 $NUBBER FLUID. FAlltD VISUAL ]$ PERFORMED UNDtR AN APPRDVfD $NUBBER Ik$P!Cil0N. kEPLACE $NUBBtR REPA!R AND REPLACEMINT PRDGRAM CAU$t Of VlfH WCW OR PIBUILI $NUBBIR LOW FLUID l$ UNKNOWW A1 THis 11Mt. IROM $1DCK. PROBABLE CAUSE l$ St AL WEAR.
** MJO 1 91*5329 itil RHR* REPLACE $NUDBIR. ikl1All!D V1 3/4 REPL AttD $NUBBIR. CAvst 0F flulD LEAKING H2509 $NUBBER l$ LtAKING FLUID. !$ NOT KN3WN Al THis 11Mt.
$NUBBER
** Md3 1 91 5332 ,
1P41 Pitt s0CKET WILD Fl111NG D0tt NOT HYDROSTA11C ltST. PIPE WA$ RLPtACID W11H NtW MAltRIAL AND ] HAVE FULL ENGAGlMENT. RIPLAtt PROPER (NGAGtMENT. l WitH NEW P!Pt. i i
** MWO 1 91 5335 if41 HPSI H+ REPLACE $NUBBIR Wi1H ON FRDM VT 4 $NUBBit REPLAttD. CAU$t OF FAILURE lt 85 $NUBBit $10CK (NEW OR RtBUILT). Not KkpWN At THis flMt. fAlltD VISUAL IkSFIC110N. WILL tt$1 FOR FUNCT!DNAL' OPERA 91Liff AT A LAltR Daft.
~ ,
** MJO 1+91*$337 .
i
.Itti'RHR* $NUBBER DID NOT FA$$ VISUAL VT4 REPAIR AND REPLACIMENT OF $NUBBER$ It A N192 $NUBBER ikSPICilDN. REPLACE Wi1H A NEW CONTROLLfD ACilV11V U$1NG APPRDVfD DR REBUILT $NUBBER FROM $10CK. PROCEDURit. PRORABtt CAU$t Of FLUID LEAKACE !$ SEAL WEAR. $NUBBER Dl0 NOT ,
F AIL fuhCil0NAL TE$f. (NOT AN IN$tRVICE > FAltust)
** MJo 1 91 $338 iti1*RHR* REPLACE $NUBBER. INSTALLED - VT3/4- REPLAttD $NUBBEN. CAU$t OF FLUl0 LEAKAGE H286A . $NUBBIR l$ LEAKING FLUID. l$ UNKNOWN A1 THit TIMt..
.. $NUBBIR-i ! ** MWO 1*91 53397 it11 RHR REPLAct $NUBBER. INSTAtttD vi+3/4 REPLActD $NUBDER. CAU't 0F FLUID LEAKAGE H218 $NUBBIR $NUBBER 16 ttAKlkG FlulD. l$ UN(NOWN A1 Th!$ 11!4[.
** MWO 1 91*$389 1821 70220 VALVE FAlltD LLRt. V1+2 WILL BC PERFORMED, RfPAlR$ ARE BtlNG PERFORMED UNDER AN MSIV APPROVED REPAIR PROCIDURE. REPLACEMENT PARI $ ARE PROCURED UNDtR AN APPROVED PROCUREMENT PROGRAM. CAU$t OF FAILURE l$
NORMAL WEAR OVER A PERIOD OF 11Mt.
** MJO 1 91 5420 it11*RHRt _ REPLACE $NUDBER. IN$1ALLED VT 3/4 REPLACib $NUBBER. CAU$t 0F LEAKING FlulD H2248' $NUBBtt 16 LEAKING FLUID. l$ NOT KNQUN AT THl$ 11ME.
$NUBBER
** MWO 1 91 5422 _ _
1821 RCIC* $NUBBER DID NOT PA$$ VISUAL VT4 REPAIR AND REPLACEMENT OF SNUBBER $ IS A
$$42 $NUBBER' INSPECTION, REPLACE WlIN A ktW CONTR0LitD AC11VITY USING APPROVED OR REDVILT $NUBBER FROM $1DCK. PROCCDURE$. CAUSE OF FLUID LEAKAGE l$
PROBABLY t[AL WEAR. $NUBBER PAS $tD FUNCT10NAL fi$i, (NOT-AN INSERVICE FAILURE) { 100
1 i RIPAlt AND RIPLACEMINI FILtl UNIT 1 1991 COMPONEk1_ DESCRIPil0N It$1 REMARK $
" MWO 1 91 5424 ,
1821 RCIC- $NUBBIR l$ LOW OF FLUlb, VI 4 RtPAIR AND RCPLACEMENT Of $NUCBik$ l$ A >
$$ 44 REPLACE W11H htW 04 REBUIL1 CON 1ROLLID AtilVlif U$ LNG APPROVED '
$NUBBIR $NUBBER FROM $10CK. FROCEDURES. CAUSE OF LOW FLUlD L(VEL ll koi LNOWN At 1His flMt. PA0BABLE CAU$E l$ SEAL WTAR. !
" MWO 1 91 5425 l 1821 MVVH 32 $NUBBER FAlltD YlCUAL V14 R[PA!R AND REPLACEMINT OF $NUBBIR$ 18
$NUBBlk INSPECil0N, REPLACI WifH NEW PERFORMtb UNDtk AN APPROVLD $NUBBER ,
OR REBUILI $NUBBER FROM $10CK. REPAIR AND R(PLACEMENT PROGRAM. CAU$f CF LOW FLUID LtVEL !$ UNKNOWN At THl$ 11ME. PRODABLt CAUSC l$ SEAL WEAR.
** MWO 1 91 $445 R/1 1821 F010A BUILD UP WORN AR[As CF VALVE $URFAtt,VE$$EL PRES $URt 1E$1 BUILDINf2 BASE MAf ttl AL 18 ACCEPTABLt ;
VALVE BODY IN PR[$$URE $fAL AREA AND RP. r.E1H0010 CORRECT NORMAL SERvlCE HlNGF PIN CAV!111$. VtAR.
" MWO 1 91 5454 1P41 ISH 33 REMOVE DAMAGED $1 RUT AND V13/4 $UPPORT l$ BEING REPLACED W11H (XACT IN REPLACE W11H NfW ONI. KIND REPLAttMENT UNDER APFROVED PLANT . ,
PkOCfDUPt. CAUsE OF DAMAGE APPEAR $ 10 Bt r FACES $1VI PIPE MOVEMENT.
" MWO 1915455
-iP41 SDC- . $PRlWG CAN$ AR[ 001 0F Dr$1GN V13 RE$tti!NG OF SPRING CAks is Vl1HIN THE H4&HT $PRING $[111NG. RESET $PRikG CANS 10 $ KILL OF THE CRAF1. REINSPECil0N BY l$i
-CANS D[$1GN 10LERANCE. GROUP WlLL BC PERFORMED AfifR $EfilNG.
FAILURE l$ (XPECit0 DUE 10 PIPE LOADING AND MOv(MENT.
" MWO 1 91 5456 i 1P41*$WH 19 - REPL ACE BENT ROD ON HANGtR V1 3 No NEW R00 COULD Bt FOUND $0 ExilTING MANGER ROO WA$ $1RAIGHTENED. CAU$L OF DAMAGE l$
UNKNOWN A1 THl$ ilM[.
" MWO 1 91 5457 it11 RHRH 60 RESET BEAR!kG RACE AND STAKE. VT 3 STAKING OF BEARING RAtts l$ A NORMAL MANGER REPAIR FROCES$ FOR THls TYPF F AILURE.
CAUSE OF FAILURE l$ P!PE MOVEMENT DURING OPERAfl0N. F AILURE 18 NOT UNEXPEC1ED. BEARING RACE $1AKED.
" MWO 1 91 5475
-itti RHR SM3 $NUBBER$ FAlltD VISUAL V14 $NUBBER$ WERE RfPLAtt0 UNDER AN APPROVED 8S1 INSPECfl0N. REPLACE W11H NEW $ NUB $tR INSTALLA110N AND REPAlt PROGRAM.
$NUBBER OR REBUILi $NUBBER$ FROM CAU$E OF LOW FLUID 15 UNKNOWN At THis STOCK. 11ME. PROBABLE CAUM 15 $EAL VEAR.
" MWO 1 91 5476 1!41 MS $$20 $NUBBER IS LOW OF FLUID. VT4 REPAlR AND REPLACEMENT OF $NUBBER$ 18
$NUBBER -REPLACE Wi1H NEW OR REBUILi PERFORMED UNDER A CONTROLLED AND c $NUBBER FROM $TOCK. APPROVID PROCEDURE. CAU$E OF LOW FLUID i l$ NOT KNOWN AT THis 11ME PROBABLE CAU$( ls $EAL WEAR.
" MWO 1 91 5490 1B21' REPLACE THE FOLL0dNG $NUBBER$ VT4 REPAlR AND REPLACIMENT OF $NUBB[R$ l$
SiU8BCR$ Wl1H NEW OR REBUILT $NUBBERS FERFORMED UNDER AN APPROVED $NUBBER FROM STOCKtMVVH 28,H 29, $$- REPAlR AND REPLACEMENT PROGRAM. CAUSE OF [ 15, FDH 12A, FDH 118. FAILURE l$ UNKNOWN AT THl$ i!ME, p PROBABLE CAUSE is $EAL LEAKAGE. l -" MWO 1 91 $512 (- ~1821 109- $NUBata FAILED VISUAL V14 REPAIR AND REPLACEMENT OF $NUBBER$ l$ N016 $NUBBER INSPECTION. REPLACE WITH NEW PERFORMED UNDfR AN APPROVED PROGRAM. OR REBUILT $NUBBER FROM $TOCK. CAUSE OF LOW FLUlD l$ UNKNOWN AT THl$ [ 11ME. PROBABLE CAU$E !$ SEAL WEAR. ( IOL
- - . . . ..-.s.,m , . . . - .._ . , . . ~ . - . . , - , --_ ...-,__m._, _l_......--.-m__ , --
REPAIR AND REPLAttMENT Filt$ UNIT 1 1991 COMPONINT DISCRIPfl0N ft$f REMARAS [' " MWO 1 91 5514
-1111 RHR- REPLACE $NUSDER. IN$1AlttD V1 3/4 REPLActD 5NUBDit. CAUSE OF FLUID LEAKAGE l 319A,Rht N- SNUBBER is LEAKING FLUID (R- is NOT ENOWN AT THis !!Mt.
307 SNUBB 307). ADDITION Of WASHER TO PADDLE END OF M 317 l$ NOT AN R/R CONetRN. , i
" MWO 1 91 5529 1
.it51 t001 VALVE FAlltD ttRt. REPLAct CHECK TOR LEAKAGE AT PRES $URI REPLActMINT of VALVI INitRNAts l$ A VALVE $1EM AND DilC. NORMAL MAINTENANCE ACilVITY PERIORMED i UNDER APPROVID FROCIDURis. CAU$E Of FAILUtt IS WORMAL WEAR. I
" MWO 1 91 5550 l itti RHRH- CNUBBER FAltfD VISUAL fiff. V13/4 REPA!R AND REPLACEMENT OF $NUBBER$ l$ A 23BA ENuBBER REPLACE $NUBBER Wif H ktW OR CONTROLLED ACilVITT UllNG APPROVED REBUILi $NUliBER f ROM $10CK. PROCEDURi$. PROBABLE CAUSE Of LEAKAGt il SEAL WEAR. kNUBBER pal 5ED ACTUATION l f tsi. (NOT A IN$tRVICE FAILURE)
=l
" MWO 1 91 5578 P/R1 1E11 RHRH- $NUBBER FAlltD FUNCTIONAL NA THl$ $NUBBER WAS REPLACtD WiiH A NtW ;
313 Ttst. REPLAtt WlfH A NEW UNii. UNIT. NO DAMAGE 10 ADJActWi HAkCERS WAS DETECTED. THl$ $NUBBIR HAD INitRNAL DAMAGE DUC TO A mis $1NG LOCK RING All0 WING PAR 1510 Di$A$$tMBLE. CAU$t UNKNOWN.
" Hwo 1915578 R/R2 i 1E51 RC$tH- $NUBBER FAlltD FUNC110NAL NA THl$ $NUBBER WA$ REPLACtD WITH A NEW 702 Titi. REPLACE Wl1H A NEW UNIT. UN11. NO DAMAGE WAS OtitCit0 TO ADJACENT HANCtRS. $NUBBER WA5 LOCKtD UP ACCORDING l 10 f tST STAND, BUT NO INitRNAL DAMAGE WAS St[N.tNUBBER WOULD MOVE BUT NOT FREELY.
" MWO 1 91 5603 1E11 F0158 REPLACE PLUG AND sitM AsstMatY N/A CAUst of FAltukt is Not SERVICE INDUCID.
VALVE DUE 10 DEttCTIVE $1tM. EXCE$$1VE PRESSURE PUT ON $1tM IN ATitMPT 10 STOP LE AKAGt. MAf TRIAL tt$tD 15 LXACT REPLACEMENT IN KIND.
" MWO 1-91 5655
.1P41 G001 THE WELD JOINT ON THE 1/2" OftRAllNG PRES $URE TEST. WILD WAS COMPLEf tLY REMOV[D AND
$1DE Of THE 1 1/2" RfDUCER WA$ REWELDED.
f0VND LEAKING BY VT 2 EXAMINER DURING 151 HYDRO. .
" MWO 1 91-5798 iP41 D001A 1HE 6" PSW tlNE 101R43 $001C HYDRO of EXPANSION JOINT ALIGNMENT PROCESS IS BEING PERFORMED EXPANSION WILL BE CUT AND PIPE SUPPORT UNDER APPROVED A&ME CODE PROCEDURES. ,
JOINT 1P41 SDG H703 WILL BE CUT 10 CAUSE OF MISAtlGNMENT IS UNKNOWN AT THIS ALLOW FOR ALIGNMENT OF TIME. EXPANSION JOINT,
" MWO 1 91 5799 1P41 0003A THE 6" PSW SUPPLY Likt 10 $URFACE AND HYDRO ALIGNMENT OP THE EXPAN510N JOINT is A EXPANSION 1R43 5001A Witt BE CUT AND SuliASLt HEANS Of REPAlt. ALL WORK Blik0
. JOINT PIPE SUPPORT 1P41 SDG 17D2 PERFORMID UNDER APPROVED PROCEDURES AND WILL BE CUT TO Alt 0W ALIGNMENT CODE REQUIREMENTS. CAUSE OF MISALIGkMENT Of EXPANSION J0!NT. 15 UNKNOWN At Th15 TIME. ,
" HWO 1 91 5805 1E11 6001A $UPPORT WELD HAS A SMAtt $URFACE INDICATION WAS REMOVED BY FLAPPING NO HEAT LINEAR INDICATION, REPAIR A$ WELDING OR HEAVY GRINDING WAS REQUIRED EXCHANGER NECESSARY. 10 REMOVE INDICAfl0N. APPEARS 10 RE
- j. INHERENT WELD INDICAil0N
" MWO 1 91 6110 l 1P41 F439A. PLUG NOT SEAi!NG PROPERLY IN CHECK FOR LEAKS AT PRESSURE NORMAL W[AR OF PART$ FOR THE ffPE l.
1 1/12" BODY SEAT THUS DAMAGING THE SERVICE SfEN. PARTS REPLACLD IN VALVE PLUG SEAilkG SURFACE. ACCORDANCE W11H APPROVED PROCEDURIS. NORMAL MAINTEN ANCE. 102
REPAlt AND LEPLACEMENT Fil($ UNil 1 1991 COMPONENT DisCRIPilDN ttST REMARK $
** MWG 1 91 6129 1E11 RHRN- ktAtlCN PIPE CLAMPS AND STAKE V1 3 REPAIR $ OF THl$ kATURE ARE RouilNE 407 &407A STARING RACE AND LL'BRICATE ON MA!NTEkANCE AC11Vl11t$. CAU$t 0F FAILURE SUPPOR15 H 407A Rt $1AKE BEAR!k0 RACE APIEAR$ 10 $E HIGH HUMIDl1T ENVIRONMENT DN H 407. AND PlPE MDV[ MENT DURING SY$1EN OPERAi!ON. FAILURi$ OF THi$ TYPt Akt ;
EXPIC1tD.
** MJO 1 91 6159 iP41 0137 DISAS$tM$LE/ CLEAN AND NONE VALVE WAS RtFURBISHtD. NO PRt$$URE PCV. RLFURBl$N REGULATOR A$ RET AINING PARI $ WERE U$tD DURING 1HE NECESSARY 10 INSURE Rttl Abit REFUR$15HMENT. CAU$E OF FAILURE WA$ DUE Rt$PON$t. 10 THE HAR$N ENVIRONMENT $tf N $1 THE VAlvt.
** MWO 1 91 6264 it11 RHR- PERFORM CONTROLLED GRINDlWo 10 tuR F ACE (MI) CONTROLLED GRINDING WAS PfRFORMED 10 24B+R 7 PIPE REMOVE LlWEAR INDICA 1!ON IN REMOVE INDICAfl04. NO FURTHtt REPAlt PIPE. If MIN WALL l$ VIOLAftD WORK WAS REDU!Rf D.
REPA!R.
** MWO 1 91 6265 itil PlPE REMOVE INDICAtl0N FOUND BY Mi $URFACE GROUND OUT INDICATIONS NO REWELDING WILD.20A*D 4 DURING l$1 [xAM. RtWELD IF RCDulRID. INDICAll0N WAS AN IkhtRENT NECESSART INDICA 110N IN THE PlPE.
- ** MWO 1*91 6286 REV.1 1C41 F007 kDCKWELL CHtCK VALVt WILL BE SURFACE VALVE WilL BE REPAlRfD PRIOR TO CHECK VALVE. REFAIRED 10 PA$$ LIRT PR10R 10 IN$1ALLA110N UNDER APPROVED PROCEDURE. ;
. lWSTALLAll0N.10 RtPLACE VELAN CAU$E OF FAILUkt l$ U$ AGE IN HAR$H VALVE PRE $(NTLY IN$1ALLED. ENVIRONMENT.
** MWO 1 91 6300 1P41 PlPC DURING HYDRO PIPE LEAKED Af 4" $URFACE AND HYDRO. REPLACEMENT PIPING WILL Bt OF [ XACT
..[ ') - 4" CARBON - BRANCH CONNEC110N BETWEEN 8" MAf tR! AL A$ fxi$flWG MAlf RI AL. CAUSE OF V
= '
$1tfL HE ADER AND 1P41 F059. P! PING WILL BE CUT AND A FAILURE !$ DUE 10 CORRO$lVE NATURE OF RIVER WAlfR. HANGER P41 $WH 271 WILL BE DETERMINAfl0N OF HOW MUCH REPLACED Af THis flME.
PlPING WILL NEED 10 BE REPLACED.
** MJO 1 91 6368 1631*FDH 17 REPAlR BEARINGS IN ABOVE V14 REPAlRING $NUBBER$ 15 PERFORMED UNDER AN
& $$A7 $1AftD $NUBBER$ APPROVED REPAIR AND REPLACEMENT PROGRAM.
$NUBSER$ REASON FOR BEARING SLIPPAGE l$ UNKNOWN A1 THl$ flME. PROBABLE CAU$E l$ WEAR AND
$YSTEM MOVEMENT.
** MWO 1 91 6395 1E11 8001A LINEAR INDICATION FOUND ON INSPEC1 Af OrtRATING PRES $URE THl$ TYPE REPAIR 15 IN COMPLIANCE WITH HEAT HEAT EXCHANGTR $ HELL. GROUND CODE ALLOWABLE REPAIR $. THREE EXCHANGER DUT TO APP.1/8" DEEP AND INDICAll0NS FOUND IN AREA 0F SUPPORT REWELDED. BRACKET. ALL INDICAtl0NS WERE SHALLOW AND $HORT IN LENGTH.
** MWO i 91 6406 1E51 RCSEH- REPLACE WORN $1RU1 ON 1E51+ VT3 THE TWO STRU1$ ARE OF THE SAME CAPAC11T 702 $NUBBER RCSEH 702 WlfH NEW STRUT. AND $1MILAR DESIGN AND ARE FUNC110NALLI INTERCHANGEABLE. THE WORN $1 RUT l$ OF A TYPt NO LONGER IN USE AT HATCH. WEAR WA$
DUE 10 NOAMAL OPERAi!ON.
** MWO 1 91 6468 1821 FDH 10 SUPPORT HA$ $EVERAL V13 EXACT REPLACEMENT IN KIND FDR PARTS HANG &R MAINTENANCE PRobtEMS, BENT- USED. NANGER WA$ REPAlRED IN ACCORDANCE PADDLE,t00SE PADDLE, LOOSE JAM W11H APPROVED MAINTENANCE PR3CEDURE.
NUT, FR02EN BEARING, AND CAUSE OF FAILURE l$ UNKNOWN BUT APPEARS PADDLE NOT CENTERED. THAT SUPPORT MAY NOT HAVE BEIN CENi[ RED.
. ** MWO 1 91 6476 R/R1 -
1E41 SS-42 THl$ $NUBBER HAD A DRAG VALUE N/A THIS SNUDBER WA$ REPLACED WITH AN SNUBBIR- 0F 0.7% ABOVE ACCEPTABLE, THl$ IDthilCAL 1YPE $1ZE REBUILT UNIT. THit l$ A PROCEDURAL CONSTRAINT. PROBLEM IS CAUSED BY NORMAL WEAR. J03
. ~ . - ~ - . . - _ . - . . . . - - - . _ - - - - - - - - - - - - --
-- . - - . - _ ~
l RtfAIR AND PEPLAttMENI flit $ UNif 1 1991 CDproNINT pt $CRll'110N ft$1 RthARKS
** MJO 1* 91 6476 R/82 I
1821 $$ 45 ACCUMUL ATOR 00L t$ 64 kt N/A fMIS SNUB 0tR WAS REPLACED W11H AN
$NUCBIR LOO 5tWID Aft [R WIMOVAL fr0M 10thflCAL litt AND $1ZE REBulli UN11. ,
$tRVICE THUS AlLDWING flulD to 1Hl$ WAS NOT A SERVICE INDUCED CONDillDN i L E AK OUI . AND is 1HERlf0RE NOT l' ART Of R/R.
l l ** MJO 1 91 6418 it41 H0$tH $NUCCtk NAS A DRAC VALUt Of N/A 1HE ENUSCER WA$ RttLAtt0 WilH IDINilCAL B3 SNUBBtR 1.0% ADOVE ACCtrtANCE.f His l$ $llt AND TVPt RIBUIL1 UNIT. CAULE Of A PROCCDURAL C0htlRAtht. IA! LURE 15 kDkMAL WEAR.
** MJO 1 91 6504 IC11 NANGER ADJU$1 HAkCER UN11L HANCIR VI 4 NAN 0ER ADJUSTMENT ll WlfHlN THE $ KILL Of i CLIVl$ CONT ACis Pitt LlpVitt. tnt CRAf f. CAUSE Of LDO$t CLAMP 18 UNI.NOWN A1 THl5 flMt. I'R09ABLE CAU$t 15
$fSitM MOVEMINf.
** MJO 1 91 6877 iP41 F1074 WAftt LtAKING FROM HINCE PIN CHICK TOR ltAKS Af ISESSURE PLUG WAS FABRICAf tD FROM $1DCK MAf tRI AL CHICK VALVE PtOG. FABRICAft AND INSTALL Of 1Hf SAME MAllRI AL AS DRIGINAL PLUG.
htV PLUG. 00C't MAf tRI AL. CAUS[ Of TAllVRt l$ LOkG I ttRVICE IN NAR$H RIVER WATIR [NVlPONMENT. t \ l l l I JO4 1}}