ML20056D495
| ML20056D495 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/31/1993 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20056D494 | List: |
| References | |
| NUDOCS 9308160381 | |
| Download: ML20056D495 (97) | |
Text
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TABLE OF CONTENTS
-PAGES l
I.
ASME NIS-1 FORM AND SUPPLEMEhTARY INFORMATION 1-6 l
II.
ABSTRACT 7-15 III.
EXAMINATION
SUMMARY
i A.
' CLASS 1 EXAMINATIONS 16-52 B.
CLASS 2 EXAMINATIONS 53-58' C.
PRESSURE TESTING 59-61 D.
COMPONENT SUPPORTS 62-78 E.
AUGMENTED EXAMINATIONS 79-80' 3
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REACTOR PRESSURE VESSEL INTERNALS 81-91 G.
REPAIRS AND REPLACEMENTS 92-96 i
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I NOTE:
Portions ofthis report are compiled from Southern Nuclear Operating Company. report;
" Nondestructive Examination Of. Selected Class-1, 2,
and.3 Components", issued for the Spring-1993-Refueling Outage at E.I.-Hatch Nuclear Plant, Unit 1.
This. report is available for review in the Records Management Department'at.the plant site.
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LIST OF ABBREVIATIONS ANI/ANII Authorized Nuclear Inspector / Authorized Nuclear Inservice Inspector
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ASME American Society of Mechanical Engineers 1()
ASNT American Society for Nondestructive Testing BC Branch Connection BWR Boiling Water Reactor CH Closure Head I
CONT Containment CPI Containment Purge and Inerting CRD Control Rod Drive CS Core Spray CU Clean-up j
C&L Cramer and Lindell i
DCR Design Change Request
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ECCS Emergency Core Cooling Systems 1
ET Eddy Current. Examination EPRI Electric Power Research Institute FB Flange Bolting FPC Fuel Pool Cooling i
FW Feedwater GE General Electric GPC Georgia Power Company HL Hanger Lug HPCI High Pressure Coolant Injection INF Indication Notification Form IGSCC Intergranular Stress Corrosion Cracking i
ISI Inservice Inspection LD Longitudinal Seam Weld Extending Downstream l
w LD-I Longitudinal Weld Downstream on Inside of Elbow' LD-O Longitudinal Weld Downstream on Outside of Elbow Lo Zero Reference Location LMT Lambert, MacGill, Thomas, Inc.
LPCI Low Pressure Coolant Injection I
1 LU Longitudinal Seam Weld Extending Upstream:
LU-I Longitudinal Weld Upstream on Inside of Elbow LU-O Longitudinal Weld Upstream on Outside of Elbow l
MSIV Main Steam Isolation Valve MS Main Steam MSA Main Steam Auxiliary MT Magnetic Particle Examination MWe Megawatt Electric MWO Maintenance Work Order MWt Megawatt Thermal NDE Nondestructive Examination NI No Indication NRC Nuclear Regulatory Commission NRI No Recordable Indication OL Overlay-6 l
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Abbreviations - cont.
PL Pipe Lug PLT Plant I
PR Pipe Restraint
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PROD Product i
PS Pipe-Support PSW Plant Service Water PT Liquid. Penetrant Examination QC Quality Control RC Reactor Recirculation RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal RHRSW Residual Heat Removal Service Water RI Recordable Indication RINTSA Recirculation Inlet Nozzle Thermal Sleeve Attachment t
RL Refracted Longitudinal RL Restraint Lug RPV Reactor Pressure Vessel u
RX Reactor RWCU Reactor Water Cleanup SBLC Standby Liquid Control SIAI Structural Integrity Associates, Inc.
7 SER Service l
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SNC Southern Nuclear Operating Company
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TDP Torus Drainage and Purification TSB Turbine Steam Bypass UT Ultrasonic Examination VLV Valve i
VT Visual Examination O
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This. list is comprised of standard abbreviations used in Inservice Inspection Documentation.
All of these abbreviations may not appear in this report.
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. TOTAL NUMBER OF SHEZTS 96 FORM NIS-1 FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS
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As Required By the Provisions Of The ASME Codes Rules l
1.
Owner: Georaia Power Company. 333 Piedmont Ave.. NE.
P.O.
Box 4545.
- Atlanta, Georgia 30302 2.
Plant: Edwin I. Hatch Nuclear Plant. Route 1.
Box 278. Baxlev. GA 31513 3.
Plant Unit 1_ 4.
Owner Certificate of Authorization (if req.) N/A 5.
Commercial Service Date 12/31/75
- 6. National Board No. for Unit HZA 7.
Components Inspected:
Component or Manufacturer State or Appurtenance Manufacturer or Installer Province National or Svstem or Installer Serial No.
Number Board No.
l Rx. Pressure Vessel Combustion Ena.
67105 N/A 20769 Rx. Pressure Vessel Combustion Ena.
67205 N/A 20769 l
1B21 Main Steam Pullman Power Prod.
N/A N/A l
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IB21 Feedwater Pullman Power Prod.
F/A N/A l
IC41 SBLC Pullman Power Prod.
N/A N/A 1E11 RHR Pullman Power Prod.
N/A N/A 1E41 HPCI Pullman Power Prod.
N/A N/A IG41 FPC & CU Pullman Power Prod.
N/A N/A IN11 MS Auxiliary Pullman Power Prod.
N/A N/A 1P41 Plt Ser Water Pullman Power Prod.
N/A N/A 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 form.
Spool piece or fittir.g 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.
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FORM NIS-1 (Back) 8.. Examination Dates 11/29/91 to 05/14/93.
9.
Inspection Interval from 01/86 to 01/96.
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- 10. Abstract of Examinations.
Include a list of examinations and a l
statement concerning status of work required for current interval.
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- 11. Abstract of Conditions Noted. ***
- 12. Abstract of Corrective Measures Recommended and Taken. ***
i We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
i Date dD 19 D Signed Georaia Power Comoany By k
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Owner i
Certificate of Authorization No.(if applicable) N/A Expiration Date N/A
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CERTIFICATE OF INSERVICE INSPECTION I,
the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of GA and employed by ****- of Hartford, CT.have l
inspected the components described in this owners' Data Report i
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during the period 11/91 to 05/93 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.
i 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 l
Report.
Furthermore, neither-the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
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Date 19 Commissions Georaia-GA00115 i
Inspector s Signature National-Board, State, Province,& No.
The following NIS-1 Form supplementary information and report includes the responses to NIS questions #10, #11, and #12.
- Hartford Steam Boiler Inspection and Insurance Company.
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NIS-1 Form Supplementary Information l :-
Owner's Data Report for
.().
Inservice Inspection l.
l Date: July 12, 1993 Owner Name & Address:
Georgia Power Company 333 Piedmont Avenue, N.E.
P.O.
Box 4545 Atlanta, Georgia 30302 Name & Address of Nuclear Generatina Plant:
Edwin I. Hatch Nuclear Plant l
Route 1, Box 278 l
Baxley, Georgia 31513 1.
Name Assioned to Nuclear Plant Station:
Edwin I. Hatch Nuclear Plant Unit 1 Commercial Service Date: December 31, 1975 Gross Generatina CaDability:
2436 MWt, 813 MWe State. Province, or Municipality Assioned Number:
.N/A l
National Board Number Assioned by Manufacturer:
N/A l
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r System Pressure /Leakace Tests System Class Test Reauired f
Reactor Pressure Vessel and 1
1 Leakage Associated Class 1 Piping and
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Components t
HPCI (1E41) 2 1 Hydrostatic HPCI (1E41) 2 1 Hydrostatic *-
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- Pressure Test performed per ASME Section XI Code Case N-498 l
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f Pipe Support & Hancer Examination
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Class 1 Core Spray System Main Steam System Residual Heat Removal System Feedwater System e
Reactor Recirculation System Reactor Water Cleanup System
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High Pressure Coolant Injection System Reactor Core Isolation Cooling System i
Class 2 High Pressure Coolant Injection System Residual Heat Removal System O
Reactor Core Isolation Cooling System Main Steam Auxiliary System Control Rod Drive System i
Core Spray System Main Steam System r
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Name & Address of Manufacturer'of Components-1.
-Reactor Pressure Vessel and Closure Head:
Combustion Engineering, Inc.
Chattanooga, TN 2.
Piping (Classes 1, 2, and 3) a.
Pullman Power Products Division of Pullman-Kellogg i
Williamsport, PA
- b. Generak Electric Company San Josa, CA i
Note:
Piping purchased by General Electric and Pullman and installed by Pullman.
Material certifications and manufacturer information are 1
available for review in the Records Management Department at the Hatch Plant Site.
3.
Piping Supports and Hangers (Classes 1, 2, and 3) a.
Bergen-Paterson Pipe Support Corporation I
Laconia, NH
- b. ITT Grinnell Corporation i
Providence, Rhode Island f
c.
Pacific Scientific Anaheim, CA i
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Liesega USA l
Laconia, NH 4.
Valves, Pumps, and Heat Exchangers a.
Crane i
New York, NY l
- b. Wm. Powell Company Cincinnati, OH q
- c. General Electric i
San Jose, CA i
- d. Target Rock Corporation East Farmingdale, NY n
l Date of Inservice Inspection:
March 1993 - May 1993 I
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Comolhtion Date of' Inservice Inspection:
May 14, 1993 i
l Name of Insocctor:
Donald R. Laakso (ANI/ANII)
Name & Mailina Address of Inspector's Employer:
The Hartford Steam Boiler Inspection and Insurance Company.
200 Ashford Center - North Suite 300 Atlanta,-Georgia 30338 e
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r ABSTRACT l
l An_ Inservice Inspection of selected Class 1, 2
and 3 components at i
Georgia Power Company's Edwin I. Hatch Nuclear Plant Unit 1 was performed g-) during the Spring 1993 Maintenance / Refueling Outage.
The components were
( examined in accordance with the applicable ISI Outage Plan, including any
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changes made during the outage as approved by GPC.
Edwin I. Hatch Unit 1 is currently in the third period of the second 10-Year Inspection Interval. The required examinations are presently on schedule as specified in the Second Ten-Year Inspection Plan.
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The nondestructive examinations were performed using VT, PT, MT and UT l
examination techniques.
SNC personnel and their contractor GE, performed NDE of the selected welds and components. In addition, GE personnel i
I performed the VT examination of selected RPV internal components.
'SNC, GE, or GPC NDE procedures were utilized for all ASME Section XI examinations.
GE personnel were qualified to the applicable SNC procedures. EPRI qualified inspectors were utilized for all examinations involving IGSCC susceptible materials.
GE procedures were used for mechanized ultrasonic examination and exams were performed by GE j
inspectors.
In addition to NDE testing of Class 1 and 2 welds and components, pressure testing, visual examination of Class 1 component internal surfaces and visual examination of pipe supports and hangers were also performed.
Third party review (e.g. an ANII) was utilized for all examinations of j
ASME Section XI components.
I Selected components were examined in accordance with GPC commitments to i
the following documents:
Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of j
Nuclear Power Plant Components," 1980 Edition with Addenda through Winter 1981.
1 United States Nuclear Regulatory Commission, Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping" which l
invokes much of NUREG 0313, Revision 2,
" Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary.
Piping.
I United States Nuclear Regulatory Commission, Generic Letter 81-11, which modifies and invokes 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 has,been closed out via-NUREG/CR-4523.
The required bulletin actions have been performed satisfactorily and will be continued during every refueling outage, j
4 SNC " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant,-
Unit 1 1993 Spring Refueling Outage."
SNC "Second Ten-Year Examination Plan, Edwin I. Hatch Nuclear' Plant
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Unite 1."
- United States Nuclear Regulatory Commission NUREG 0803, " Generic Safety Evaluation Report Regarding Integrity of BWR SCRAM System"
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Representativo samples of.the following systems, comprised of salected l
Class 1, 2,
and 3 components, were examined.using various NDE techniques, in accordance:with the above documents:
Class 1 fss
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Reactor Pressure Vessel (1B11).
Main Steam. System (1B21)
L Feedwater System (1B21) i L
Reactor Recirculation System (1B31)
Control Rod Drive System (1C11)
Standby Liquid Control System (1C41)
Residual Heat Removal System (1E11)
L Core Spray System (1E21) l High Pressure Coolant Injection System (1E41)
Reactor Core Isolation Cooling System (1E51)
Reactor Water Cleanup System (IG31)
Class 2 Standby Liquid Control System (1C41)
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 (1E51) l Main Steam Auxiliary System (IN11) 1 i
Other - Augmented (Non ASME Section XI) i UT thickness measurements were performed on selected components in-the Extraction Steam and Condensate Feedwater. Piping Systems.
'A portion of' O_these components were selected due to_ their similarity in design 'and operating conditions to components involved with the'"Surry pipe break i
' incident".
Seven (7) 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 i
performed due to commitments to GL 88-01.
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CLASS 1 EXAMINATIONS NUREG 0313
()GPCiscommittedtotheperformanceofsurfaceandvolumetricexaminations 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 end.
Cateaory A Fifty-four (54) Category A welds were examined.
Fifty-three (53) of these welds were examined using UT and PT techniques and the remaining one (1) was examined using PT techniques only. No indications were found that i
exceeded Code allowable limits.
Cateaory C Twenty (20) Category C welds were examined using UT and PT techniques and-the remaining fourteen (14) welds were examined using UT techniques only.
No indications were found that exceeded Code allowable limits.
Catecorv D l
Eleven (11) Category D welds were examined using UT and PT techniques.
l No indications were found that exceeded Code-allowable limits.
Five (5) RINTSA welds were examined by UT and no indications were found that exceeded Code allowable limits.
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Cateaory E Twenty-six (26) Category E (overlayed) welds were examined by UT NDE techniques. UT examinations revealed interbead lack of fusion indications that had not been previously recorded in five of the twenty-six overlays examined. All results-for new indications were evaluated by Structural Integrity Associates, Inc. and found to be-acceptable for continued I
service.
Mechanical Stress, Improvement Process (MSIP)
Eleven (11) Category D welds in Nozzle to safe-end assemblies and eighteen (18)' Category A welds in RWCU system piping were~ treated with MSIP. PT and automated UT techniques were applied before and after application of MSIP-on the 11 nozzle to safe-end welds. These 11 Category D welds are now-considered to be Category C welds and will be examined as such in-the future. PT and manual UT techniques were applied after application of MSIP on the 18 RWCU system welds, and will be examined according to the-inspection schedule for Category A welds in future outages.
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t Other Class 1 Examinations Eighty.(80) ASME Section XI component examinations were performed utilizing l
UT, MT, PT and VT as applicable.
These examinations included; RPV welds, and valve bolting materials.
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()pipingwelds,valveinternals, 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 RPV internal components.
See the Invessel Inspection section of this report for more detailed information.
Nine (9) Class 1 valves were disassembled for maintenance / inspection during the outage.
The internals of these valves were VT inspected by GPC QC and SNC personnel.
One of the valves exhibited unacceptable conditions relevant to the visual examination and was repaired and
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reinspected satisfactorily.
i Twenty (20) CRD's were replaced during the outage which facilitated visual
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examination (VT-1) of the bolts, studs, and nuts.
Per SIL 433, all Shroud Head Bolts were examined. Indications of cracking were recorded in seven of these bolts.
All seven indications were evaluated by General Electric and found to be acceptable for continued service.
Class II Examinations s
O Twenty-six (26) welds were examined using surface and/or volumetric NDE techniques as applicable.
Two (2) of these welds were examined per NUREG i
0619 (UT only), three (3) examinations were for the GPC augmented
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examination commitments (MT only), one (1) examination'was for NUREG-0803 (MT only) and the remaining twenty (20) examinations were per ASME Section
-XI requirements.
l An unacceptable linear indication was found in one (1) weld and was repaired by controlled grinding.
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r Pressure Testina i
Two (2) Class 2 hydrostatic tests and one (1) Class 1 system leakage test
.were all performed satisfactorily. Pressure Test Section of this Report sprovides specific test identification and details.
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Auamented Examinations
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Seven (7) welds in the non-safety portion of-the RWCU System were examined-by UT per a GPC commitment to the NRC for NUREG 0313 Rev. 2 augmented requirements.
No reportable indications were detected.
Pipe Support Examinations (Class 1 and 21 l
r Thirty-seven (37) pipe supports were VT examined per the requirements of ASME Section XI during the outage.
No unacceptable indications were reported.
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Eauipment Support Examinations (Class 1 and 2)
Ten (10) equipment supports were VT examined per the requirements of'ASME-Section XI during the outage.
No unacceptable indications were reported.
Snubber Examinations (Class 1 and 2)
I Two hundred thirty-eight (238) snubbers were VT examined per GPC QC procedures.
All of the snubbers were determined to be acceptable.
Repairs and Replacements (Class 1 and 2)
_ (g Numerous repair / replacement activities were performed prior to and during V the outage.
An-itemized list of the repair / replacement activities is i
included in the Repair / Replacement Section'of-this report.
Reportable Indications Following is an itemized list of ='l welds and' components which were reported with indications or we
.onsidered unacceptable.
All of these
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items were either repaired and/t evaluated and then determined to be j
acceptable.
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cummary of Indio2tiena a
Identification Indication Corrective Action I
Support Improper spring can Reset spring can
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1E11-RHRH-109 setting MWO 1-93-1385 Support Improper spring can Acceptable as is per 1P41-ISH-75 setting SCS engineering guidelines Valve Bolting Loose nuts Tightened nuts 1B21-F013H MWO 1-93-2197 Weld 0.8" linear Indication removed 1E11-2RHR-20A-PD-C-4 indication MWO 1-93-1537 Shroud Head Bolts Crack indications Acceptable for
- 15, #17, #19, #22, continued operation
- 30, #32, and #34 per GE Component Erosion / Corrosion Acceptable for 1-CF-39 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-CF-37 point below continued operation required level per SNC
("/ 1-1R5-2) Component Erosion / Corrosion Acceptable for s.
point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-5HD-1 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-2R5-6 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-5HD-3 point below continued operation required level per SNC i
' Weld
.374" interbead.
Acceptable for 1E11-1RHR-20B-D-3 lack of fusion continued operation I
indication per SIAI Component Erosion / Corrosion Repaired 1-8E-9 point below
- MWO 1-93-2113 required level
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Id ntification Indicatien Carr:ctivo Action Component Erosion / Corrosion Acceptable for point below continued operation 1,);1-5HD-2 required level per SNC Component Erosion / Corrosion Acceptable for 1-12E-5 point below continued operation required level per SNC Component Erosion / Corrosion
. Acceptable for 1-8E-8 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-2R5-4 point below continued operation required level per SNC Component Erosion / Corrosion Replaced 1-10E-16 point below
- MWO 1-93-5003 required level
- MWO 1-93-2112 Weld UT indication Acceptable for N3D (N-SH) continued operation per GE Weld overlay Interbead lack of Acceptable for 1B31-1RC-28B-4 fusion indications continued operation per SIAI-
.29" interbead lack Acceptable for 1B31-1RC-12AR-K-2 of fusion indication continued operation per SIAI Steam Dryer 6 crack-like Acceptable for Vertical Vane indications continued operation Bank Welds per:GE K-11 Weld Overlay Interbead lack of Acceptable for 1B31-1RC-12BR-D-2 fusion indication continued operation J
per SIAI Component Erosion / Corrosion
. Repaired 1-10E-23 point below
- MWO 1-93-2112 required level Component Erosion / Corrosion Repaired a
1-8E-9S point below
- MWO 1-93-2113 1
required level
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IC:ntificatien Indiention Carrcctivo Acticn R
' Component Erosion / Corrosion Acceptable for 1
1-10E-2 point below continued operation js required level per SNC 1
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i Component Erosion / Corrosion Repaired 1-10E-17 point below
- MWO 1-93-2112 required level Component Erosion / Corrosion Acceptable for i
1-8E-10 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-10E-22 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for~
1-10E-13 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-M2R-2 point below continued operation required level per SNC Component Erosion / Corrosion Acceptable for 1-8E-11 point below continued operation required level per SNC i
r] Component Erosion / Corrosion Acceptable for
(> 1-10E-1 point below' continued operation-
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required level per SNC Component Erosion / Corrosion Acceptable for 1-5HD-2A point below continued operation required level per SNC i
- These MWOs did not require initial / final ANII review.
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,-g The following sections contain a summary of.the NDE Examinations performed,
'X j provide additional information and provide the results of those examinations.
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SUMMARY
or
'O CLASS'1 EXAMINATIONS O
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' Visual' Examination-of Class 1 CRD Bolting ASME Section XI requires examination of.the CRD components (bolts, studs j-and nuts) whenever the housings are disassembled.
Twenty (20) CRDs were l
" A replaced during the. outage which facilitated visual examination (VT-1) of the bolts, studs and nuts.
The subject examinations were performed by.
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GPC QC personnel in conjunction with the CRD maintenance / replacement L
- activities.
Listed below.are the CRDs which were examined.
All of these' 1
CRDs were replaced per MWO 1-92-6959.
l 50-19 38-07 34-03 30-11 18-15 06 02-27 14-47 10-31 26-43 l
42-23 26-19 l
22-07 10-15 1
30-47 38-23 34-19 14-07 10-07 30-31 l
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O E.I. NATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS
'ASME.
EXAMINATION / AREA PROCEDURE BLOCK SWEET NO.
RESULTS REMARKS RPV EXAMINAil0NS B1.22 A-1A/02 BMT-E UT-H-410/05
.119-H S93H1U328 NRI B-A
-BOTTOM HEAD TORUS MERIDIONAL 593H1C161 UT CAL ASME WELD S93H1U329 NRI
-593H1C162 UT CAL S93H1U330 NRI
.S93H1C163 UT CAL B3.10 A-1A/02 C-6 (270-0)
MT-H-500/05 61-H
$93H1M043 NRI EXAMINED FROM OD ONLY. UT TO BH
' SUPPORT SKIRT-N2H (270 DEGREE)
UT-H 410/05 593H10265 NRI THE EXTENT POS$1BLE.
ASME-TO N1A (O DEGREE) C. W.
S93H1C234 UT CAL SEE RELIEF REQUEST 2.1.5.
81.40 A-2/03 HC 2 (34-1)
MT-H-500/05 64-H S93HiM045 NRI B-A '
CLOSURE HEAD-TO-FLG CENTERLINE UT-H-410/05 S93H1U271 NRI ASME
.' STUD 34 TO STUD 1 (CU).
S93H1C239 UT CAL 593H1U278 NRI
$93H1C246 UT CAL 593H1U279 NRI S93H1C247 UT CAL B3. 90 -
A-1/04'
-N2C (N-SH)
UT H-410/05 61-H 593H1U295 NRI ONE-SIDED EXAM DUE TO NO22LE.
B-D
'B LOOP RECIRCULATION INLET N0ZZ S93H1C258 UT CAL LIMITED EXAM DUE 10 INSULATION' ASME TO SHELL S93H10293 NRI RING. 74% COVERAGE.
-NRI 593H1C254 UT CAL B3. 90 A-1/04 N2F (N-SH)-
UT H-410/05 61-H
$93H1U296 NRI ONE SIDED EXAM DUE TO N0ZZLE.
BD A LOOP RECIRCULATION INLET N0ZZ S93H1C259
- UT CAL LIMITED EXAM DUE TO INSULATION ASME TO SHELL
.$93H1U294-NRI RING. 74% COVERAGE.
$93H10290 NRI S93H1C253 UT CAL N2F (RINTSA)
OT-H-415/05 125 H
'S93H1U207-RI GEOMETRY RINTSA WELD
NUREG-03130 181
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E.I. MATCH UNIT.1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME EXAM EXAMINATION CAL EXAM / CAL SECTION XI FIGURE No.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RPV EXAMINATIONS 6
N2G (RINTSA)
UT-H-415/05 125-H 593H1U206 RI GEOMETRT RINTSA WELD
$93HlC129 UT CAL NUREG-0313D N2H (RINISA)
UT-H 415/05 125 H 593H1U208 NRI RINTSA WELD
$93H1C131 UT CAL NUREG 0313D B3. 90 A-1/04 N2J (N SH.i UT-H 410/05 61-H
$93H1U297 NRI ONE-SIDED EXAM DUE TO NO22LE.
B-D A LOOP RECIRCULATION INLET NO22 593H1C260 UT CAL LIMITED EXAM DUE 10 INSULATION ASME TO SHELL
$93H1U292 NRI RING. 74% COVERAGE.
S93H1C255 UT CAL 593H1U289 R1 GEOMETRY
+-
N2J (RINTSA)
UT-H-415/05 125-H
$93H10209 RI GEOMETRY RINTSA WELD S93H1C132 UT CAL NUREG 03130 N2K (RINTSA)
UT-H-415/05 125-H 593H1U210 RI GECHETRY RINTSA WELD
$93H1C133 UT CAL NUREG 03130 B3.100 A-1/04 N3C (!R)
GE-UT-401/3 61-M 35 NRI B-D C LOOP MAIN STEAM PB2-IR 33 UT CAL ASME 36 NRI 37 UT CAL 40 NRI 38 UT CAL J
B3. 90 A-1/04 N3C (N-SM).
GE-UT 400/0 62 H 38 NRI EXAM LIMITED TO ONE SIDE DUE B-D C LOOP MAIN STEAM 34 UT CAL TO N0ZZLE GEOMETRY.
ASME 37 NRI 25.8% COVERAGE
39 NRI 36 UT CAL-19
_ _. ~ _.
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~ [
m CLASS 1 COMPONENTS ASME EXAM EXAMINATION CAL EXAM / CAL SECTION XI F10VRE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RpV EXAMINATIONS i
n.
83.100 A-1/04 N30 (tR)
GE-UT-401/3
.61 M 34 NRI B-D D LOOP MAIN STEAM OUTLET N0ZZLE PB2 IR 33 UT CAL ASME IR 33 NRI 32 UT CAL B3. 90 A*1/04 N30 (N-SH)
GE-UT-400/0 62-H 30 RI ALLOWABLE LAM.
LIMITED EXAM DUE TO N0ZZLE
~ ~ ~ ~
8-D
- D LOOP MAIN STEAM CUTLET SHELL GE-UT-300/2 30 UT CAL GEOMETRT (ONE-SIDED EXAM).
.TO N0ZZ 31 NRI 73.6% COVERAGE.
32 NRI SEE INF 193M1008.
29 RI PLANAR FLAW
'UT CAL 2010 RI RELOOK 1008 UT CAL 1009 UT CAL
-2011 Rt RELOOK 1010 UT CAL A-1/04' N4A (CYL BORE)
NI
+-
STRAIGHT CYLINDRICAL' BORE GE-UT-303/1 NIR 11 UT CAL NUREG-0619 SECTION 6
NI 12 '
GE-UT 402/0
_.61-H 10' NRI ZONE 1 & 2A COVERAGE LIMI?ED a
BD
'A-A LOOP FEEDWATER INLET N0ZZLE GE-UT-303/1 CTS 2007 NRI-DUE TO PROXIMITY OF N0ZZLE
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1006 UT CAL-
-96.4% COVFRAGE
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CLASS-1 COMPONENTS ASME EXAM EXAMINATION CAL EXAM / CAL SEttIDM XI-FIGUDE No.
' EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
pcSULTS REMARKS RPV EXAMINATIONS B3.90 A*1/04
-N4A (N SH)
GE UT-400/0 62-H 12 NRI ONE-SIDED EXAM DUE TO N0ZZLE BD GE-UT-300/2 17 UT CAL GEOMETRY AND DUE TO PROXIMITY
'ASME.
11 NRI 0F N0ZZLE N11A.
15 UT CAL 46.6% COVERAGE 13 NR!
16 UT CAL 2001 NRI 1003 UT CAL 1001 UT CAL
'1002 UT CAL A-1/04 N48 (CTL BORE)
GE-UT-402/0 61 H 7
NRI LIMITED EKAM DUE TO
. STRAIGHT CTLikDRICAL BORE GE-UT-303/1 NIR 12 UT CAL THERMOCOUPLES.
NUREG 0619 SECTION
.8 NR' 84.9% COVERAGE 11 UT CAL i
B.t.100 A 1/04 N4B (IR)
GE UT-402/0 61 H 22 NRI GERIS IR EXAM LIMITED DUE TO B-4 A-B LOOP FEEDWATER INLET N0ZZLE 'GE-UT-303/1 CTB 23 UT. CAL PROXIMITT OF N022LE N9.
MURCG-0619 IR 23 NRI 100% COVERAGE 24 UT CAL 2005 NRI L-1004.
UT CAL 1005 UT CAL 2008 NR1 1006 UT CAL 1007 UT CAL f
93.90 A-1/04
'N48 (N-SH)'
GE-UT-400/0 62-H 15 NRI EXAM LIMITED TO ONE SIDE DUE B-D GE-UT-300/2 18 UT CAL TO N0ZZLE GEOMETRY AND ASME 16 NRI PROXIMITY OF N0ZZLE N9.
UT CAL 14 NRI 16 UT CAL 2002 NRI 1003 UT CAL 1001 UT. CAL 1002-UT CAL t
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. ASME.
EXAM.
-SECTION XI' ; FIGURE NO.
EXAMINATION / AREA FROCEDURE BLOCK SHEET NO.
RESULTS PEMARKS RAV EXAMINATIONS A 1/04
'N4C (CYL BORE)
GE-UT-402/0 61-H 2
NRI STRAIGHT CYLINDRICAL BORE GE-UT-303/1 NIR 12 UT CAL NUREG 0619-SECTION-1 NRI 11 UT CAL 2006 NRI 1006.
UT CAL 2009 NRI 1007 UT CAL B3.100 A-1/04 N4C (IR)
GE-UT 402/0
'61-M 20 NRI LIMITED EXAM DUE TO PROXIMITY-B-D.
B-C LOOP FEEDWATER INLET N0ZZLE GE-UT-303/1 CTB 23 UT CAL OF N0ZZLE N11B.
NUREG 0619 IR 21 NRI 96.4% COVERAGE 24 UT CAL 2006 NRI 1004 UT CAL 1005 UT CAL 2009 NRI 1006 UT CAL 1007 UT CAL
'B3. 90 A-1/04
'N4C (N-SH)
GE-UT-400/0 62-H 18 NRI EXAM LIMITED TO ONE SIDE DUE B-D B-C LOOP FEEDWATER INLET N0ZZ TO GE-UT*300/2 18 UT CAL TO N0ZZLE GEOMETRT AND DUE TO ASNE SHELL 17 NRI PROXIMITY OF N0ZZLE N11B.
NRI 20 -
- NRI 1003 UT CAL 1001 UT. CAL 1002 UT. CAL
. A 1/04 N40 (CYL BORE)
GE-UT-402/0 61-M
~ 3
. NRI.
LIMITED EXAM DUE To STRAIGHT CTLINDRICAL BORE NIR-1 12 UT CAL THERMOCCUPLES.
-+
NUIEG-0619 SECT 104
' 4 NRI 84.9% COVERAGE-
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EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RPV EXAMINATIONS B3.100 A-1/04
'N40 (IR)
GE-UT-402/0 61-H 24 NRI
- B-D
' B-D LOOP FEEDWATER INLET N02ZLE CTB 25 UT CAL NUREG-0619
'L B3. 90 A 1/04 N4D (N SH)
GE-UT-400/0.
62-H 26 NRI EXAM LIMITED TO ONE SIDE DUE B-D '
B D LOOP FEEDWATER INLET N0ZZ TO 27 UT CAL TO N0ZZLE GEOMETRT.
ASTiE
'SHELL INLET N0ZZLE D 27 NRI 34.9% COVERACE 28 UT CAL 28 NRI 29 UT CAL B3.90 A-2/03 NT UT-H-410/05 64 H
$93H1U272 NRI ONE-SIDED EXAM DUE TO N0ZZLE.
B-D MAIN STEAM VENT N0ZZLE 593H1C240 UT CAL 75% COVERAGE.
ASME 593H1U280 NRI S93H1C248 UT CAL 593H1U281 NRI S93H1C249 UT CAL B3.100 A 2/03 N7 (IR)
UT-H 480/04 64 H.
593H1U269 NRI B-D MAIN STEAM VENT N0ZZLE 1R 593H'< C238 -
UT CAL ASTE B3.100 A-1/04 NBA (IR)
UT-H-480/04 61-H s93H10239 NRI BD A LOOP JET PUMP 593H1C219 UT CAL ASME 23.90 A-1/04
- NBA (N-SM)
' UT H 410/05 61-H 593H1U236 NRI-NO EXAM UPSTREAM DUE TO N0ZZLE B-D A LOOP JET PUMP 593H1C216 UT CAL' CONFIGURATION. 76.5% COVERAGE.
$93H1U237 NRI
$93H1C217 UT CAL 593H10238 NRI 293H1C218 UT CAL 23 r;
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O E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME' EXAM EXAMINATION
' CAL EXAM / CAL SECTION X.1 FIGURE No.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RPV EyAMINATIONS B3.100-A-1/04 NSB (IR)
UT-H-480/04 61 H 593H1U258 NRI B-D B LOOP JET PUMP INSTRUMENT 593H1C231 UT CAL AS;;E N0ZZLE IR-B3. 90 A 1/04 NBS (N-SH)
.UT-H-410/05 61-H 593H1U255 NRI NO EXAM UPSTREAM DUE TO NO22LE BD B LOOP JET PUMP INSTRUMENT
$93H1C228 UT CAL CONFIGURATION. 76.5% COVERAGE.
ASME N0ZZLE TO SHELL 593H1U256 NRI S93H1C229 UT CAL 593H1U257 NRI S93H1C230 UT CAL B4.13
.A-1A/02
'N10 (N-SH).,
VT-H-720/03
$93H1V205 SAf BE RPV INSTRUMENTATION N0ZZLE TO ASME SHELL B5.10 A-2A/02 NUT 25
'MT N 501/04 593H1M040 NRI B-G-1.
CLOSURE HEAD NUT ASME B6.10 A-2A/02 NUT 26 HT-H-501/04 593H1M040 NRI B G-1.
. CLOSURE HEAD NOT ASME B6.10 A-2A/02-NUT-27 MT-H-501/04 593H1M040 NRI B-G-1 CLOSURE HEAD NUT
-ASME B6.10
'A 2A/02 NOT-28'
.MT-H-501/04 593H1M040
' NRI B G-1 CLOSURt HEAD NUT.
~ASME B6.10 A 2A/02 NUT 29 MT-H-501/04 593H1M040 NRI BG1
'. CLOSURE HEAD NUT ASME
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- CLASS 1 COMPONENTS
'ASME-EXAM EXAMINATION CAL EXAM / CAL SECTION Xi FIGURE NO.
EXAMINAit0N/ AREA -
PROCEDURE BLOCK SMEET NO.
RESULTS REMARKS RPV EVAMINATIONS B6.10 A-2A/02 NUT-30' Mi-H-501/04 593H1M040 NRI
.B-G 1 CLOSURE HEAD NUT' ASME' B-G-1 CLOSURE HEAD. WASHER,
VT-H-710/03 593H1v083 SAT B5.50 A-2A/02 WASHER 25 ASME B6.50 A-2A/02 WASHER-26 VT-H-710/03 593H1vo83 SAT B-G 1 CLOSURE HEAD WASHER ASME B6.50-A-2A/02 WASHER-27 vi-H-710/03 593H1v083 SAT 8 G-1 CLOSURE HEAD WASHER
-AS"E B6.50:
A-2A/02 VASHER-28 VT-H-710/03
$93H1V083 SAT B-G-1 CLOSURE HEAD WASHER AS"E
'B-G-1
' WASHER'29 VT-H-710/03 593H1v083 SAT 86.50 A-2A/02-CLOSURE HEAD WASHER' ASME B-G-1
. WASHER-30 VT-H-710/03 S93H1V083
. SAT B6.50
'A-2A/02 CLOSURE HEAD WASHER ASME
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EXAM]NAT[ON/ADEA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RPV EXAMINATIONS B15.10 CLASS 1 (PT)
VT-H-720/03 593H1v211 SAT
.B-P PRESSURE RETAINING BOUNDART
$93H1V212 SAT ASME LEAKAGE TEST 593H1V213 SAT 593H1v214 SAT
-$93H1V215 SAT
$93H1v216 SAT
$93H1V217-SAT
$93H1V218 SAT
$93H1V219 SAT 593H1V220 SAT 593H1V221 SAT 593H1V222 SAT B7.60 FLANGE BOLTING GPC B-G-2 CRD HOUSING ASE B6.50 A-3/02 LOCATION-1 THRU 20' UT-H-460/02 30-H
$93H10285 SAT THICKNESS B-G-1 THICKNESS MEASUREMENTS NRC B-30/06 SHROUD HEAD BOLTS UT-H-418/D0 136 H
$93H1UO54 RI CRACK INDICATIONS. SEE INF #
593H1CO24 UT CAL 193H1004.'PER GE ASSESSNENT, SIL-433 CONTINUED OPERATION IS JUSTIFIED.
B1.21 A-1A/02 C7 UT H-410/05 119-H 593H1U266 NRI ONE-SIDED EXAM DUE TO RPV B-A BOTTOM HEAD TORUS TO BOTTOM HEAD
$93H1C235 UT CAL SKIRT. REQUIRED VOLUME WAS ASME DOME WELD-593H1U275 NRI SCANNED BY BOTH ANGLES.
593H1C243' UT CAL 100% COVERAGE.
S93H1U261 NRI
-593H1C233 UT CAL 593H10276 NRI S93H1C244-UT CAL
NRI
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E.1. NATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME
-EXAM ~
EXAMINATION CAL EXAM / CAL SECitCN *!
FIGURE Wo.
EXAMINATION / AREA PROCEDURE
-BLOCK SHEET No.
RESULTS REMARKS FEE 0 WATER STSTEM B7.50 A 3/02 1821-1CHSV*1FB VT H 710/03 593H1v008 SAT B-G-2
. FLANGE BOLTING ON CLOSURE HEAD AS"E VENT-B9.11 A 10/05
.1821 1FW-12AA-14 MT-H-500/05-148 H 593H1M033 NR1
- BJ ELBOW TO PIPE UT-H-400/11 593H10095 NRI ASME 593 HIC 057 UT CAL 593H1UO96 THICKNESS B9.11 A-10/05 1821-1FW-12AA-15 MT-H-500/05 148-H
$93H1M024' NRI B-J PIPE TO TRANSITION GE-UT-213/0 DA-182 R!
GEOMETRY RUREG-0619 CA-197 UT CAL 89.11 A-10/05-
-1821-1FW-12AA MT-H-500/05 148-H S93H1M025 NRI
' BJ TRANSITION PIECE GE-UT-213/0 DA-181 RI GEOMETRY NUREG 0619 CA-196 UT CAL
'89.11 A-11/05 1821+1FW-12AB-9 MT-H-500/05 148-H 593H1M030 NRI
. BJ.
. PIPE TO TRANSITION GE-UT-213/0 DA-190 Rt GEOMETRY NUREG-0619 CA-208 UT CAL B9.11 A-11/05 1821-1FW-12AB-10 MT N-500/05 148-H
$93H1M031 NRI B-J TRANSITION PIECE GE-UT-213/0 593H10287 NRI
- RUREG-0619 UT-H-400/11 593H1C251 UT CAL DA-173 RI GEOMETRY CA-186 UT CAL 99.11
.A-12/05 1821-1FW-12BC-9 MT-H-500/05 148-H
$93H1M027 NRI 3-J PIPE TO TRANSITION GE-UT-213/O DA-204 RI GEOMETRY CLREG-0619 CA-224 UT CAL B9.11
' A'-.12/05 1821 1FW-12BC-10' MT-H-500/05 148-H
$93H1M026 NRI B-J TRANSITION PIECE TO.
GE-UT-213/0 -
DA-177 RI GEOMETRY NtnEG-0619 CA-190.
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. CLASS 1 COMPONENTS-ASME EXAM EXAMINATION CAL
' EXAM / CAL
-SECTION XI FIGU9E No.~
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS
'FEEDWATER SYSTEM 89.11 A-13/06 1821-1FW-12BD-15 MT-H-iOO/05 148-H 593H1M028 NRI B-J P!PE TO TRANSITION GE UT-213/0 DA-169 R1 GEOMETRY CUREG 0619 CA 180 UT CAL 69.11 A-13/06 1821-1FW-12BD-16 MT-H 500/05 148-H S93H1M029 NRI B-J TRANSITION PIECE
'GE-UT-213/1 593H1U286 NRl NUREG-0619 UT-H-400/11 593H1C250 UT CAL
.DA-168 RI GEOMETRY CA-179 UT CAL B9.11 A 8/08 1921 1Fb-1SA 12 MT-H-500/05 77-H S93H1M036 NRI 8J PIPE TO ELBOW UT-H 400/11 S93H1U138 NRI ASME
$93H1C083 UT CAL 593H10137 NRI 593H1C082 UT CAL 593H10139 THICKNESS MAIN STEAM SYSTEM 89.11.
A 5/07 1821 1MS-88-BSR-2 MT*H-500/05 5-H 593H1M035 kRI ONE-SIDED EXAM DUE TO FLANGE.
B+J PIPE TO FLANGE UT-H-400/11 593H1U142 NRI 100% COVERAGE.
ASME 593H1C086 UT CAL 593H1U141 NRI 593H1C085 UT CAL 593H1U140 RI GEOMETRY 593H1C084 UT CAL 593H1U143 THICKNESS 89.11 A 4/06 1821-1MS-24A-8
-MT*H-500/05 147-H
$93H1M016' NRI ASME UT-N-400/11 593H1UO28 NR1 B+J ELBOW TO PIPE 593H1C018 UT CAL 593H10034-THICKNESS B10.10 ~
A 4/06 1821-WS-24A 8PS-A-1 AND 2.
MT-H-500/05 593H1M018 NRI B-A'1
- DEVICE B21 MA2 ASME 28
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~ASME EXAM EXAMINATION CAL.
EXAM / CAL SECil04 XI LLGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS MAIN STEAM SYSTEM A'4/06
_1821 1MS-24A-8PS B-1 AND 2 MT*H-500/05 593H1M017 NRI B10.10
+
B K-1 DEVICE B21-HA2 ASEE.
B10.10 A-5A/02-1821+1MS-248 14SL-1 THRU 4 MT'H 500/05
$93H1M019 NRI B K 1J DEVICE B21 CB1-ASME 89.11-A-6/07
.1821-1MS-24C MT-H-500/05 152-H
$93H1M032 NRI B-J -
NO22LE TO TRANSITION PIECE UT-H-400/11 593H1UO97 NRI ASME 593HtC058 UT CAL 593H1UO98 THICKNESS 89.32' A-7/06 ~
1821 1MS-24D-8BC
.MT-H 500/05
$93H1M034 NRI BJ~
PIPE TO BC ASME' 89.11 A-7A/02 1821 1MS 24D*19 MT-H-500/05
' 147 H
$93H1M052 NRI ONE-SIDED EXAM DUE to VALVE B+J PIPE TO VALVE.
UT H-400/11 S93H1U318 NRI CONFIGURATION. CODE COVERAGE ALME
$93H1C273 UT CAL FROM PIPE SIDE.
S93H1U317 RI GEOMETRY 100% COVERAGE.
593H1C272 UT CAL RECIRC. SYSTEM
'B5.10 A 39/00 1831-1RC-4JP-A-1 (PRE-MSIP)
UT-H-409/07 120-H
$93H1U181 NRI-PRE-MSIP EXAMINATIONS.
.BF NSA N02ZLE TO SAFE-END 121-H
-S93H1C116 UT CAL REFERENCE C00E CASE N-461.
$93H1U182 NRI S93H1C117 UT CAL 593H1U183 NRI
$93H1U184 NRI
$93 HIC 119 UT CAL 393H1U185 NRI
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- ASME,
-EXAM EXAM! NATION CAL EXAM / CAL
'SECTION XI. FIGURE NO.
EXAMlWATION/ AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARR$
RECIRC. STSTEM B5.10 A 39/00 1931-1RC-4JP-A*1 (POST-MSIP)
PT-H-600/03 120 H
$93H1P072 NRI '
POST MSIP EXAMINATIONS.
B-F NBA N0ZZLE TO SAFE *END UT-H-409/07 121-H S93H10224
_ NRI REFERENCE CODE CASE N 461.
NUREG-03130 593H1C147 UT CAL
$93H1U221 NRI 593H1C144 -
$93H1C146 UT CAL 593H10222 NR!
$93H1C145 UT CAL 593H1U220 NRI
A-39/00 1831-1RC-4JP-A-2 (PRE-MSIP)
UT-H-400/11 60-H 593H1U187 NRI PRE MSIP EXAMINATIONS.
SAFE-END TO PENETRATION SEAL
$93H1C122 UT CAL REFERENCE CODE CASE N-461.
BJ
~ NUREG 03130 593H1U186 NRI 593H1C121 UT CAL 89.11
'A-39/00 1831-1RC-4JP-A-2 (POST-MSIP)
PT*H-600/03 80-H
$93H1P073 NRI POST MSIP EXAMINATIONS.
-B-J SAFE-END TO PENETRATION SEAL UT*H-400/11 593H1U212 NRI REFERENCE CODE CASE N-461.
NUREG-03130 593H1C135 UT CAL 593H1U211 NRI S93H1C134 UT CAL B5.10 A-39/00 1831-1RC*4JP-B 1 (PRE-MSIP)
UT H-409/07 120-H 593H10164 NRI PRE-MSIP EXAMINATIONS.
.BF NSB N0ZZLE TO SAFE-END 121-H 593H1C098 UT CAL REFERENCE CODE CASE N-461.
NUCEG 03130 593H1U165 NRI 593H1C099 UT CAL 593H1U166 NRI S93H1C100 UT CAL
$93H1U167 NRI 593H1C101' UT CAL 593H1U168 NRI 593H1C102 UT CAL
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EXAMINATION / AREA PPDCEDURE BLOCK SHEET NO.
RESULTS REMA2KS RECIRC. SYSTEM
~ B5.10 :
A-39/00 1931 1RC-4JP-B-1 (POST +MS!P)
PT H 600/03-120 H 593H1P074 NRI POST MSIP EXAMINATIONS.
B-F N88 N0ZZLE TO SAFE END UT-H-409/07 121-H
$93H1U215 NRI REFERENCE CODE CASE N-461.
NUREG-03130 593H1C138 UT CAL 593H1U218 NRI
$93H1C141 UT CAL 593H1U216 NRI -
593H1C139 UT CAL 593H1U217 NRI S93H1C140 UT CAL 593H1U219 NRI
A-39/00
.1931-1RC-4JP-B 2 (PRE-MSIP)
UT-H-400/11 80 H
$93H1U188 NRI PRE-MSIP EXAMINATIONS.
B-J
' SAFE-END TO PENETRATION SEAL
$93H1C123 UT CAL REFERENCE CODE CASE N-461.
NUREG-03130 593H1U189 NRI
$93H1C124 UT CAL 89.11 A-39/00 1831-1RC-4JP B-2 (POST MStP)
.PT-H-600/03-80-H
$93H1P075 NRI POST MSIP EXAMINATIUNS.
BJ SAFE-END TD PENETRATION SEAL --
UT*H 400/11 593H10214 NRI REFERENCE CODE CASE N-461.
NUAEC-03130
$93H1C137 UT CAL S93H10213 NRI 593H1C136 UT CAL 99.11 A-18/04
.1831-1RC-12AR-F-2 GE-UT 212/1 134-H DA-151 NR1 B-J PIPE TO ELBOW DVERLAT CA 157 UT CAL NUREG-0313E DA 152 NRI CA-158 UT CAL 39.11 A-18/04 1831-1RC-12AR-F'3 UT-H 408/04 134-H DA-133 NRI B-J
'ELBOU TO PIPE OVERLAY CA-139 UT CAL NUREG 0313E DA-134 NRI' CA 140 UT CAL B9.11 A-18/04 183i 1RC-12AR*F GE-UT-212/1 134-H DA-139-NRI
.31-
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME EXAM' EXAMINATION CAL-EXAM / CAL' SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCR SHEET NO.
RESULTS REMARKS RECTRC. SYSTEM B9.11 A 18/04
'1B31-1RC-12AR-G 3.
GE-UT*212/1 134-H DA-115 NRI B-J ELBOW TO PIPE CVERLAY CA-117.
.NUREG-0313E DA 116 NRI CA-118 UT CAL B9.11' A-18/04 1931-1RC-12AR-G-4
'GE-UT-212/1 134-H DA 141 NRI 2
-B-J PIPE TO SAFE-END DVERLAY CA-147 UT CAL NUREG-0313E-DA-142 NRI CA-148 UT CAL B5.10 A-18/04 1831-1RC-12AR G-5 PT-H-600/03 85-H
$93H1P069 NRI BF SAFE-END TO NO2ZLE GE-UT-209/1 31-H DA-170 RI GEOMETRY
'NUREG 0313C CA-181 UT CAL DA-171 RI GEOMETRY CA-182 UT CAL CA-183 UT CAL DA-172 RI GEOMETRY CA-184 UT CAL CA-185 UT CAL 89.11 '-
A-18/04 1831 1RC 12AR-H 2 GE-UT-212/1' 134-H DA-166-NRI BJ PIPE TO ELBOU OVERLAY' CA-177 UT CAL NU::EG-0313E -
'89.11 LA-18/04 1831-1RC 12AR-H-3~'
GE-UT 212/1 134 H DA-104 NRI
-B-J
ELBOW TO PIPE OVERLAY CA-104 UT CAL NUREG-0313E-DA-105 NRI CA-105 UT CAL 593H10241 WELD PROFILE
.' B9.11.
A-18/04 1931-1RC-12AR N-4' GE-UT-212/1 134-H DA-143 NRI-BJ-PIPE TO SAFE-END DVERLAY CA-149 UT CAL-NUREG-0313E DA-144 NRI
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EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS PECIRC. SYSTEM.
B5.10.
A-18/04
'1931-1RC-12AR-H-5 ei H-600/03 85-H S93H1P076 NRI
_ 8-F SAFE-END TO N0ZZLE GE-UT 209/1 31-H DA-163 RI GEOMETRY NUREG-0313C-CA-172 UT CAL DA-164 RI GEOMETRY CA-173 UT CAL CA-174 UT CAL DA-165 RI GEOMETRY CA-175 UT CAL CA*176 UT CAL B9.11 A-18/04
-1831-1RC-12AR-J-3 GE-UT-212/1 134+H DA 106 RI PREVIOUSLY RECORDED INDICATION
.B*J ELBUW TO PIPE OVERLAY CA-106 UT CAL NO APPARENT GROWTH.
NUREG 0313E DA-107 NR1 CA-107 UT CAL 593H10240 WELD PROFILE 89.11 A 18/04 1831-1RC-12AR-J-4 PT-H-600/03 17-H
$93H1P071 NRI ONE-SIDED EXAM DUE TO SAFE-END B-J PIPE TO SAFE-END.
GE-UT-208/1 DA-147 NRI TAPER. CODE COVERAGE FROM NUREG-0313C.
DA-148 NRI 100% COVERAGE.
B5.10
'A-18/04'
'1831-1RC-12AR-J-5.
PT-N-600/03 85-H 593H1P070.
NRI NUREG-0313C GE-UT-209/1
' 31-H DA-178 RI GEOMETRY BF SAFE-END TO N0ZZLE CA-191 UT CAL DA-179 RI GEOMETRY CA-192 UT CAL CA-193 UT CAL DA-180 RI GEOMETRY CA-194-UT CAL
~A'18/04' 1831-1RC-12AR-K-2.
GE-UT-212/1 134-H DA-149 R1 NON-GEOMETRIC 0.29" INDICATION.
B-J PIPE TO ELBOW OVERLAY CA-155-UT CAL INTERBEAD LACK OF FUSION.
NUIEG-0313E DA-150 NRI SEE INF 193H1010.
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EXAM EXAMINATION CAL EXAM / CAL SECTION XI ' FIGURE NO.
EXAMINATIOW/ AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RECIRC. SYSTEM 89.11 A-18/04
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' ELBOW TO PIPE OVERLAY CA-108 UT CAL NUREG-0313E-DA 109 NRI' CA-109 UT CAL
- 89.11' A-19/04 1831-1RC-12BR C-1 PT H-600/03 17-H
$93H1P015 NRI ONE-SIDED EXAM DUE TO REDUCER
~
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$93H1C160 UT CAL FROM PIPE SIDE.
$93H1U324 NRI 100% COVERAGE.-
593H1C159 UT CAL 593H1U326 THICKNESS
' B+J '
' 1
'1831 1RC 12BR-D-i PT-H-600/03 17-H
$93H1P001 NRI ONE-SIDED EXAM DUE TO B-C 59.11 A-19/04 B-C TO PIPE UT*H 400/11 593H1U319 NRI GEOMETRY. CODE COVERAGE FROM NUREG-0313C 593H1C155 UT CAL THE PIPE SIDE.
S?3H1U320 NRI 100% COVERAGE.
$93H1U348 TN'.CKNESS 89.12 A-19/04 iB31'1RC-12BR-D-1LD PT-H-600/03' 17-H 593H1P027 NRI BJ LONG11UDINAL SEAM WELD EXTENDING UT-H-400/11 S93H1UO63 NRI NUREG-0313A
- DOWNSTREAM-593H1C030 UT CAL B9.11 A 19/04 1831-1RC-12BR D-2 UT H-408/04 134-H DA-198 RI NON GEOMETRIC INTERBEAD LACK OF FUSION.
B-J PIPE TO ELBOW OVERLAY GE-UT-212/1.
CA-218 UT CAL SEE INF 193H1013.
NUREG-0313E DA-199 NRI CA 219 UT CAL S93H1U335 NRI
B9.11 A-19/04 1B31-1RC-12BR-D*3' GE-UT-212/1 134-H DA-188 NRI B-J ELBOW TO PIPE OVERLAY-CA-206 UT CAL NUXEG-0313E DA 189 NRI CA 207 UT CAL 4
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v E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS i
ASME EXAM EXAMINATION CAL EXAM / CAL
'SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RECIRC. SYSTEM B9.11 A 19/04 1931-1RC-12BR-D-4 PT-H-600/03-17-H 593H1P068 NRI B.J PIPE TO SAFE-END GE-UT 208/1 DA-193 RI IIEOMETRY IXJREG-0313C UT-H-400/11 CA-211 UT CAL DA-194 NRI S93H1U334-NRI S93H1C164 UT CAL B5.10 A 19/04 1931-1RC 12BR D-5 PT*H 600/03 85-H S93H1P090 R1 PREVIOUS INDICATION. NO SAFE-END TO N0ZZLE GE-UT-209/1 31 H -
DA-195 kl GEOMETRY CHANGE.
B-F NUIEG-0313C' CA-213~
UT CAL DA-196 RI GEOMETRY CA-214 UT CAL CA-215 UT CAL DA-197 RI GEOMETRT CA-216 UT CAL CA 217 UT CAL 89.11 A-19/04 1B31-1RC-12BR-E-1 PT-H-600/03 17-H
$93H1P003 NRI ONE-SIDED EXAM DUE TO B C B-J' B-C TO PIPE UT H-400/11
$93H1U322 NRI CONFIGURATION. CODE COVERAGE NUREG-0313C 593H1C158 UT CAL FROM THE PIPE SIDE.
S93H1U321 NRI 100% COVEtAGE.
S93H1C157-UT CAL 593H1U323 THICKNESS' B9.11 A-17/04 1931 1RC 22BM-1 UT-H-408/04 134 H
$93H1UO12 NRI B-J CAP TO PIPE OVERLAY
$93H10008 UT CAL NUXEG-0313E' 4
.B9.31 A-17/04' 1931-1RC-22BM-1BC-1' PT-H-600/C3 47-H 593H1P002 NRI BJ PIPE TO B C UT-H-400/11 S9341U013
- NRI NUREG-0313C'
'A-17/04 1831 1RC-22BM-1BC-2_
.PT-H-600/03 47 H
$93H1P004
' NRI BJ PIPE.TO B-C UT-H-400/11 593H1UO14 NRI GM EG-0313C S93H1C010 UT CAL B10.10 A 17/04 iB31-1RC 228M-1HL-A-1 AND 2' PT-H-600/03 593H1P031.-
NRI
- B-K-1 DEVICE B31-HB4
. NUREG 0313L 35
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RESULTS REMARKS RECIRC. SYSTEM B10.10 A-17/04 1931-1RC-22BM-1HL-B-1 AND 2 PT-H 600/03
$93H1P030 NRI B-K-1 DEVICE B31-HB4 NUREG 0313L
-89.11 A 17/04 1831 1RC-22BM 2
,PT H-600/03 47 H
$93H1P013 NRI ONE-SIDED VOLUMETRIC B-J' PIPE TO CROSS UT H+400/11 593H1UO22 NRI EXAMINATION DUE TO CROSS.
NUREG 0313C 593 HIC 014 UT CAL 593H10023 NRI S93H1C011 UT CAL B9.11 A-17/04-
.1831 1RC-22BM-3 PT-H-600/03 47-H.
$93H1P014 NRI ONE-SIDED EXAM DUE TO B-J-'
CROSS TO PIPE UT-H-400/11 593H10024 NRI CONFIGURATION OF CROSS.
NUREG-0313C1
$93H1C015 UT CAL S93H10025 NRI 593H1C012 UT CAL 89.31 A-17/04 1831-1RC+228M 30"-1.
PT-H 600/03' 47-H
$93H1P005 NRI B+J PIPE TO B-C '
ST-H-400/11 S93H1UO21 NRI NUREG-0313C 593H1C013 UT CAL B9.31 A-17/04 1931 1RC-22BM-3BC-2
. PT-H-600/L'3 47-H 593H1P083 NRI B-J PIPE 10 B-C UT H-400/11 593H1U230 NRI NUREG 0313C.
$93H1U231 NRI
.S93H1C154.
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UT-N 408/04 134-H'
$93H1U235 RI' LINEARS PREY!OUSLY RECORDED INDICATION BJ PIPE TO CAP OVERLAY--
593H1C215
,NUREG-0313E' B9.11 A-14/05 1831-1RC-28A 3 PT-N 600/03 151-H
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'GE-UT-208/1 DA-101 RI GEOMETRf'
-l
'l 89.11 A*14/05 1B31-1RC-284.GE-UT-212/1 134-H DA-102 NRI B+J ELBOW TO PIPE OVERLAY-CA 102 UT CAL NUREG+0313E DA 103 NRI CA 103
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O E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASEE EKAM:
EXAMINATION CAL EXAM / CAL SECTION XI ' FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET No.
RESULTS REMA#RS RECIRC.' SYSTEM 89.11 A-15/05 1B31-1RC 288-3 UT H-408/04 134-H DA-137 NRI B-J PIPE TO ELBOW OVERLAT CA-143 UT CAL
'NUREG-0313E DA-138 NRI CA-144 UT CAL B9.11 A-15/05 1931-1PC-28B 4 GE-UT-212/1 134-H DA-145 RI NON-GEOMETRIC INTERBEAD LACK OF FUSION B-J-ELBOW TO PIPE OVERLAT CA-151 UT CAL -
INDICATIONS.
NUREG-0313E DA-146 RI NON-GEOMETRIC SEE INF 193H1009.
CA-152 UT CAL 89.11 A 15/05 1831-1RC-288-5 PT-H-600/03 151-H 593H1P012 NRI ONE-SIDED EXAM DUE TO TEE B-J PIPE TO TEE GE-UT 208/1 DA-191 NRI CONFIGURATION. CODE COVERAGE NUREG-0313C CA*209 UT CAL FROM PIPE SIDE.
DA-192 RI GEOMETRT 100% COVERAGE.
CA-210 UT CAL B9.11 A 15/05 1931-1RC-288-6 PT-H 600/03 151-H 593H1P026 NRI ONE-SIDED EXAM DUE TO TEE B-J TEE TO PIPE GE-UT-208/1 DA-186 RI GEOMETRT CONFIGURATION. CODE COVERAGE NUREG-0313C CA-204 UT CAL FROM PIPE SIDE.
DA-187 R1 GEOMETRT 100% COVERAGE.
CA-205 UT CAL B9.12 A-15/05 1831-1RC+288-6LD PT-H-600/03
'151-H
-S93H1P011 NRI B-J LONGITUDINAL SEAM WELD EXTENDING UT-H-400/11 593H10051 NRI NUREG-0313A DOWNSTREAM 593H1CO23 UT CAL B10.10
'A-15/05 1931-1RC-288-6HL-1 THRU 4 PT-H 600/03 593H1P091
- NRI LIMITED EXAM DUE TO SUPPORT B-K-1
' DEVICE B31-HB1 AND WHIP RESTRAINT' NU7;EG-0313L INTERFERENCE. 77% COVERAGE.
' 09~11
'A-15/05 1831-1RC-288-7 PT-H-600/03 151-H 593H1P007 NRI
' B-J PIPE TO ELBOW GE-UT 208/1-DA-110 R1 GEOMETRT CUREG-0313C CA*110 UT CAL 37
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- t E l. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME'
-EXAM EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS RECIRC. SYSTEM B9.12 A-15/05.
1831-1RC-288-7LD-l.
PT-H-600/03
'151 H
$93H1P008 NRI
. B-J LONGITUDINAL WELD DOWNSTREAM ON UT-H-400/11 S93H1UO49 NRI NUREG-0313A INSIDE OF ELBOW 593H1C021 UT CAL a-89.12' A 15/05 1831-1RC-289-7LD PT-H-600/03 151-H 593H1P009.
NRI B-J LONGITUDINAL WELD DOWNSTREAM ON UT-H-400/11 593H10048 NRI NUREG-0313A OUTSIDE OF ELBOW' 593H1C020 UT CAL 89.11 A 15/05 1831 1RC-288-10 GE-UT-212/1 134-H DA-202 NRI
-B-J P!PE TO ELBOW OVERLAY-UT-H-408/04 CA-222 UT CAL NUREG 0313E DA-203 NE!
$93H1C261 UT CAL 89.11 A-15/05 l1831-1RC 288-11 UT-H-408/04 134-H
$93H1UO73 NRI B-J ELBOW TO PUMP OVERLAY
$93H1C040 UT CAL NUREG-0313E 89.11 A-15B/02 1831-1RC-288 15 -
UT-H-408/04 134 H
.593H1U301 RI PREVICUSLY RECORDED
. B-J ELBOW TO PIPE OVERLAY S93H1C262 UT CAL INDICATION. NO CHANGE FROM NUREG-0313E PAST DATA.
B10.20 A-20/03 RC-8 PUMP LUG-2A1.
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'RC-B PUMP LUG 2A2' PT-H-600/03 S93H1P080 NRI BK1 RESTRAINT LUG AS;E -
810.20 A-20/03'
'RC-B PUMP LUG-281 PT-H 600/03
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O E.1. HATCM UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASM EXA4 EXAMINATION CAL EXAM / CAL SECTION XI FIGURE No.
EXAMINATION / AREA PROCEDURE BLOCK SNEET No.
RESULTS REMARKS RECIRC. SYSTEM B10.20-A-20/03' RC-B PUMP LUG-282 PT-H-600/03
$93H1P082 NRI B-K+1 RESTRAINT LUG ASME CONTROL ROD DRIVE SYSTEM B5.10 A-1/04' 1C11-1CRD-3-R-18A (PRE-MSIP)
PT-H 600/03 97+ M
$93H1U174 NRI PRE MSIP EXAMINATIONS.
B-F CAP TO N022LE UT*H 409/07 120-H
$93H1C108 UT CAL REFERENCE CODE CASE N-461.
NUREG-0313D 593H1U175 NRI S93 HIC 109 UT CAL S93H1U176 NRI S93H1C111 UT CAL S93H1U177 NR1 S93H1C110 UT CAL S93H1U178 RI S93 HIC 112 UT CAL
$93H1U179 NR1 593H1C113 UT CAL 593H1U180 RI GEOMETRY S93H1C114 UT CAL B5.10
.A-1/D4 1C11 1CRD-3-R-18A (POST-MSIP)'
PT-H-600/03 97 H 593H1P078 NRI POST MSIP EXAMINATIONS.
B-F CAP TO N0ZZLE-UT-H-409/07 120-h S93H1U225 NRI REFERENCE CODE CASE N-461.
KUREG-0313D S93H1C148 UT CAL S93H1U226 NRI 593H1C149 UT CAL 593H1U227-RI GEOMETRY
'593H1C150 UT CAL S73H1U228 NRI S93H1C151 UT CAL 593H1U229 NRI S93H1C152 UT CAL RESIDUAL HEAT REMOVAL SYSTEM
'89.11 A*23/04.
.GE UT 212/1 134-H DA 111 NRI B+J '
ELBOW TO PIPE OVERLAY CA-111 UT CAL INTERBEAD LACK OF FUSION.
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FIGURE NO.
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RESIDUAL NEAT REMOVAL' SYSTEM 89.11-
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NUREG-0313E DA 118 NRI CA-116 UT CAL B9.11 A-22/05
'1E11 1RHR-248 R MT-H 500/05 152-H 593H1M022 NRI B-J ELB0tl TO PIPE UT H-400/11 S93H10061 NRI
$93H10062 THICKNESS 99.11 A 22/05 1E11-1RHR-245 A-12 GE-UT-212/1 135-H-DA-207 RI PREVIOUSLY RECORDED INDICATION
.B-J VALVE TO PIPE OVERLAY CA 227 UT CAL NO APPARENT CHANGE.
NUREG-0313E DA-208 NRI CA-228 UT CAL g
C9.11
.A-22/05 1E11-1RHR 248 R*13' GE-UT-212/1 134 H
'DA 205 RI PREVIOUSLY RECORDED INDICATION
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'DA+206 NRI CA-226 UT CAL B9.11
'A-22/05:
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RESULTS REMARKS CORE SPRAY SYSTEM B5.130 A-26/05 1E21-1CS-10A-18A (PRE MSIP)
GE-UT-208/1 150-H DA-135 RI GEOMETRY PRE-MSIP EXAMINATIONS B F-PIPE TO SAFE-END EXTENSION UT-H-409/07 137-H CA-141 UT CAL NUREG-0313D DA-136 RI GEOMETRY CA-142 UT CAL S93H1U160 NRI S93H1C115 UT CAL B5.130 A 26/05 1E21-1CS 10A-18A (POST-MSIP)
PT-H-600/03 150-H 593H1P087 NRI POST-MSIP EXAMINATIONS BF PIPE TO SAFE-END EXTENSION' GE-UT-208/1 137 H DA-161 RI GEOMETRY NUREG-03130 UT-H-409/07 CA-170
'lT CAL DA-162 RI GEOMETRY 4
CA-171 UT CAL S93H1U273 NRI 593H1C241 UT CAL i
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A-26/05
'1E21 1CS-10A 19A (PRE-MSIP)
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.NUREG-03130 DA-128 RI GEOMETRY CA*131 UT CAL DA-129 RI GEOMETRY CA 132 UT CAL
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RESULTS PEMARKS CORE SPRAY SYSTEM B5.10
'A rs/05
'1E21-1CS-10A-20A-(POST-MSIP)
PT-H-600/03 108-H 593H1P068 NRI POST-MSIP EXAMINATIONS.
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.B9.11 A-27/05 1E21-1CS-10B-3 MT-H-500/05 137-H S93H1M021 NRI B-J ELBOW TO PIPE UT-H-400/11
$93H10055 NRI ASME.
593H1CO25 UT CAL 593H1UO60 THICKNESS B5.130 A 27/05 1E21-1CS-108 19A (PRE-MSIP)
UT-M-409/07 150-H DA-122 NRI PRE-MSIP EXAMINATIONS B-F PIPE TO SAFE-END EXTENSION GE-UT-108/1 137-H CA-125 UT CAL
'NUREG-0313D DA 123 RI GEOMETRY CA-126 UT CAL
$93H1U159 NRI
~
B5.130 A-27/05 1E21 1CS 108-19A (POST MSIP)
- PT-H-600/03 150-H
$93M1P084 NRI POST-MSIP EXAMINATIONS.
BF PIPE TO SATE-END EXTENSION GE-UT 208/1 137-H DA-156 NRI NUREG-03130 UT-H-409/07 CA-165 UT CAL DA-157 RI GEOMETRY CA-166 UT CAL
$93H1U274 NRI S93H1C242 UT CAL B9.11 A-27/05 1E21*1CS-10B-20A (PRE-MSIP)
GE-UT-208/1
'85-H DA-124 R1 GEOMETRY PRE-MSIP EXAMINATIONS.
B+J SAFE-END EXTENSION TO SAFE-END CA-127 UT CAL REFERENCE CODE CASE N-461.
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PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS CORE SPRAY SYSTEM C9.11 A-27/05 1E21-1CS-108-20A (POST-htlP)
PT-H-600/03 85-H
$93M1P085 NRI POST-MSIP EXAMINATIONS.
B-J
. SAFE-END EXTENSION TO sal'-END GE UT-208/1 DA 158-RI GEOMETRY REFERENCE CODE CASE N-461.
NUREG-03130 CA-167 UT CAL DA-159 R1 GEOMETRY CA-168 UT CAL DA-160 R1 GEOMETRY CA-169 UT CAL B-F A-27/05' 1E21 1CS-10s-21A (PRE-MSIP)
'GE-UT-209/1 108-H DA-119 NRI.
PRE-MSIP EXAMINATIONS.
B5.10 :
SAFE-END TO N0ZZLE 85-H CA-119 UT CAL NUREG-03130 CA-120 UT CAL DA-120 RI GEOMETRY CA-121 UT CAL CA-122 UT CAL DA-121 RI GEOMETRY CA-123 UT CAL CA-124 UT CAL 85.10 '
A-27/05 --
-1E21-1CS-108 21A (POST-MSIP)
PT-H 600/03 108-H
$93H1P086 NRI POST-MSIP EXAMINATIONS B-F
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' SAFE-END TO N0ZZLE GE-UT-209/1 85-H DA-153 Rt GEOMETRY NUREG-03130-CA-159-UT CAL DA 154.
RI GEOMETRY CA 160
-UT CAL CA-161 UT CAL DA-155 RI GEOMETRY CA 162 UT CAL CA 163 UT CAL HIGH PRESSURE COOLANT INJECT 10N' SYSTEM 89.11' A-28/05 1E41 1HPCI 10-0-12 MT-H 500/05 137-H
$93H1M037 NRI B-J PIPE TO TEE UT-H 400/11 593H1U267.
N1 ASME 593H1C236 UT CAL 593H10268 NI
$93H1C237-UT CAL 43
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O-E.I. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME' EXAM EXAMINAfl0N CAL EXAM / CAL
- SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK
_ SHEET Wo.
RESULTS REMARKS REACTOR CORE ISOLATION COOLING SYSTEM 89.11 A-30/04' 1E51-1RCIC-4 D-23 MT-H-500/05 7-H 593H1M041 N1 ONE SIDED EXAM DOE TO VALVE.
B*J PlPE TO VALVE UT-H-400/11 593H1U252 NRI CODE COVERAGE FROM PIPE SIDE.
ASME 593H1C226 UT CAL 100% COVERAGE.
S93H1U253 RI GEONETRY S93H10227 UT CAL
$93H1U254 THICKNESS PEACTOR WATER CLEAN UP SYSTEM-89.11 A-32/05 1G31-1RWCUM 6-0 2 PT*H-600/03 133 H-S93H1P032 kRI BJ PIPE TO ELBOW UT-H-400/11 S93H10103 NRI M EG-0313A 593H1C063 UT CAL 89.12 A-32/05 1G31*1RWCUM-6-0-2-IR PT-H-600/03 133-H 593H1P033 NRI
-B-J LONG SEAM WELD DOWNSTREAM ON UT-H 400/11
$93H1U148 NRI NUREG-0313A INSIDE OF ELBOW 593H1C091 UT CAL 593H1U149 THICKNESS B9.12 A-32/05 1G31*1RWCUM 6 D-2-LU PT-H-600/03 133-H 593H1P034 NRI B-J LONG SEAM WELD EXTENDING UT H-400/11 S93H1U154 hRI NUREG 0313A UPSTREAM
$93H1C094 UT CAL S93H1U130 THICKNESS
.89.12 A-32/05 1G31-1RWCLH-6 0-2-OR PT H 600/03 133-H
$93 HIP 035 NRI
~'B-J LONG SEAM WELD DOWNSTREAM ON UT N-400/11 593H1U152 NRI NUREG-0313A OUTSIDE OF ELBOW' 593H1C093 UT CAL 593H10153 THICKNESS 89.11
'A-32/05-1G31-1RWCUM-6-D-3 PT*H-600/03 133-H S93H1P036 NRI B-J ELBOW TO PIPE.
UT-N 400/11 S93H1U104 NRI NUREG 0313A 593H1C064 UT CAL
'89.12 A-32/05 1G31+1RWCUM 6-D-3 LD PT-H-600/03 133-H
$93H1P037 NRI BJ LONG SEAM WELD EXTENDING' UT-H-400/11 S93H1U156 NRI
- C"JIEG-0313A -
' DOWNSTREAM
$93H1C095 UT CAL 593H1U131 THICKNESS 44.
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EXAMINATION / AREA' PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS REACTOR WATER CLEAN-UP SYSTEM B9.11 A-32/05 1G31-1RWCUM-6-D-4 PT-H-600/03 133-H
$93H1P056 NRI ONE-SIDED EXAM DUE TO VALVE.
B-J PIPE TO VALVE UT-H-400/11 S93H1U116 NRI CODE COVERAGE FROM PIPE SIDE.
NUREG-0313A
-$93H1C066 UT CAL 100% COVERAGE.
S93H1U135 NRI S93H1C080 UT CAL B9.12 A 32/05 1G31-1RWCUM-6 D-4 LU PT-H-600/03 133-H
$93H1P057 NRI B*J LONG SEAM WELD EXTENDING UT-H-400/11 593H1U117 NRI NUREG-0313A UPSTREAM 593H1C074 UT CAL B9.11-A-32/05 1G31-1RWCUM-6-D 5 PT-H-600/03 133-H 593H1P058 NRI ONE-SIDED EXAM DUE TO VALVE.
.- B - J
' VALVE.TO ELBOW UT-H-400/11 S93H1U118 NRI 100% COVERAGE.
NUREG 0313A 593 HIC 075 UT CAL
$93H10136 NRI 593H1C081 UT CAL B9.12.
A-32/05' 1G31-1RWCUM 6-0 5-IR
- PT-H-600/03 133-H 593H1P059 NRI B*J LONG SEAM WELD DOWNSTREAM ON UT-H-400/11' 593H1U119 NRI NUIEG-0313A-INSIDE OF ELBOW S93H1C076 UT CAL 89.12 A-32/05
-1G31-1RWCUM-6-0-5-OR PT-H-600/03 133-H'
$93H1P%0 NRt B-J LONG SEAM WELD DOWNSTREAM ON UT*H-400/11 593H1U120 NRt NUREG 0313A OUTSIDE OF ELBOW -
593H1C077 UT CAL B9.11 A-32/05.
1G31-1RWCUM-6*D 6 PT-H-600/03 133-H S93H1P061 NRI BJ-.
' ELBOW TO PIPE UT-H-400/11 593H1U115 NRI NUREG-0313A 593H1C078 UT CAL 89.12 A-32/05 1G31-1RWCUM-6-D-6-LD:
~
PT*H-600/03 133-H 593H1P067-NRI BJ LONG SEAM WELD' EXTENDING UT-H-400/11
'S93H1U114 NRI NUREG-0313A DOWNSTREAM 593H1C079 UT CAL B9.32
.A-32/05-1G31-1RWCUM-6-D-6-BC-1 PT*H 600/03 S93H1P062 NRI BJ PIPE TO BRANCH CONNECTION NUREG-0313A
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- O E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME-EXAM EXAMINATION CAL EXAM / CAL SECTION XI -FIGURE NO.
' EXAMINATION / AREA PROCEDUq BLOCK SHEET NO.
RESULTS REMARKS REACTOR WATER CLEAN-UP SYSTEM 89.11 A*32/05 1G31+1RWCUM-6-D-7 PT-H-600/03 133-H
$93H1P063 NRI B-J PIPE TO ELBOW UT-H-400/11 593H10144 NRI NU;EG-0313A:
$93H1C087 UT CAL B9.12 A-32/05 1G31-1RWCUM-6-D-7-IR PT H-600/03 133-H 593H1P064 NRI B-J LONG SEAM WELD DOWNSTREAM ON UT-H-400/11 593H1U146 RI GEOMETRY
-NUREG-0313A
.INSIDE OF ELBOW 593 HIC 090 N/A-UT CAL B9.12 A 32/05' 1G31-1RWCUM-6-D-7-LU PT H 600/03 133-H
$93H1P065 NRI B-J LONG SEAM WELD EXTENDING.
UT H-400/11
-S93H1U145 NRI NUREG-0313A UPSTREAM 593H1C088 UT CAL B9.12 A-32/05 1G31-1RWCUM-6-D-7-OR,
PT H-600/03 133-H 593H1P066 NRI B-J-LONG SEAM WELD DOWNSTREAM ON UT-H-400/11 593H1U147 NRI NUREG-0313A OUTSIDE OF ELBOW S93H1 COB 9-UT CAL B9.11 A-32/05
~1G31-1RWCUM-6-D-8.
PT-H-600/03 133-H
$93H1P038 NRI B-J
. ELBOW TO PIPE.
UT-H 400/11
$93H1U102 NRI NUREG-0313A
$93H1C062 UT CAL B9.12 A-32/05 1G31-1RWCUM 6-D-8 LD PT-H-600/03 133-H
$93H1P039 NRI B-J LONG SEAM WELD EXTENDING UT-H 400/11 S93H1U106 NRI NUREG-0313A DOWNSTREAM
-THICKNESS 99.11-A-32/05 1G31*1RWCUM-6-D-10 PT-H-600/03 133-H
.593H1P040 NRI B-J ELBOW TO PIPE UT-H-400/11 593H1U101 NRI-NUREG-0313A'
$93H1C061 UT CAL PT'N-600/03 133-H
$93H1PO41 NRI 89.11 A-32/05
~1G31-1RWCUM-6-D-10-A B-J PIPE.TO PIPE UT-H-400/11 593H1U100 RI GEOMETRY
~ E EG-0313A 593H1C060 UT CAL 89.12 A-32/05 1G31+1RWCUM 6-D*10-A*LD-PT-N-600/03~
133*H 593H1PO42 NRI B-J.
LONG SEAM WELD EXTENDING UT-H-400/11
$93H1U109 NRI l'UREG 0313A DOWNSTREAM' 593H1C070' UT CAL S93H1U124 THICKNESS
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O E.I. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS
-RSME EXAM EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINAil0N/ARCA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS
.PEACTOR WATER CLEAN-UP SYSTEM 89.12 A-32/05 1G31*1RWCUM-6 D 10-A LU PT-H 600/03 133 H
$93H1PO43 NRI B-J-LONG $EAM WELD EXTENDING UT H 400/11 593H1U108 NRI
,NUREG-0313A UPSTREAM 593H1C069 UT CAL 593H1U126 THICKNESS 89.12
'A-32/05.
1G31-1RWCUM-6-0-10 LD PT-H 600/03-133-H
$93H1PO44 NRI BJ-LONG SEAM WELD EXTENDING UT-H-400/11 593H10107 NRI NUREG 0313A
$93H1U127 THICKNESS B9.11 A-32/05 1G31 1RWCUM-6-D 11 PT-H-600/03-133-H
$93H1PO45 NRI B-J PIPE TO ELBOW UT-H 400/11 593H1UQ99 RI GEOMETRT
'NUREG-0313A-593H1C059 UT CAL 89.12 A-32/05.
1G31-1RWCUM 6-D 11-IR PT-H-600/03 133-H
$93H1PO46 NRI B-J LONG SEAM WELD DOWNSTREAM OH UT-H-400/11 593H1U111 NRI NUREG-0313A INSIDE OF ELBOW 593H1C072 UT CAL S93H1U123 THICKNESS B9.12 A 32/05-
~1G31-1RWCUM-6-D-11-LU
_PT'H 600/03 133-H 593H1PO47 NRI B-J LONG SEAM WELD EXTENDING UT-H-400/11 593H1U112 NRI NUREG-0313A UPSTREAM
$93H1C073 UT CAL 593H1U122 THICKNESS 89.12 A-32/05) 1G31+1RWCUM-6-D-11-OR PT-H-600/03 133-H 593H1PO48 NRI B-J LONG SEAM WELD DOWNSTREAM ON UT H-400/11 S93H1U110 NRI
.NUREG-0313A:
OUTSIDE OF ELBOW:
.S93H10071 UT CAL S93H1U125 THICKNESS
~
99.11.
A 32/05 1G31 1RWCUM 6 D-12
'PT-H-600/03 133-H
$93H1PD49 NRI B-J
. ELBOW TO PIPE'.
UT-H-400/11 593H1U0S4 NRI NU2EG-0313A-S93 HIC 049 UT CAL 89.12 -
A 32/05 1G31-1RWCUM-6-D 12-LD
.PT+H 600/03 133*H S93H1P050 NRI
'B-J LONG SEAM WELD EXTENDING -
UT-H-400/11 593H10090 NRI
' tu;EG 0313A-
'47
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME EXAM EXAMINAfl0N CAL EXAM / CAL SECTION XI FIGURE NO.'
' EXAMINATION / AREA PROCEDURE BLOCK
$NEET NO.
RESULTS REMARKS REACTOR WATER CLEAN-UP STSTEM B9.11 A-32/05 1G31-1RWCUM-6-D 13 PT-H-600/03 133-H 593H1P051 NRI B-J PIPE TO ELBDW UT*H-400/11 S93H1U105 NRI NUREG-OP IA S93H1C065 UT CAL B9.12 A-32/05 iG31-iRWCUM-6-D-13 IR PT-H-600/03 133-H
$93H1P052 '
NRI B-J LONG SEAM WELD DOWNSTREAM ON UT H-400/11
$93H1U150 NRI NUREG+0313A INSIDE OF ELBOW 593H1C092 UT CAL
$93H1U151 THICKNESS B9.12 A-32/05 1G31-1RWCUM 6-D-13-LU PT H-600/03 133-H 593H1P053 NRI EXAM LIM!iE9 70 4" Cd CW SIDE B-J LONG SEAM WELD EXTENQlNG
'UT-H-400/11 593H1UO91 NRI DUE TO WELDED SUPPORT.
NUREG 0313A UPSTREAM
$93H1C054 UT CAL 100% SURFACE COVERAGE.
83.5% VOLUMETRIC COVERAGE B9.12 A-32/05 1G31 1RWCUM-6-D*13-OR
~ PT-H-600/03 133 H
$93H1P054 NRI B-J LONG SEAM WELD DOWNSTREAM ON UT-H-400/11 593H1U157 NRI NUREG-0313A OUTSIDE OF ELBOW
$93H1C096 UT CAL 593H1U153 THICKNESS 99.11 A 32/05 1G31-1RWCUM-6-D-14 PT-H 600/03 133-H
$93H1P055 NRI ONE SIDED EXAM DUE TO ELBOW TO 8-J ELBOW TO VALVE UT*H-400/11 593H10085 NRI VALVE CONFIGURATION.
CUREG-0313A 593H1C050 UT CAL 100% SURFACE COVERAGE.
593H1UC89 R1 GEOMETRY 52% VOLUMETRIC COVERAGE.
. A 32/05 1G31-1RWCUM 6 D-16 PT-H-600/03 133-H 593H1P077-RI 3/32" LINEAR ~
CODE ALLOWABLE LINEAR SURFACE BJ PENETRATION TO PIPE UT*H-400/11 593H1U203 NRI INDICATION. ONE-SIDED EXAM DUE NUREG-0313A
$93H1C126 UT CAL 70 PENETRATION. CODE COVERAGE 593H1U202 NRI FROM PIPE SIDE.
S93H1C125 UT CAL 100% COVERAGE.
-89.12 A 32/05 1G31-1RWCUM-6-D.16-LD
.PT-H-600/03 133-H 593H1P092 NI B-J LONG SEAM WELD EXTENDING UT H-400/11 593H1U2D4 NRI CUREG-0313A DOWNSTREAM
B9.11 A-32/05 1G3161RWCUM-6-D 17
.PT-H 600/03 133-H.
593H1P016 NRI B*J PIPE TO ELBOW UT-H-400/11 S93H1UO81
_RI-GEOMETRY NUREG-0313A-593H1C046 UT CAL 48
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS AS;'.E EXAM EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET No.
RESULTS REMARKS REACTOR WATER CLEAN-UP SYSTEM 89.12.
A-32/03 1G31-1RWCUM-6-D-17-IR PT-H 600/03 133-H 593H1P025 NRI B-J LONG SEAM WELD DOWNSTREAM ON UT*H-400/11 593H1UO79 NRI I:tREG-0313A JINSIDE OF ELBOW 593H1C044 UT CAL
'B9.12 A-32/05 1G31-1RWCUM 6-D 17 LU
'PT-H-600/03 133 H
$93H1P093 NI
[B-J LONG SEAM WELD EXTENDING UT*H-400/11 593H1U205 NRI NUREG-0313A-UPSTREAM-
A-32/05
~ 1G31 1RWCUM-6-D-17-OR PT*H-600/03 133-H 593H1P024 NR1 8J LONG SEAM WELD DOWNSTREAM ON UT-H-400/11 593H1UO80 NRI NtAEG-0313A OUTSIDE OF ELBOW 393H1C045 UT CAL
.89.11 A-32/05 1G31-1RWCUM 6-D 18 PT-H-600/03 133-H 593H1P023 NRI B-J ELBOW TO P!PE UT-H 400/11 593H1UO78 -
NRI 5:UREG 0313A 593H1C043 UT CAL 89.12 A-32/05 1G31'1RWCUM-6-D 18 LD PT+H-600/03 133-H S93H1P022 NRI BJ LONG SEAM WELD EXTENDING UT-H-400/11 593H10072 NRI NtAEG 0313A
. DOWNSTREAM
A-32/05 1G31-iRJCUM-6-D-19 PT-H-600/03 133-H 593H1P021 NRI BJ PIPE TO ELBOW UT-H-400/11 593H10065 NRI
-NUREG 0313A
$93H1C032 UT CAL B9.12 A-32/05 1G31-1RWCUM 6-D 19-IR PT-H-600/03-133-H 593H1P020 NRI BJ LONG SEAM WELD DOWNSTREAM ON UT-H-400/11 593H10%9 NRI' NOREG-0313A INSICE OF ELBOW
- C9.12 A-32/05 1G31'1RWCUM-6-D-19-LU PT-H 600/03 133-H 593H1P019 NRI BJ LONG SEAM WELD EXTENDING
. UT-H 400/11
$93H1UO71 NRI
$7JREG-03134 UPSTREAM S93H1C037 UT CAL 89.12 L A-32/05 1G31-1RWCUM-6-D*19 OR PT-H 600/03 133-H
$93H1P018
-NRI B'J LONG SEAM WELD DOWNSTREAM ON-U' H-400/11 593H1UO70 NRI NUREG-0313A OUTSIDE OF. ELBOW 593H1C038 UT CAL L49
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 1 COMPONENTS ASME EXAN EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCIC SHEET NO.
RESULTS REMARKS REACTOR UATER CLEAN-UP STSTEM B9.11 -
A-32/05 1G31 1RWCUM 6-0-20 PT-H-600/03 133-H 593H1P017 NRI ONE SIDED EXAM DUE TO ELBOW:
B-J ELBOW TO VALVE UT-H-400/11 593HlV066 NRI AND VALVE CONFIGURATION.
NUREG 03134 593H1C033 UT CAL 100% SURFACE COVERAGE.
593H1UO67 NRI 72% VOLUMETRIC COVERAGE.
$93H1UO68 NRI 593H1C035 UT CAL VALVE BOLTING B7.70 A-4/06 821-F013A BOLTING VT*H 710/03 593H1v068 SAT B-G-2 VALVE BOLTING ASME B7.70 A-4/06 B21-F0138 BOLTING VT-H-710/03 S93H1V069 SAT B-G-2 VALVE BOLTING
-ASME B7.70 A-5/07 821 F013C BOLTING VT-H 710/03 S93H1V070 SAT B-G 2 VALVE BOLTING ASME B7.70 A-5/07 821-F0130 BOLTING VT-H-710/03 593HIV071 SAT B-G-2 VALVE BOLTING
. AST.E -
BT.70 A-5/07 -
B21-F013E BOLTING VT-H-710/03.
593HIV072 SAT B-G-2 VALVE BOLTING ASME B7.70 A-6/07 821 F013F BOLTING
'VT-H+710/03 S93H1v073 SAT B-G-2 VALVE BOLTING ASME.
B7.70 A 6/07 B21-F013G BOLTING VT*H-710/03
$93H1V074 SAT B-G-2 VALVE BOLTING
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E.1. HATCH UNIT 1 SPRING 1993 REFUEtING OUTAGE CLASS 1 COMPONENTS
~AEME EXAM.
EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SNEET NO.
RESULTS REMARKS VALVE BODIES 812.50 A-26 E21-F006A BODY 450C-INS-N/A SAT MWO 1-92-6700 INSPECTED UPPER INSIDE PORTION-
' B-M-2
-VALVE BODIES
'012-05 0F THE VALVE ONLY DUE TO WATER
- ASME AND INACCESSIBILITY.
B12.50 A 28..
E41-F002 BODY' 450C-INS-N/A SAT MWO 1-92-6809 REPLACED VALVE STEM, PACKING, BM2-VALVE BODIES 012-0S~
PRESSURE SEAL, AND OPERATOR.
ASME B12.50
.A-28 E41-F003 BODY 45CC* INS-N/A UNSAT MWO 1-92-6808 STELLITE ON ONE SIDE OF DISK B-M-2
' VALVE BODIES 012-OS SAT MWO 1-93 1324 WAS CRACKED. SEE DC 1-93-943.
ASME REPLACED DISK. VT ACCEPTABLE.
B12.50~
'A-32 G31*F001 BODY 450C-INS-N/A SAT MWO 1-92 6807 REPLACED STEM OPERATOR AND B-M-2 VALVE BODIES-012-OS YOKE, INSPECTED INTERNALS.
=S2 2, ;-..
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O E.I. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 2 COMPONENTS
' ASME -'
EXAM EXAMINATION CAL EXAM / CAL SECil04 XI ' FIGURE No.
EXAMINATION / AREA-PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS CONTROL R00 DRIVE SYSTEM C5.11 B 84/03 1C11 2CRD-8N $0V-4 MT-H 500/05 593H1M038 NRI CF
. ELBOW TO TEE
--NUREG D803s RESIDUAL PEAT REMOVAL SYSTEM C3.10 B-32/04 1E11-2HX-A-USC 3 MT H-500/05 593H1M003 NRI C-C UPPER SUPPORT BRACKET AS;;E C1.30 B-32/04 -
1E11-2HX-B-3 UT-H-400/11 72-H
$93H1UO18 NRI ONE-SIDED EXAM DUE To FLANGE
-C-A LOWER $ HELL RING TO FLANGE
$93H10029 R!
GEDHETRY 100% COVERAGE.
$93H1U001 RI GEOMETRY S93H1C001 UT CAL S93H1U003 RI.
GEOMETRY
$93H1C003 UT CAL 593H10171 RI GEOMETRY
$93H1U004 THICKNESS B-38A/02 1E11-2RHR-4A-D-C-6 MT-H-500/05 593H1M007 NRI ELBOW TO PIPE' AUGMENTED.
l C5.11 B-69/05-
-1E11+2RHR 6A-RVD-7
'MT-H-500/05 S93H1M003 41
- C-F PIPE TO ELBOW ASME I
C5.11 B-72/06 1E11-2RHR 8-FPS-3 MT H 500/05 S93H1M011 NRI
- C-F TEE TO PIPE
- ASME B-62/05 1E11 2RHR-168 DS 12 MT-H 500/05 S93H1M010 NI VALVE TO P1PE:
AUGMEETED 54 -
10 0
0 E.I.' HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 2 COMPONENTS ASME EXAM
.SECTION XI FIGURE No.
'EXtMINATION/ AREA PROCEDURE BLOCK SHEET NO.
FESULTS REMARKS RESIDUAL HEAT REMOVAL SYSTEM
.C5.11 B-58/05 1E11 2RHR*168-HXO-2 MT-H-500/05 593H1M047 NRI C-F ELBOW TO VALVE ASME C5.11-B 45/05 1E11 2RHR-20A-FD-C-4 Mi-H-500/05 S93H1M012 RI NON GEONETRIC 0.8" LINEAR INDICATION.
C-F VALVE TO TEE-593H1M020 R!
NON-GEOMETRIC SEE INF :93H10n3.
-ASME 593H1M054 NRI 593H1U327 THICKNESS
$93H10033 SIZING
$93H10044 WELD PROFILE C5.21 B-46/05 1E11-2RHR-24A-BP-7
.MT-H-500/05 139 H 593H1M014 NRI C-F ELBOW TO PIPE UT-H-400/11 593H10075 RI GEOMEIRY ASME-593H1C042 UT CAL 593H1UO74 RI GEOMETRY
$93 HIC 041 UT CAL 593H1UO20 THICKNESS C5.11 B-38/05 1E11-2RHR*24A-TS-C-7 MT-H 500/05
$93H1M053 NRI C-F-PIPE TO ELBOW
-ASME-CORE SPRAY SYSTEM 89.11 B-6/04 1E21-2CS-10A 4.
'MT-H-500/05 137-H S93H1M015 NI ONE-SIDED EXAM DUE TO VALVE.
.B-J VALVE TO PIPE UT-H-400/11 S93H1UO26 NI CODE COVERAGE FROM PIPE SIDE.
ASME 593H1C016 UT CAL' 100% COVERAGE.
593H1UO27 RI GEOMETRY
$93H1C017 UT CAL S93H1U163 THICKNESS HICH PRESSURE COOLANT INJECTION SY$ REM C5.21 B-21/05 1E41-2HPCI-10-SS-5 MT*H-500/05 137-H 593H1M006 N1
'C-F
-PIPE TO ELBOW UT-H-400/11
'S93H10019 NRI ASME 593H1C007 UT CAL S93H1UO56 THICKNESS i
55 a.. a -.
.--_.-..-~._...,._..,_....___._...._u._..
t O
O LO E.I. HATCH UNIT 1 SPRlWG 1993 REFUELING OUTAGE CIA 5S 2 COMPONENTS ASME
. EXAM EXAMINATION CAL EXAP/ CAL SECTION Xi FIGUDE NO.
EXAMINAftDN/ AREA PROCEDURE BLOCK SHEET NO.
RESULTS PEMARKS HIGH PRESSURE COOLANT INJECTION SYSTEM B-20/05
. 1E41-2HPCI-10-SS 29R MT-H 500/05 137-H 593H1M050 NRI ONE* SIDED EKAM DUE TO VALVE
-VALVE TO PIPE UT-H 400/11 S93H1U310 NRI GEOMETRf. CODE COVERAGE FROM ASME 593H1C269 UT CAL PIPE SIDE. BASELINE EXAM.
S93H1U311 NRI 100% COVERAGE.
593H1C270 UT CAL 593H1U312 RI GEOMETRY 593H1C271 UT CAL S93H1U313 THICKNESS B-20/05
' 1E41-2HPCI 10-SS-309 MT H 500/05 137-H
$93H1M049 NRI-ONE SIDED EXAM DUE TO TEE
-~
TEE TO PIPE UT-H-600/11 593H1U307 NRI CONFIGURATION. CODE COVERAGE ASME S93H1C266 UT CAL FROM THE PIPE SIDE BASELINE.
S93H1U308 NRI EXAM.100% COVERAGE.
S93H1C267-UT CAL 593H1U309 R!
$93H1U314 THICKNESS B 12/04 1E41-2HPCI-10-TL-5A MT H-500/05 54-H 593H1M051 NRI ONE SIDED EXAM DUE TO VALVE PlPE TO VALVE UT-H-400/11 593H1U304 NRI.
CONFIGURATION. CODE COVERAGE
- ASME
$93H1C263 UT CAL FROM PIPE SIDE.
593H1U305 NRI 100% COVERAGE.
593H1C264 UT CAL 593H1U306 RI GEOMETRY E93H1C265 UT CAL
$93H1U303 THICKNESS C5.21 B-10/04 1E41-2HPCI-14-R-10
' MT-H 500/05 116-H
$93H1M005 NRI ONE-SIDED EXAM DUE.TO PIPE
'N C-F P!PE TO FLANGE UT-H-400/11-
$93H1U006 NI
. TO FLANCE CONFIGURATION.
$93H1C006 UT CAL 100% COVERAGE.
S93H1U005 NI S93H1C005 UT CAL S93H10007 THICKNESS C5.11 B-14/05 1E41-2HPCI 18-TD-2 MT-H 500/05 593H1M001 NRI C-F '
ELBOW TO P!PE-ASHE 56
,,,,-*---e-+-.
.-,e,----
,,,---e
..m-m..~. - *,,
..-.rw--
....,e-
...e..
.-s-*-
.-+.--,.,m-w-
-.. ~.. <..... -,,.,...
...-,m-..,__-__,_-._..--,____-.r--_..r_
- m
l
.6 E.I. NATCH UNIT 1 SPRING 1993 REFUELING OUTAGE CLASS 2 COMPONENTS ASME.
EXAM EXAMINATIf4 CAL EXAM / CAL SECi!ON XI FtrCRE NO.
EXAMINATION / AREA PROCEDURE BLOCK SNEET NO.
RESULTS REMARKS REACTOR CORE ISOLATION COOLING SYSTEM B-95/02-1E51-2RCIC-4-SS-1 MT-H-500/05.
S93H1M042 NI VALVE TO PIPE AUGMENTED C5.11 B-24/05 f1E51-2RCIC-10-TD-1
_MT-H 500/05 593H1M009 NRI C-F FLANGE TO TEE ASME
' REACTOR WATER CLEAN-UP SYSTEM B-83/07.
1G31 2RWCU 4 R-3A
'UT-H-400/11 142-H S93H1UO58 NRI TEE TO PIPE
$93 HIC 026 UT CAL NCEG 0619 593H1UO57 NRI S93H1CO27 UT CAL B-83/07 1G31-2RWCO-4-R-4C UT-H-400/11, 142-H
$93H1UO59 NRI
~ PIPE TO PIPE.
.593H1C028 UT CAL NCEG-0619 MAIN STEAM AUXIt'IARY SYSTEM' C3.20 B-74/06
'i=11-2MSA-24A-11PS-1 THRU 4 MT-H 500/05
$93H1M048 NRI C-C DEVICE N11-MSH ASME
'C5.21 B-75/06-
.1N11-2MSA-24B-9 MT-H-500/05--
147-H 593H1M023 NRI C-F -
TEE TO PIPE UT-H-400/11 593H1UO92 NRI ASME 593H1C055 UT CAL 593H1UO93 NRI
' THICKNESS
-TURBINE STEAM BYPASS SYSTEM C3.20.
B-81/04 1N37-2TSB-16B-12PS-1 AND 2 MT-N-500/05 593H1M013 NR CC DEVICE N11-TBH-36 ASME 57~
- = -
~
- tm j
E.T. MATCH UNIT 1 4tRING 1993 REFUELING OUTAGE CLASS 2 COMPONENTS ASME EXAM EXAMINATION CAL EXAM / CAL SECT 104 XI FIGURE NO.-
ExAMINAitoN/ AREA' PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS CONTAIN"ENT PURGING AND INERTING SYSTEM
-C5.11 B-31/05 1T48-2 CPI-6-SVT-3 MT-H-500/05 593H1M002 NI C-F ELBOW TO PIPE AS".E
. 58
..-.,.2-.:~.-.....::.-...
- - - -..u ~
~.......-- -
.- u
I 1
Q 1
i'
SUMMARY
l 0:
r CIASS 1 AND 2 PRESSURE TESTS.
PRESSURE TESTING O
59
GENERAL 1
This section of the report provides a discussion of the pressure tests which were performed during the 1993 Plant E.I. Hatch Unit 1 Spring
'( )
Refueling Outage. These pressure tests were performed for the purpose of inservice inspection on Cltss 1, and 2 components. The pressure tests and their boundaries are ir:2ntified in the Inservice Inspection Plan-l documents prepared by Souttern Nuclear Operating Company.
(
All pressure tests were performed 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 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 procedure 42IT-TET-006-1S, ISI Pressure Test of the Class 1 System.
TEST RESULTS Only minor leakage at mechanical joints was found during the VT-2 examinations. Any component which was disassembled prior to startup or to repair leakage, was re-examined during startup at normal operating 1
pressure (1005 psig) per GPC procedure 42IT-TET-004-OS, Operating i
Pressure Testing of Piping and Components.
CLASS 1 PRESSURE TEST
SUMMARY
a TEST I.D.
PROCEDURE MWO NUMBER l
1B21-LT-1 421T-TET-006-1S 1-92-6939 CLASS 2 PRESSURE TE9TS One (1) Class 2 Hydrostatic Pressure Test was performed during the outage per ASME Section XI paragraph IWA-5211(d)._The test was performed i
in accordance with GPC procedure 42IT-TET-003-OS, Hydrostatic Pressure Testing of Piping and Components.
One (1) Class 2 Hydrostatic Pressure Tests-was performed during the outage per ASME Section XI Code Case N-498. The test was performed in accordance with GPC procedure 421T-TET-004-OS, Operating / Pressure Testing of Piping and Components.
TEST RESULTS' only minor leakage at mechanical joints was reported during the VT-2 examination and all results were determined to be acceptable or were.
repaired.
}
60
i CLASS 2-
SUMMARY
I I'
TEST I.D.
PROCEDURE MWO NUMBER 1E41-HT-3 42IT-TET-003-OS 1-92-6937.
~
- 421T-TET-004-OS None-Required
- Pressure Test performed per ASME Section XI Code Case N-498
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SUMMARY
OF VISUAL EXAMINATIONS
(
CLASS 1 AND 2 i
COMPONENT SUPPORT:1
?
e i
i b
i f
I 1
62
~ -..
COMPONENT SUPPORT EXAMINATIONS i
i This section of the report provides a discussion of the visual y
examinations performed on selected component supports on Hatch Unit 1.
i Os Equipment supports and pipe supports inspected are listed on separate tables as part of this section. The subject examinations were performed during the Refueling / Maintenance Outage.
Examinations were performed using SNC Procedure VT-H-730 (VT-3 and VT-4).
The procedure and all-examination data sheets are available for review at the plant site.
Pinina Support Examinations Class 1 t
Eight (8) component supports from the B21, B31, E21, E41, E51, and G31' systems were visually examined.
No unacceptable indications were detected.
Class 2 Twenty-nine (29) component supports from the C11, Ell, E41, E51, and N11, systems were visually examined.
No unacceptable indications were detected.
Eauipment Support Examinations Class 1 8
one (1) equipment support from the Bil system was visually examined.
No unacceptable indications were detected.
Class 2 Nine-(9) equipment supports from the C41, Ell, E21,- E41, E51, and_T47, detected.
No unacceptable indications were systems were visually examined.
(
i b
9 63 p
9
.y c-1993 E.I. NATCH UNIT 1 PIPE SUPPORTS
'ASME.
'CLAH SUPPORT.
FIGURE NO' HANGER TYPE RESULTS REPORT NO.
INF NO.
MWO NO.
RETUt.TS REPORT NO.
REMARKS 1
1821-FDH+10' A-8/08.
RESTRAINT.
A S93H1V066' 1
1831-HB1 A-15/03 SPRING A
593H1V064 1
1831-HB2 A-158/02 SPRING A
593H1V063 1
1E21-CSH 802.-
A-27/05 RESTRAINT A
S93H1V059 2
1-1E41 HPSEH-52 A-28/05 SPRING A
S93H1V061-
'1-
'1E41-HPCIM-30 A-29/06 RESTRAINT
'A
$93H1V030 1
1E51-RCSEH 18
- A-30/04
' SPRING A
S93H1VC58 1
1G31 X-14 A-32/05 ANCHOR A
$93H1VDil 2
'1E21-CSH-27 B-8/04 SPRING A
$93h1V038 2
1E41-HPClH-14 B 10/04 SPRING A
$93H1V053 2
1E41-HPSEH-10 B-15/05 SPRING -
A 593H1V031-2 1E41-HPSEH-15 B-16/05 RESTRAINT A
S93H1V032 2
1E41-HPSEH-32 B-19/05.
SUPPORT-A S93H1V054 21 1E41-HPSEH-19 B-22/05 HANGER A'
593H1V033 2
1E11-RHRM-4 B 36/3 SPRING A
$93H1v016 2
1E11 RHRM-125 B 47/04 RESTRAINT A
S93H1v014 2
1E11-RHRM-271 1B 47/04 RESTRAINT A'
593H1V021.
2 1E11-RHRM 383 B-49A/01
-RESTRAINT A
S93H1V045 2
1E11 RHRH-384 B 49A/01-RESTRAINT A
S93H1V046 2-1E11-RHRM-397 B-52/05 SPRING A
S93HIV051 2.
1E11 RHRM-376.
-B-54/04-RESTRAINT A'
593H1V020 2
-B-72/06 RESTRAINT A
$93H1V080 2
1N11 MSH 19:
B-74/06 SIMPLE A
$93H1V025.
2
-1N11-MSH-57 B 74/06 SPRING A
S93H1V028 2
,1N11-MSH 31 B 75/06 1 HANGER
'A^
- $93H1V026---
' 64.
. ~ ;... :...
g
- 0 0
1993 E.I. HATCH UNIT 1 PIPE SUPPORTS ASME ICLASS SUPPORT.
FINRE No NANGER TYPE
'RESULTS REPORT NO.
INF NO.
MWO NO.
RESULTS REPORT NO.
REMARKS 2
IN11 MSH 58:
945/06 SPRING.
.A
$93H1V029 2
1N11-AC 1 8-76/06
ANCHOR A
$93H1V047 "2
1N11-MSH 56-B-77/06 SPRING A
$93H1V027 2
1N11*1BH 26 B 80/05
$UPPORT A
'593H1V034 2-1C11 CRD-H26 B 84/03 -
SIMPLE.
A S93H1V041
.2
.1C11-CRD-H24
-B-84/03 ANCHOR A'
S93H1V040'
'2 ic11 CRD H23
-B-84/03
~ RESTRAINT A
$93H1V039
'2 1C11-CRD HS B-85/05 SUPPORT-A S93H1V042 2
'B-85/05 NANGER 1A
$93H1V043
.2 1E51-RCSEH-15 B-96/01 SPRING A
593H1V048 2
'B-96/01 SPRING-1A 593H1YO22 2
1E51-RCICH-19 B-99/01 RESTRAINT
'A 593HIVD23
.- j 5
'65 i
...m.... m. u..
.-.-m,,
..,,_....;.._.-..-.A,
-, ~..
..,_.s._,-,,..A........J.,.,_,,,..J,,..J.,
b
.Q-f%.:
A-3
~ 1993 E.I. HATCH UNIT i EQUIPMENT SUPPORTS
.ASME' CLASS-SUPPORT FIGUDE NO MANGER TYPE RESULTS. REPORT No.
INF NO.
MWO NO.
RESULTS REPORT NO.
REAARKS 1
iB11-A001-S01 1811*SK1
' REACTOR VESSEL A-
$93HIV082 2
1C41-A001 501 1C41 SK2 TANK
-A 593H1V044 2-1E11-B0014 $01 1E11-$K4' HT EXCH A
S93H1V019 2
1E21'C001A*S01 1E21-SK6 PUMP A
593H1V017 2
1E41-C001-501 1E41 SK7-PUMP A.
S93H1V052 2 '.
1E51 C001-S01 1E51-SK8 PUMP A.
593HIV024 2
iT47-8007A-S01 1147-SK9.
COOLING UNIT A
> $93H1V079 2
1T47-8008A-501 11T47-SK10 COOLING UNIT' A
593H1V067 2
1147 8009A S01 1T47-SK11 C00t!NG UNIT A.
' 593H1V062-2 1C41-C001A S01 1C41-SK3.
PUMP A
S93H1V078 66 1
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+.
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a +,
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ev...
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+..%o
,,...%.e,4.,w,,
P SNUBBER SUPPORT EXAMINATIONS This section of the report provides a discussion of-the-visual =
examination (VT) performed on snubber supports.
All safetyfrelated l
j --
snubbers were VT examined lar GPC QC personnel using GPC procedure 45QC-INS-012-OS-(VT-3).
The subject examinations were performed prior to and during the.
Refueling / Maintenance Outage.
The procedure and all examination data sheets are available for review at the plant site, t
Examinations Class 1 Seventy-five (75) snubbers from the B21, B31, Ell, E41, E51, and G31 systems were visually examined. No unacceptable indications were l
detected.
Class 2 One hundred sixty-three (163) snubbers from the Ell, E21, E41, E51, N11, and T48 systems were visually examined. No unacceptable indications were detected.
h i
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~
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1993 E.1. HA1CH UNIT 1 SNUBBERS ASME CLASS
-SUDPORT
~ FIGURE NO HANGER TYPE RESULTS REPORT NO.
INF NO.
MWO NO.
RESULTS REPORT NO.
REMARKS 1
B21 SS1 A-4/06 HYDRAULIC SNUBBER A
N/A 1
.B21-SS2 A 4/06 HYDRAUL!C SNUBBER A
N/A 1'
B21-SS6 A-5/07 HYDRAULIC SNUBBER A
N/A 1
821-S$7
'A-5/07 HYDRAULIC SNUBBER A
N/A 1
B21-SS23 A-6/07.
HYDRAULIC' SNUBBER A
-N/A 1
,B21-SS24 A-6/07
- HYDRAULIC SNUBBER A
N/A 1
821-S$36 A*7/06 HYDRAULIC SNUBBER A
N/A 1
B21-5S37 A-7/06 HYDRAULIC SNUBBER A
N/A
.1 B21-FDH 12 A-8/08 HYDRAULIC SNUBBER A
N/A
-- 1 B21-FDH-11' A-9/07 HYDRAULIC SNUBBER A
N/A 1
821-FDH-23 A-10/05
' HYDRAULIC $NUBBER A
N/A
~
l' B21*FDH 24 A-10/05 HYDRAULIC SNUBBER A
N/A 1
B21 FDH-15 A-11/05
-HYDRAULIC SNUBBER
'A N/A 1
B21-FDH-16 A-11/05 HYDRAULIC SNUBBER A
N/A
~1 B21-FDH-19 A 11/05 HYDRAULIC SNUBBER-A-
N/A
~
i B21-FDH-17 A-12/05' HYDRAULIC SNUBBER A
'N/A 1
821-FDH-18 A-12/05 HYDRAULIC SNUBBER A
N/A 1
821-FDH-26 A-13/06-
. HYDRAULIC SNUBBER -
A N/A 1
B21-FDH A-13/06 HYDRAULIC SNUBBER A
N/A 1
B31-SSA8 A-14/05 HYDRAULIC SNUBBER A
N/A
.1 B31 SSA1 A 14A/01
' HYDRAULIC SNUBBER' A
N/A 1
B31-SSA2..-
=A-14A/01 HYDRAULIC SNUBBER.
-A N/A
-1 B31-SSA3 A-14A/01:
HYDRAULIC SNUBBER A
N/A
~1-831-SSA4-
- A-14A/01.
HYDRAULIC SNUBBER A
N/A.
68 ~
...x,,
I
)
1993 E.I. HAYCH UN!Y 1 SNUBBERS ASME QAj_S
'SUPPORY-
-FIGURE NO-HANGER YYPE PESULTS PEPORY NO.
INF NO.
MWO NO.
RESULTS REPORY NO.
REMARKS S
1 B31-SSA5 A-14A/01 HYDRAullC SNUBBER A
-N/A 1
831-SSA6_
A 14A/01 HYDRAULIC SNUBBER A
N/A 1
831 SSA12 A-148/02 HYDRAULIC SNUBBER
- A N/A 1
831-SSA13 A-14B/02 HYDRAULIC SNUBBER A
N/A 1
B31-SSA14 A-14B/02 HYDRAULIC SNUBBER A
N/A 1.
B31 SSB7 JA-15/05 HYDRAULIC SNUBBER A
N/A
~1 B31-5588 A 15/05
'HYDRAUllC SNUBBER A
N/A 1
831 5532 A-15A/01 HYDRAUllc SNUBBER A
N/A 1
B31-SSB3 A-15A/01 HYDRAULIC SNUBBER A
N/A 1
B31 5S84 A-15A/01 HYDRAULIC SNUBBER A
N/A 1
B31-SSB5-A-15A/01 HYDRAULIC SNUBBER A
N/A 1
B31-SSB6 A-15A/01 HYDRAULIC SNUBBER A
N/A 1.
B31 55B12 A 158/02 HYDRAULIC SNUBBER-A N/A
'1 831-55B13 A 158/02 HYDRAULIC SNUBBER A-N/A 1
831-SSB14 A-15B/02 HYDRAUllC SNUBBER A
N/A
'1 E11-54 A-21/05
-HYDRAULIC SNUBBER A
N/A 1
E11-S1_
A 21/05-HYDRAULIC $NUBBER A
N/A 1
E11 S2
= A 21/05 HYDRAULIC SNUBBER A
N/A 1
E11-55 A-21/05 HYDRAULIC SNUBBER A
N/A 1-E11 S15 A-22/05 HYDRAULIC SNUBBER A
N/A 1
-E11-SM-1 A-22/05 HYDRAULIC SNUBBER
-A-
.N/A 1
E11-SM-2 A-22/05 HYDRAULIC $NUBBER A
N/A 1
E11-SM -A-22/05 HYDRAULIC SNUBBER A
N/A.
1-E11 SM-3 A-23/04 -
HYDtAULIC SNUBBER A
N/A' "69
... ~.,.
. = -..
..,.... _ - - _-. w
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f~~'[
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.GJ 1993 E.1. HATCH UNIT 1 SNUBBERS ASME CLASS SUPPORT-F!GURE NO NANGER YYPE RESULTS REPORT NO.
INF NO.
FWO NO.
RESULTS REPORT NO.
REMARKS 1
Eil SM 4 A-23/04
~ HYDRAULIC SNUBBER A
N/A 1 --
E41-SS-21 A-28/05 HYDRAULIC SNUBBER A
N/A 1.
E41-SS 8 A-28/05 HYDRAULIC SNUBBER A
N/A 1
E41 SS-22 A*28/05 HYDRAULIC SNUBBER A
N/A
-1 E41 SS 17
-A-28/05 HYDRAULIC SNUBBER A
N/A i
~ E41-SS-18 A 28/05 HYDRAULIC SNUBBER A
N/A
-1 E41 SS-20 A 28/05 HYDRAULIC SNUBBER A
N/A 1
E41-SS A-28/05 HYDRAULIC SNUBBER A'
N/A 1'
B21-RCIC SS 43 A-30/04 HYDRAULIC SNUBBER A
N/A' 1
B21 RCIC-SS-44 A-30/04 HYDRAULIC SNUBBER A
N/A 1
B21 RCIC-SS-41 A-30/04 HYDRAULIC SNUBBER' A
N/A 1
821-RCIC SS-42 A-30/04 HYDRAULIC SNUBBER A
N/A 1
G31-S17 A-32/05 HYDRAULIC SNUBBER A
N/A 1
G31'SM-7
' A-32/05 HYDRAULIC SNUBBER A'
~.N/A 2
E21-CSH-71 B-3/04
~ HYDRAULIC SNUBBER A
N/A 2
'E21-CSH-79 B-6/04 HYDRAULIC SNUBSER A
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-E41 HPCIN 13 B-10/04 HYDRAULIC SNUBBER.
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E41-HPSEH.55 B-20/05 HYDRAULIC SMUSBER -
A N/A 2
E41-HPSEH-61 B-22/05 HYDRAULIC SNUBBER A
N/A l.-
2-E51 RCSEH 20 B 24/05 HYDRAULIC SNUBBER A
N/A L
2 E51-RCSEH-21
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T48-CPM-20
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N/A 2
T48 CPH-14 B-27/05 HYDRAULIC SNUBBER A
N/A l
2 T48-CPH 55 B-30/06 HYDRAULIC SNUBBER A
N/A 2
T48-CPH 40 B 30/06 HYDRAULIC SNUBBER-A N/A 2
E11*RHRH-202 B-33/05'-
HYDRAULIC SNUBBER
.A N/A.
2 E11 RHRH-309 -
B-35/04 HYDRAULIC SRUBBER
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E11 RHRM-323 B 36/05 HYDRAULIC. SNUBBER A-N/A-2 E11 RHRH-195-B-41/06 HYDRAULIC SNUBBER A
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E11-RHRH-192 B-41/06
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E11 RNRM-187 B 42/05 HYDRAULIC SNUBBER A.
'N/A' 2
E11*RNRM-233
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N/A 2
E11-RHRH-234-B-43/04 HYDRAULIC SNUBBER A-N/A 2
-E11 RHRH-230' B-44/05-HYDRAULIC SNUBBER LA N/A 2
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REMARKS 2
E11-RHRH-224 B 46/05 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH-225 B-47/04 HYDRAULIC SNUBBER A
N/A 2
E11 RHRH-288.
B-48/06 HYDRAULIC $NUBBER A
N/A 2'
E11*RHRH+220 B-49/05 HYDRAULIC SNUBBER A
N/A 2
E11*RHRH 222 B-49/05 HYDRAUllC SNUBBER A
N/A 2
E11-RHRH-192 B-49A/01 HYDRAULIC SNUBBER A
N/A
.2-E11-RHRM 244 B 51/05 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH-245 B 51/05 HYDRAULIC SNUBBER A
N/A 2
E11 RNRH-239 B-52/05 HYDRAULIC SNUBBER A
N/A 2
E11 RHRH-238 B 52/05 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH-237 B-52/05 HYDRAULIC SNUBBER A
N/A 2
E11 RHRM-210
'B-53/05 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH 212
~ B-54/04 HYDRAULIC SNUBBER A
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E11-RHRH-215' B 55/06 HYDRAULIC SNUBBER A
N/A 2
E11 RHRH-214 B-55/06 HYDRAULIC $NUBBER A
N/A 2
E11 RHRH-213 B 55/06 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH-216 B-56/06 HY?RAULIC SNUBBER A
N/A 2
E11-RHRH-217 B-56/06 HYDRAUllC SNUBBER A
N/A 2
E11 RHRH-306 B-56/06 HYDRAULIC SNUBBER A
N/A 2
E11-RHRH-305 B-56/06 HYDRAULIC SNUBBER A
N/A 2
E41 HPSEH 92 B 57/05 -
HYDRAULIC SNUBBER A
N/A 2
E41 HPSEH-93 8-57/05 HYDRAULIC SNUBBER A
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E11-RHRH 218 B-58/05 HYDRAULIC SNUBBER A
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E11+RHRH 279 B-60/05
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N/A 2
E11-RHRH 250 B-61/05 HYDRAULIC SNUBBER A
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E11-RHRH-251.
'B 61/05',
NYDRAUllC SNUBBER A
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E11 RHRM 242-B-62/05 HYDRAULIC SNUBBER A_
N/A 2
'E11-RHRM 240 B-62/05 HYLRAULIC SNUBBER A
N/A 2
E11-RHRM-399 B-62/05 HYDRAULIC SNUBBER' A
N/A 2
E11 RNRM-249 '
,B-63/05 HYDRAULIC SNUBBER A
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E11-RHRM 254
'B-65/04
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-E41-HPSEH-o6
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E41-HPSEH-67, B-67/05 HYDRAULIC SNUBBER A
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E41-HPSEH 63 B-67/05:
' HYDRAULIC SNUBBER A~
N/A 2
E41-HPSEH-800 B-67/05 HYDRAULIC SNUBBER A
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E41 NPSEH 85 B-69/05
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.A.
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E41-HPSEH-87 B-69/05 HYDRAULIC SNUBBER A.
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E41 HPSEH-80 B-69/05 HYDRAULIC SNUBBER A
N/A 2-E41-HPSEH-81 B-69/05
- HYDRAULIC SNUBBER.
A
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E41-HPSEH-82
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.E41-HPSEH 84 B-69/05 HYDRAULIC SNUBBER A.
N/A 2
' E11-RHRM-400 B-70/04 HYDRAULIC SNUBBER A
..N/A I
E11-RHRH-207 B-72/06
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REMARES
-2 E41-MPSEH-76 B-73/06 HYDRAULIC SNUBBER A
N/A 2-E41 HPSEH-77 B 73/06-HYDRAULIC SNUBBER A
N/A 2.
N11-MSH-59 B-74/06 HYDRAULIC SNUBBER A
N/A 2-
.N11-MSH-20 B-74/06 HYDRAULIC SNUBBER A
N/A
. 2-N11-MSH 23 B 74/06 HYDRAULIC SNUBBER A
N/A 2"
'N11-MSH 38 B-74/06 HYDRAutIC SNUBBER A
h/A 2
N11-MSH 40 B-75/06 HYDRAULIC SNUBBER A
N/A 2
N11-MSH 30 B 75/06 HYDRAULIC SNUBBER A
N/A
'2 N11-MSH-33 B-75/06 HYDRAULIC SNUBBER A
N/A 2
N11-MSH-39 B-75/06 ~
HTDRAUllC SNUBBER A
N/A
'2-N11-MSH 6 B-76/06.
HYDRAULIC SNUBBER A'
N/A 2
.N11-MSH 36 B-76/06 HYDRAUllC SNUBBER A
N/A' 2
N11-MSH 14 B-77/06 HYDRAULIC SNUBBER A
- N/A 2
N11-MSH-37 B-77/06-HYDRAULIC SNUBBER A
N/A 2-N11*TBH-32.
.B-80/05
' HYDRAULIC SNUBBER-A N/A
-2
. N11-TBM 33 -
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-HYDRAULIC SNUBBER A
N/A N11-TBH-30 B-81/04 HYDRAULIC SNUBBER A
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- ASME
,; CLASS SUPPORT FIGURE NO HANGER TYPE RESULTS REPORT NO.
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NWO NO.
RESULTS REPORT NO.
REMARKS 1
B21-FDH 700 A-9/07 MECH SNUBBER A
N/A 1
B21 FDH+701 A*10/05 MECH SNUBBER A
N/A 1
B21-FDH-13 A 11/05 MECH SNUBBER A
N/A 1
821-FDH 21 A-11/05-MECH SNUBBER A
N/A 1
B21-FDH-829 A-11/05 MECH SNUBBER A
N/A 1
B21-FDH-14 A-12/05 MECH SNUBBER A
.N/A 1
B21-F0H-20 A-12/05 MECH SNUBBER A
N/A 1
'B21 FDH 22.
A-12/05 MECH $NUBBER A
N/A 1-B31-SSA7 -
.A 14/05
. MECH SNUBBER
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't.
~B31-5581 A-15A/01
' MECH SNUBBER A
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E51-RCIC-H705 A-31/06 MECH SNUBBER
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'1 G31 SM-6 A-32/05 MECH SNUBBER A
N/A 1
G31-SM-5 A-32/05 MECH SNUBBER A
N/A
.2 E41 HPCIH-700 B-13/05 MECH SNUBBER A'
N/A 2
E41-HPSEH-1
.B-14/05 MECH SNUBBER A
N/A 2
E41-HPSEH 700 B 15/05 MECH SNUBBER A.
-N/A 2
.E41-NPSEH 702
..B-16/05 MECH SNUBBER A
N/A 2'
E11-RHRH-725 B-20/05 MECH SNUBBER-A N/A 2
E11-RNRN-729
-B-22/05 MECH SNUBBER A
.N/A 2
E51-RCSEH-715 B-24/05
' MECH SNUBBER
.A N/A -E51-RCSEH 719 B-24/05' MECH SNUBBER-A N/A 2
E51-RCSEH-720 :
B-24/05 MECH SNUBBER A
N/A 2'
E51-RCSEH-721
~ B-25/05 -
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REMARKS 2
T48-CPH-702 B-26/05 MECH SNUBBER A
N/A 2-T48-CPM-6 B-28/05 MECH SNUBBER A
N/A 2
E11 RHRH-312 B 34/04 MECH SNUBBER A-N/A 2
E11-RHRH 313 B-34/04 MECH SNUBBER A
N/A 2~
E11-RNRH-310 6-35/04
. MECH SNUBBER A
N/A 2-E11-RHRH-709 ~
B-36/05
. MECH SNUBBER A
N/A 2
E11-RHRM-711 B-36/05 MECH SNUBBER A
N/A
'2 E11-RHFP 316 B-37/04
' MECH SNUBBER
'A N/A 2
E11-RHRM-719 B-37/04 MECH SNUBBER A
N/A 2
-E11 RHRM-324 B-38/05 MECH SNUBBER A
N/A t
2-E11*RHRH-325 B-38/05
' MECH SNUBBER
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-E11-RHRH 188 B-39/05 MECH SNUBBER A
N/A 2'
E11 RHRM-189 B-39/05 MECH $NUBBER A
N/A 2
E11 RHRH+1.99 B-40/04 MECH SNUBBER
'A.
N/A 2
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N/A 2
E11 RNRM-193 B-41/06 MECH SNUBBER A
N/A
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N/A 2
E11 RHRN-716
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N/A 2
E11-RHRM 223
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N/A-
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N/A 2
E11-RHRM-221 B-49/05-
' MECH SNUBBER A
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N/A 2
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N/A 2
E11-RHRH-211 B-54/04 MECH SNUBBER A
N/A' 2
E11-RHRM-728 B-57/05 MECH SNUBBER A
N/A 2
E11-RHRH-34 B-58/05 MECM SNUBBER
~A N/A 2
E11 RHRM 252 B-61/05-MECH SNUBBER A
N/A 2-E11-RHRH-733 B 67/05 MECH SNUBBER A
N/A 2'
E11-RHRM-730 B-67/05 MECH SNUBBER A
N/A 2
E11-RHRM-732
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MECH SNUBBER A
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E11-RHRM-734 B-73/06
-MECH SNUBBER A
N/A 2
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N/A
'2' E11-RNRH-735 B-73/06 MECH SNUBBER A.
N/A 2.
E51-RCICH 700 B-89/06 MECH SNUBBER A
N/A 2
E51-RCICH-701-B 89/06 MECH SNUBBER A
N/A 2
E51-RCSEH-701 B-95/02.
MECH SNUBBER
- A
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-MECH SNUBBER A
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E51-RCSEH-703-B-95/02
' MECH SNUBBER A
N/A 2
E51-RCSEH-704 B-96/01 MECH SNUBBER A
N/A-2
.E51-RCSEH-705 B 96/01 MECH SNUBEER.
A N/A 2..
E51 RCSEH 707 B 96/01 MECH SNUBBER A
N/A 2
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REMARKS-2
~E51-RCSEH 711 B-96/01.
MECH SNUBBER A
N/A 2
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE AUGMENTED EXAMINATIONS ASME EXAM EXAMlNATION CAL EXAM / CAL SECTION XI FIGURE NO.
EVAMINATION/ AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS REACTOR WATER CLEAN-UP SYSTEM C-116/01 1G31-3RWCU 4 R-22 UT-H-400/11 145-H
$93H1C166 N/A UT CAL ELBOW TO PIPE 593H1U331 NRI NUREG-0313S
$93H10332 NRI
$93H1C167 N/A UT CAL S93H1U333 N/A THICKNESS C-117/01 1G31-3RVCU-4 R-25 UT-H-400/11 145-H S93H1U246 RI ROOT GECNETRY PIPE TO ELBOW
$93H1C220 N/A UT CAL NUREG-03135 S93H1U249 NRI S93 HIC 223 N/A UT CAL 593H1U134 N/A THICKNESS C-117/01 1G31-3RWCU-4 R-26 UT-H-400/11-145-H S93H1U172 R1 GEOMETRY ELBCJ TO PIPE S93H1C106 N/A UT CAL
+-
WIEG-0313S 593H10173 NRI S93H1C107 N/A UT CAL 593H1U133 N/A THICKNESS C 117/01 1G31-3RWCU-4-R-33 UT-H-400/11 145-H 593H10247 NRI ELBOW TO PIPE-593H1C221 N/A UT CAL NtKEG-0313S
$93H1U250 NRI S93H1C224 N/A UT CAL 593H1U132 N/A THICKNESS C-117/01 1G31-3RWCU-4 R-34 UT-H-400/11 145-H
$93H1U248 NRI PIPE TO ELBCW 593H1C222 N/A UT CAL l'UREG-0313S
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- + -
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.v-E.I. HATCH UNIT 1 SPRING 1993 REFUEllNG OUTAGE IN VE$$EL VISUAL EXAMINATIONS ASME EXAM EXAMINATION CAL EXAM / CAL
'SECTION XI -FIGURE NO.
EXAMINATION / AREA PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS M-30 VT-H 750/05 593H1W121 SAT C.S. LOWER SPRGR JUNCTION BOX D NUREG CR-4523 70 Noz 530 - 190-270 DEG
+ -
M-4 VT-H-750/05 593H1V122 SAT JUNCTION BOX B REPAIR CLAMP NU;;EG CR-4523
.N-1A VT-H 750/05 593H1V126 SAT 90 DG CORE SPRY S PP HEADER-NUREG CR-4523 SHROUD TO LOWER ELBOW 1 9 10 DEG
-d N-1B VT-H 750/05 593H1V127 SAT 90 DG CORE SPRY S-PP LOWER ELBOW NUREG CR-4523
'2 0 10 DEG N 1C
.VT-H-750/05 593H1V128 SAT 90 DG CORE SPRY S-PP VERT RUN-
- e NUREG CR-4523' LWR ELBOW TO CPLG 3 9 10 DEG W.
VT-H-750/05
$93Hiv129 SAT 2
.90 DG CORE SPRY S-PP COUPLING 4 NUREG CR-4523 9 10 DEG
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' NU;EEG CR-4523 COUPLING TO UP EiB_5 9 10 DEG -
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.VT H-750/05' 593H1v131 SAT 90 DG CORE SPRY S PP UPPER ELBOW'
- NUREG CR-4523 6 9 10 DEG '
N-1G-VT H-750/05 593H1V132 SAT 90 DG CORE SPRY S-PP HORIZ 3EC-
. NUREG CR*4523 UPPER ELB.TO BRCKT 7 9 30 DEG
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' EXAMINATION / AREA PROCEDURE BLOCK
$NEET NO.
PESULTS REMARKS N'1H VT-H 750/05 S93H1V133 SAT 90 DG CORE SPRY S PP BRACKET AT
- NtAE? ;R'4523 30 DEG 9 8' B13.21 N-11.
VT H-750/05 593HiV134 SAT B-N-2 90 DG CORE SPRY S-PP BRACKET ASME ATTACHMENT WELDS - 30 DEG BRACK r
N-1J-VT H 750/05 -
S93HIV135 SAT 90 OG CORE SPRY S-PP MORIZ SEC-NU2EG CR-4523 BRACKET TO JUNC BOX 9 9 30 DE' N-1K--
VT H-750/05 593H1V136 SAT 90 DG CORE SPRY S-PP JUNCTION
'EUREG CR 4523 BOX 10 9 90 DEG -
N+1L VT H-750/05 593H1V137 SAT 90 DG CORE SPRY S*PP MORIZ SEC-CUREG CR-4523 JUNC BOX TO BRCKT 12 a 150 DE N'1M VT-H-750/05 593H1V138 SAT 90 DG CORE SPRY 5-PP BRACKET 13 '
CUREG CR-4523 a 150 DEG N-1N-VT-H-750/05 593H1V139
' SAT B13.21 B-N-2 9G OG CORE SPRY S-PP BRACKET ASME ATTACHMENT WELDS 150 DEG N-10 VT
- H-750/05
$93H1v140 SAT 90 DG CORE SPRY S-PP HORIZ SEC*
NWEG CR 4523 BRCKT TO UP ELBOW 14 9 150 DE :
N-1P
-VT-H 750/05 '
593H1V141 SAT
- + -
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90 DG CORE SPRY.S PP UPPER ELBOW
.NUREG CR-4523 15 9 170 DEG 373 x.
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E.I. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE IN* VESSEL VISUAL EXAMINATIONS
- ASME'
' EXAM EXAMINATION CAL-EXAM / CAL SECTION XI. FIGURE NO.
EXAMINATION / AREA PROCEDURE BLO K SHEET No.
RESULTS REMARKS N-10 VT-H-750/05
$93H1V142 SAT
- -1 90 DG CORE SPRY S PP VERT RUN -
.NU%EG CR*4523-
.UP ELBOW TO CCUP 16 0 170 DE-N 1R VT-N-750/05 593HIV143 SAT 90 DG CORE SPRY S PP COUPLING 17 NUREG CR*4523 a 170 DEGREES N-1S VT-H-750/05 593H1v144 SAT 90 DG CORE SFRY S-PP VERT RUN-EUREG CR-4523 COUP 10 LOW ELBOW 18 9 170 DEG N-1T.
VT*H 750/05
$93H1V145
$AT 90 DG CORE SPRY S-PP LOWER ELBOW NUREG CR-4523..
19 9170 DEG.
La -
N-1U -
VT-H-750/05 593H1V146 SAT
.90 DG CORE SPRY S PP HEADER-LOW NUPEG CR-4523 ELBOW TO SHROUD 20 G_170 DEG N-1V
'VT-H 750/05 393H1V147 SAT
-4 90 DG CORE SPRY S-PP S-PIPE
'CUREG CR-4523
' JUNCTION BOX TO NO2 11 a 150 DEG N-2A VT.H-750/05
$93H1V148.
. SAT 270 DEG CORE SPRAY S PP HDR -
a NUREG CR-4523 SHROUD TO LWR ELB 1 0 190 DEG N-28 VT N-750/05 593H1v149-SAT '
' 270 DEG CORE SPRAY S* PIPE LOWER RUREG CR-4523 ELBOW 2 9190 DEG S PIPE N-2C-VT-H-750/05 593H1V150 SAT
.-270 DEG CORE SPRAY S-PP VERT >
- NU;EG CR-4523 RUN-LOW ELB TO COUP.3 9 190 DG
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'593H1V151
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' COUPLING 4 Q 190 DEG 88:
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E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE IN-VESSEL VISUAL EXAMINATIONS ASME
. EXAM EXAMINATION ~
CAL EXAM / CAL SECTION XI FIGURE NO.
EXAMINATION / AREA -
PROCEDURE BLOCK SHEET NO.
RESULTS REMARKS N-2E VT-H 750/05' 593HIV152 SAT 270 DEG CORE SPRAY S-PP VERT
- +
. NUREG CR-4523 COUPLING TO UP ELB 5 9 190 DEG N-2F' VT-H-750/05 S93H1V153 SAT
'270 DEG CORE SPRAY S-P!PE UPPER NUREG CR-4523 ELBOW 6 9 190 DEG Na2G.
VT H-750/05
$93H1V154 SAT 270 DEG CORE SPRAY S-PP HORIZ MAEG CR-4523 SC-UP ELB 10 BRCKT 7 9 210 DG N 2H ;
VT-H 750/05 593H1V155 SAT
- 270 DEG CORE SPRAY S-PP BRACKET NU%EG CR-4523 AT 210 DEG
.N-21 VT-H-750/05 593H1V156 SAT B13.20 B-2-2 270 DEG CORE SPRAY S-PP BRACKET ASME ATTACHMENT WELDS 9 210 DEG N-2J
-VT-H-750/05
$93H1V157 SAT a
- 270 DEG CORE SPRAY S-PP HORIZ NU%EG CR-4523 SC-BRCKT TO JNC BX 9 9 210 DG N-2K VT-H 750/05 S93H1V158 SAT 270 DEG CORE SPRAY S-PP JUNCTION NUREG CR-4523 BOX 10 Q 270 DEG N*2L
.VT-H-750/05-S93H1V159 SAT 270 DEG CORE SPRAY S-PP HORIZ NU%EG CR-4523 SEO-JNC BX TO BRCKT.12 9 330 -
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.VT-N-750/05.
.S93H1V160 SAT NU1EG CR-4523.
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RESULTS REMARKS
'ASME ATTACHMENT WELDS a 330 DEG N-20 VT-H-750/05 593H1V162 SAT
- 270 DEG CORE SPRAY S-PP HORIZ
+-
NUREG CR-4523
.SC-BRCKT TO UP ELB 149 330 DG N 2P VT-H-750/05 S93H1V163 SAT
-+
270 DEG CORE SPRAY S-PP UPPER NUREG CR-4523 ELBOW 15 a 330 DEG N-2Q VT -H-750/05 593HIV164 SAT 270 DEG CORE SPRAY S-PP VERT NUREG CR-4523 RUN-UP ELB TO COUP 16 G 350 DG N-2R VT-H-750/05 593H1V165 SAT 270 DEG CORE SPRAY S PIPE NUREG CR-4523 J. COUPLING 17 E 350 DEG.
N-2S VT-H-750/05
$93H1v166 SAT 270 DEG CORE SPRAY S PP VERT NUREG CR 4523
.RUN-COUP TO LOW ELB 18 a 350 0l N-2T vi-N-750/05
$93H1V167 SAT 270 DEG CORE SPRAY S-PIPE LOWER NUREG CR-4523 ELBOW 19 a 350 DEG N - 2U -
VT-H 750/05 593H1V168 SAT 270 DEG CORE SPRAY 5-PP HDR -
NUREG CR-4523 LWR ELB TO SHROUD 20 a 350 DG N 2V VT H-750/05 593H1v169:
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. BOX TO NOZ 11 a 330 DEG 0-3E VT-H 750/05 593H1V172 SAT FEEDWATER NOZZLE INNER RADIUS 9 225 DEG INNER RADIUS a 225 D
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Q E.1. HATCH UNIT 1 SPRING 1993 REFUELING OUTAGE IN VESSEL VISUAL EXAMINATIONS
'ASME EXAM' EXAMINATION CAL EXAM / CAL SECTION XI FIGURE NO.'
- EXAM!hATION/ AREA' PROCEDURE BLOCK SMEET No.
RESULTS REMARKS
.0-4E VT H-750/05 593H1V1' SAT FEEDWATER N0ZZLE INNER RADIUS 9
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315 DEG INNER RADIUS G 315 0 P-1 VT-H-750/05 593H1v123 SAT 813.21' B N-2
'CRD STUB TUBES ASME' P-3 VT*H-750/05 593H1V125 SAT Examined area made 813.21 B-N-2 SHROUD SUPPORT WELD FROM BELOW accessible during O' ASME CORE and 180' access hole cover reptscement.
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SUMMARY
1 OF CLASS 1 AND 2-
~
3 REPAI.RS AND REPLACEMENTS' i
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REPAIRS AND REPLACEMENTS 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 / replacement activities for each cycle.
The following tables provide an itemized list of those components which were included in the ASME Section XI Repair and Replacement Program.
Copies of the individual Repair / Replacement evaluation sheets are filed with the MWO Packages and are available for review at the site.
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93
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ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT
SUMMARY
'MPL NUMBER
- CMSS, DESCRIPTION OF PROBLEM SUITABILITY OF REPAIR / REPLACEMENT MWO/DCR CODE NDE PRESSURE TEST 1P41-F052 2
VALVE BODY HAS PITS IN THE VALVE BODY BEING USED HAS BEEN APPROVED BY 1-91-6790 SURFACE HYDROSTATIC VALVE IT.AND MUST BE REPLACED.
DEDICATION UPGRADE. REPAIRS WILL BE MADE PER PROCEDURE AND INSPECTIONS PERFORMED PER SECTION XI.
HANGER AND $NUBBER ARE THIS PROBLEM 15 INSTALLAil0N RELATED AND IS 1-91-7235 VT-3 N/A HANGER / SNUBBER OUT OF ADJUSTMENT.
NOT ATTRIBUTABLE 10 SERVICE INDUCED DEGRADATION REV. 2 OR FAILURE. PROPOSED REPAIR IS ACCEPTABLE.
CHECK VALVE STICKS OPEN.
REPLACEMENT OF SPRING WILL INSURE VALVE OPERATES 1-92-584 N/A MWO FUNCTIONAL CHECK VALVE PROPERLY, AND IS A SUITABLE METHOD OF REPAIR.
TEST 1-E11-F031B 2
DISC HAS SEPARATED FROM DISC REPLACEMENT WILL BE WITH LIKE IN KIND DISC.
1 92-1466 N/A MWO FUNCTIONAL CHECK VALVE HINGE P!NS. REPLACE WITH CAUSE OF FAILURE WAS SEPARATION FROM HINGE PINS REY. 1 TEST NEW DISC.
RETAINING NUT CAME LOCSE. NOT KNOWN AT THIS TIME AS.TO WHY THIS HAPPENED.
DISC HAS A LINEAR DISC WILL BE REPLACED WITH IDENTICAL COMPONENT.
1-92-1744 N/A OPERATING 4" POPPET INDICATION RUNMING ALONG ALL WORK IS IN ACCORDANCE WITH APPLICABLE ASME Rev. 3 PRESSURE TEST (DISC, GLOBE TYPE)
THE PATH OF STEM TRAVEL.
CODE AND PLANT PROCEDURES. THIS IS A SUITABLE INDICATION IS TCO LARGE METHOD OF REPAIR. CAUSE OF FAILURE IS UNKNOWN.
FOR REMOVAL.
REPLACE THE DISC, SEAT REPLACEMENT OF THESE PARTS WILL ENSURE VALVE TO 1-92 2199 N/A MWO FUNCTIONAL GLOBE STOP CHECK RING, GASKET AND PACKING OPERATE PROPERLY.
Rev. 1 TEST DUE TO NORMAL WEAR.
'2-1Eil F0258 RELIEF VALVE OLD VALVE HAS DEGRADED OVER TIME DUE TO MAINTENANCE 1 92-4715 SURFACE HYDROSTATIC LPCI LOOP WILL BE REMOVED AND ACTIVITIES (SPECIFICALLY IN SEAT AREA). REPLACEMENT
~ RELIEF VALVE
' REPLACED WITH 3 NEW VALVE.
IS IN ACCORDANCE WITH APPLICABLE CODES AND PROCEDURES.
VALVE WILL BE WELDED TO EXISTING PIPE.
1E21 F032A.
2 MINOR BLEMISHES ON DISC REPLACEMENT OF THE BLEMISHED DISC IS SUITABLE 1-92-4728 N/A MWO FUNCTIONAL RELIEF VALVE SEATING SURFACE IS BECAUSE IT-IS AN EXACT REPLACEMENT, AND IT WILL TEST PRECLUDING SUCCESSFUL ALLOW SUCCESSFUL TESTING OF THIS VALVE.
TESTING OF THl$ VALVE.
1E41 F022 2
REPLACEMENT OF A 2" VELAN PER DCR YOGT VALVE IS AN ACCEPTABLE REPLACEMENT.
1-92-6698 SURFACE OPERATING-VALVE CHECK VALVE WITH A V0GT P!PE REPLACEMENT IS TO FACILITATE REPAIR AND IS Rev. 2 PRESSURE TEST 2". MACHINING OF VALVE ACCEPTABLE. IT'IS PER CONSTRUCTION CODE AND WILL DOWNSTREAM; DISC REVEALED INHERENT BE INSPECTED PER ASME XI CLASS II.
HYDROSTATIC VO!D IN MATERIAL. NO UPSTREAM REPLACEMENT AVAILABLE.
.2 REPLACE DISC AND NUT.
REPLACEMENT PARTS ARE IDENTICAL TO ORIGINAL PARTS.
1-92-6701 N/A MWO FUNCTIONAL VALVE DISC'HAS MINOR PITTING.
CAUSE OF FAILURE APPEARS TO BE NORMAL FOR TH19 TYPE
-REV. 1 TEST INSTALLATION.
94
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O ATTACHMENT TO THE OWNER'S DATA REPORT REPATR AND REPLACEMENT
SUMMARY
ASME MPL NUMBER CLASS DESCRIPTION OF PROBLEM SUITABILITY OF REPAIP/ REPLACEMENT MWO/DCR CODE NDE PRESSURE TEST 1921-55-1 1
' REMOVE AND FUNCTIONAL TEST SNUBBER FAILED FUNCTIONAL TEST AND WAS REPLACED WITH 1-92 6776 VT-3 N/A S%UBBER SNUBBER. IF SNUBBER FAILS A REBUILT SNUBBER FROM STOCK. CAUSE OF FAILURE IS FT THEN REPLACE WITH NEW UNKNOWN AT THIS TIME.
REPLACE THE WEDGE GATE THE REPLACEMENT WEDGE GATE IS SUITABLE BECAUSE IT 1-92-6869 N/A MWO FUNCTIONAL VALVE IN VALVE-1E11-F088 DUE TO MATCHES THE ORIGINAL CLASSIFICAfl0N FOR ASME 111 TEST NORMAL SERVICE WEAR.
CLASS !! AND THE WEAR IS CONSIDERED NORMAL FOR THIS TYPE SERVICE.
1931-F023A/B 1
REMOVE THE BONNET VENT SEALING BONNET PORTS OF THESE VALVES WITH TAPER 1-93-33 SURFACE PRESSURE TEST
' 1931-F031A/B LINES AND PLUG WITH TAPER.
PLUGS AND SEAL WELDS IS AN APPROVED METHOD OF 1N92 076 DURING VESSEL VALVES PLUGS PER DCR 1H92-076.
REPLACEMENT OF THESE VENT LINES. REMOVAL OF PRESSURE TEST PIPING IS TO PREVENT FORCED OUTAGES DUE TO
~ CRACKING OF PIPING DUE TO IGSCC.
INSTALL NEW HPCI TEST THIS REPLACEMENT IS BEING PERFORMED UNDER AN 1-93-252 SURFACE HYDROSTATIC' VALVE VALVE TO CST AND RELOCATE APPROVED DESIGN CHANGE REQUEST FOR IMPROVEMENT VOLUMETRIC 1E51 LINE.-
0F SYSTEM OPERATION. SUITABILITY EVALUATION IS VISUAL COVERED BY THIS DCR.
REPLACE VELAN STOP CHECK V0GT VALVE HAS BEEN APPROVED AS A SUITABLE 1-93-418 SURFACE OPERATING YALVE VALVE WITH V0GT.STOP REPLACEMENT ON GENERIC DCR 88-251. REPLACEMENT REY. 1 PRESSURE TEST CHECK VALVE.
-IS IN ACCORDANCE WITH PLANT PROCEDURES AND 88-251 APPLICABLE CODES.
ROTATE 1E41-F001 VALVE VALVE IS BEING ROTATED PER AN APPROVED DESIGN 1-93-441 SURFACE HYDROSTATIC VALVE 50 THAT THE OPERATOR IS CHANGE REQUEST. NO INSERVICE FAILURE INVOLVED.
REV.1 VOLUMETRIC IN THE VERTICAL POSITION.
VT 2 1E41 2
LINEAR INDICAT]ON FOUND REPAIR METHOD IS THE NORMAL METHOD OF REPATRING 1-93-441 SURFACE HYDROSTATIC P!PE DURING WELD PREP PT.
1 BASE METAL DEFECTS. APPROVED WELDERS AND WELD VOLUMETRIC INDICATION WILL BE GROUND PROCEDURES ARE BEING USED. CAUSE OF INDICATION VT*2 OUT AND REPLACED WITH IS NOT KNOWN. WELD HAS NOT BEEN EXAMINED THIS WELD METAL.
10 YR. INTERVAL.
r 1E11 2
REMOVE PIPING, VALVES, PIPING IS BEING REMOVED PER. APPROVED DESIGN 1-93-451 SURFACE HYDROSTATIC
- VALVES, AND SUPPORTS AS DESCRIBED.
CHANGE REQUEST. NO SERVICE INDUCED FAILURE INVOLVED.
1H92-007 VOLUMETRIC AND OPERATING PIPING,'
HEAD SPRAY PIPE IS NO LONGER USED.
VT-2 PRESSURE TEST AND SUPPORTS 1531-C001A 1
.INDICAil0N FOUND IN WELD.
-REMOVAL OF INDICATIONS FROM WELD JOINTS AND REWELDING 1-93-774 SURFACE OPERATING f;ECIKC SEAL GRIND OUT AND INDICATION IS A NORMAL METHOD OF REPAIR. CAUSE OF INDICATION REY. 1 PRESSURE TEST VE%T-AND REPAIR.
IS NOT KNOWN AT THIS TIME.
DURING RECIRC-PUMP RUN.
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ATTACHMENT TO THE OWNER'S DATA REPORT REPAIR AND REPLACEMENT
SUMMARY
4 ASME MPL M **0ER.
CLASS DESCRIPTION OF PROBLEM
-SUITABILITY OF REPAIR / REPLACEMENT MWO/DCR CODE NDE PRESSURE TEST B114001 1
REMOVE EXISTINC ACCESS REPLACEMENT OF HOLE COVER IS BEING PERFORMED UNDER 1-93-1252 VT-3 N/A ACCESS HOLE HOLE COVERS AND REPLACE AN APPROVED DESIGN CHANGE REQUEST. SUITABILITY OF COVER WITH BOLTED COVERS.
THIS REPLACEMENT IS COVERED UNDER THIS DCR.
I REPLACEMENT IS BEING DONE TO PREVENT AND ELIMINATE IGSCC.
.+
CLAMP IS OUT OF CLAMP IS BEING ALIGNED BY SKILL OF THE CRAFT. CAUSE 1-93-1319 VT-3 N/A I
PIPE CLAMP ALIGNMENT WITH SNUBBER.
OF FAILURE APPEARS TO BE CAUSED BY PIPE MOVEMENT REALIGN AND CLAMP.
DURING OPERATION.
1E41 F003 1
REPLACE VALVE WEDGE.
ORIGINAL WEDGE HAD INDICAil0NS IN HARD SURFACING 1-93-1324 N/A PRESSURE TEST -
VALVE ON SEAT. INDICATIONS WERE INDUCED BY SERVICE DURING VESSEL CONDITIONS. NEW WEDGE IS FREE OF. INDICATIONS AND PRESSURE TEST IS A SUITABLE REPLACEMENT.
1821 N11B'
.i REPLACE COUPLING ON-COUPLING IS BEING REPLACED UNDER APPROVED PLANT 1-93-1481 SURFACE WILL BE PIPING SENSING LINE FROM PROCEDURES. CAUSE OF FAILURE WAS IGSCC.
REV. 1 VT-3 INSPECTED VESSEL. WELD HAS P!N DURING VESSEL HOLE LEAK AT COUPLING.
PRESSURE TEST' 1E11-RHRSW PIPE 2
WELD HALF COUPLING THIS WORK IS BEING PERFORMED UNDER AN APPROVED 1 93-2978 SURFACE HYDROSTATIC TO 10" LINE 10 DCR.' SUITABILITY IS ADDRESSED VIA THE DCR 1H91-173.
1H91 173 VT-2 FACILITATE YENT LINE NO SERVICE INDUCED FAILURE INVOLVED.
1 INSTALLATION.
I 1831 1
REPLACE EXISTING THE NEW SNUBBERS ARE MORE RELIABLE. SPARE PARTS 1-90-2736 VISUAL N/A SNUBBERS SNUBBERS WITH NEW REQUIREMENTS ARE LESS.
1821-109-H010 1
SNUBBER FAILED THE DRAG REPAIR OF HYDRAULIC SNUBBERS IS PERFORMED USING 1-91-6217 VT-4 N/A SNUBBER.
TEST. REMOVE AND REBUILD.
A CONTROLED REPAIR PROGRAM. CAUSE OF FAILURE IS NORMAL WEAR OF PARTS.
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