ML20235G928
| ML20235G928 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/22/1987 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20235G915 | List: |
| References | |
| NUDOCS 8709300293 | |
| Download: ML20235G928 (149) | |
Text
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, OWNER'S DATA REPORT e
FOR INSERVICE INSPECTION l
EDWIN I. HATCil NUCLEAR PLANT l
UNIT 1 O
MARCH 1987 - JUNE 1987 m
O B709300293 870922 i PDR ADOCK 050 1 G
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TABLE OF CONTENTS PAGES I. ASME NIS-1 FORM AND SUPPLEMENTARY INFORMATION 1-7 II. ABSTRACT 8 I-III.. EXAMINATION
SUMMARY
A. CLASS 1 WELDS AND COMPONENTS 15-54 B. CLASS 1 YALVE INTERNALS 55-56 C. CONTAINMENT LINER PENETRATION WELDS 57-62 D. CLASS 1 EXAMINATION FIGURES 63-87 E. CLASS 2 WELOS 88-94 F. CLASS 2 EXAMINATION FIGURES95-121 G. PRESSURE TESTING. 122-123 H. COMPONENT SUPPORTS 124-139 J. REACTOR PRESSURE VESSEL INTERNALS 140-142 K. REPAIRS AND REPLACEMENTS 143-144 u
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HOTE: Portions of this report are compiled from Southern Company Services issued report; " Nondestructive Examination Of Selected Class 1, 2, and 3 Components", for the Spring 1987 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 Inspectort _
ASME" American Society of Mechanical Engineers ASNT American Society' for' Nondestructive Testing
.BC Branch Connection BWR- Boiling Water Reactor CH Closure Head
' CONT Containment CPI Containment Purge and Inerting System CRD Control Rod Drive System CS Core Spray System
- CV Clean-up C8L Cramer'and'Lindell Engineers DCR Design Change Request _i ET' Eddy. Current Examination-
': EPRI Electric Power Research Institute FB Flange Bolting O FeC Fuei eool Coo,ing System FW Feedwater System GE General Electric GPC ' Georgia Power Company HL Hanger Lug j HPCI High Pressure Coolant Injection System INF Indication Notification Form IGSCC Intergranular Stress Corrosion Cracking ISI Inservice Inspection ITL International Testing Laboratories LD Longitudinal Seam Weld Extending Downstream LD-I Longitudinal Weld Downstream on Inside of Elbow LD-0 Longitudinal Weld Downstream on Outside of Elbow LitT - Lambert, MacGi'll, and Thomas, Inc.
Lo Zeru Reference Location LU Longitudinal Seam Weld Extending Upstream lL LU-I' Longitudinal Weld Upstream on Inside of Elbow O to-0 Longitudinal Weld Upstream on Outside of Elbow n
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MSIV. flain Steam Isolation Valve MS Mein Steam System q MSA fiain Steam Auxiliary System b KT Magnetic Particle Examination 1 MWO fiaintenance Work Order NDE Nondestructive Examination NI No Indication NRC Nuclear Regulatory Commission NRI No Recordable Indication OL Overlay PL Pipe Lug PLT Plant PR Pipe Restraint PROD Product PS Pipe Support PSW Plant. Service Water System PT Liquid Penetrant Examination QC Georgia Power Company Quality Control RC Reactor Recirculation System e RCIC Reactor Core Isolation Cooling System RHR Residual Heat Removal System RI Recordable Indication RINTSA Recirculation Inlet Nozzle Thennal Sleeve Attachment Welds RL Refracted Longitudinal RL Restraint Lug RPV Reactor Pressure Vessel RX Reactor RWCU Reactor Water Cleanup System SCS Southern Company Services SER Service SRV Safety Relief Valve TDP Torus Drainage and Purification System TSB Turbine Steam Bypass System UT Ultrasonic Examination VLV Valve VT Visual Examination This list is comprised of standard abbreviations used in Inservice Inspection Documentation. All of these abbreviations may not appear in this report.
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TOTAL NUMBER OF SHEETS /#
FORM NIS-1 7_y FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As Required By the Provisions Of The ASf1E Codes Rules
- 2. Plant Edwin I. Hatch Nuclear Plant, Route 1, Box 278, Baxley, 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 N/A
- 7. Components Inspected:
Component or Manufacturer State or Appurtenance Manufacturer or Installer Province National or System or Installer Serial No. Number Board No.
====== ============ ============ ======== ===
Rx. Pressure Vessel Combustion Eng. 67105 N/A 20769 Rx. Pressure Vessel Combustion Eng. 67205 N/A 20769 1821 Main Steam Pullman Power Prod, N/A 1821 Feedwater Pullman Power Prod. N/A O 1821 M.S. Relief Pullman Power Prod.
- N/A
- 1B31 Rx. Recirc Pullman Power Prod. N/A j Byron Jackson
- 1831 Recirc Pump N/A 1C11 CRD Pullman Power Prod. N/A 1C41 SBLC Pullman Power Prod. N/A 1 Ell RHR Pullman Power Prod. N/A lE21 Core Spray Pullman Power Prod. N/A 1E41 HPCI Pullman Power Prod. N/A lE51 RCIC Pullman Power Prod. 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 of fitting numbers too numerous to list for each specific system. Material certifications for all piping, fittings, etc. , are available for review in the Records Management Department at the plant site.
T'T U ** Exception taken to note 2.
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- 7. Components Inspected (continued):
l Component or Manufacturer State or l-r3 Appurtenance Manufacturer or Installer Province National l b or System . or Installer Serial No. Number Board No. q maman======= ============ ============ ======== ========u q l
1G31 RWCU Pullman Power Prod. N/A {
- l 1G41 FPC & CU Pullman Power Prod. N/A 1
1N11 M S Auxiliary Pullman Power Prod. N/A 1N37 Turbine Bypass Pullman Power Prod. N/A
- l 1P41 Plt Serv Water Pullman Power Prod. N/A 1T48 Cont. Purge Pullman Power Prod. N/A 1
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- - Spool piece of fitting numbers too numerous to list for each specific l system. Material certifications for all piping, fittings, etc. , are i available for review in the Records Management Department at the plant site. j l
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FORM NIS_1 (Back)
- 8. Examination Dates 03/31/87 to 06/25/87 .
t V 9. Inspection Interval from 01/86 to 01 /96
- 10. Abstract of Examinations. Include a list of examinations ** and a statement concerning status of work required for current interval.
- 11. Abstract of Conditions Noted. **
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- 12. Abstract of Corrective tkasures Recontended and Taken.
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.
Date 5+ d Pt 19W Signed Georgia Power Company 32_o owner Certificate of Authorization No. (if applicable) N/A Expiration Date N/A i
CERTIFICATE OF INSERVICE INSPECTION l l
I I, the undersigned, holding a valid comission issued by the National Board i
/ of Boiler and Pressure Vessel Inspectors and/or the State or Province of I f3 GA. and employed by *** of Hartford, CT have inspected the l t,"j l l components described in this Owners' Data Report during the period 03/87 l l to 06/87 and state that to the best of my knowledge and belief, the Owner l l has performed examinations and taken corrective measures described in this l 1
Owners' Data Report in accordance with the requirements of the ASME Code, l Section XI. I I I l By signing this certificate neither the Inspector nor his employer makes anyl I warranty, expressed or implied, concerning the examinations and corrective l l measures described in this Owners' Data Report. Furthermore, neither the l I Inspector nor his employer shall be liable in any manner for any personal l l injury or property damage or a loss of any kind arising from or connected I with this inspection.
I I l Date , 9//Y 1997 1
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- //)] Comissions Georgia - 201 l InWecto'r'ySiljn ure National Board, State, Province, & No.I
- The following NIS-1 Form supplementary infonnation and report includes the responses to HIS questions #10, #11, and #12.
- Hartford Steam Boiler Inspection and Insurance Company.
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14 NIS-1 Form Supplementary Information Owner's Data Report m for b) Date: September 11, 1987 Inservice Inspection Owner Name & Address: Georgia Power Company 333 Piedmont Avenue, N.E.
P.O. Box 4545 i Atlanta, Georgia 30302 Name & Address of Nuclear Generating Plant:
Edwin I. Hatch Nuclear Plant Route 1, Box 278 Baxley, Georgia 31513 Name Assigned to Nuclear Plant Station:
Edwin I. Hatch Nuclear Plant Unit 1 Commercial Service Date: December 31, 1975 Gross Generating Capability:
2436 f1Wt, 813 tiWe State, Province, or Municipality Assigned Number:
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N/A National Board Number Assigned by Manufacturer:
N/A Name of Component or Part of Component ISI Involved: I Representative samples of the following components and areas were examined with nondestructive testing techniques.
Class 1 Reactor Pressure Vessel Reactor Pressure Vessel Closure Head Main Steam Piping System Feedwater Piping System Residual Heat Removal System Control Rod Drive System Reactor Recirculation System f, Core Spray System Reactor Water Cleanup System Containment Penetration Welds Valve Internal Surfaces 4
Class 2 RHR System Core Spray System p'
'v HPCI System RCIC System Control Rod Drive System Containment Purge and Inerting System ;
Reactor Water Cleanup System Main Steam Piping System Turbine Steam Bypass Piping System Hydrostatic Testing Class 2 Residual Heat Removal System (ISI Hydro lEll-PT-18 and 1 Ell-PT-19)
Class 3 Standby Liquid Control System (ISI Hydro 1041-PT-1 and 1C41-PT-3) f, System Pressure / Leakage Tests d ,
System Class Test Required Reactor Pressure Vessel and 1 Leakage Associated Piping and Components Pipe Support & Hanger Examination Class 1 Main Steam System Residual Heat Removal System Core Spray System High Pressure Coolant Injection System l
Class 2 Core Spray System '
High Pressure Coolant Injection System Residual Heat Removal System Containment Purge System
I Class 3 Main Steam Safety / Relief Valve Discharge System p RHR Service Water System-O Core Spray System l Plant Service Water System Fuel Pool Cooling System Name & Address of Manufacturer of Components:
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- 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 Williamsport, PA
- b. General Electric Company San Jose, CA Note: Piping purchased by General Electric and Pullman and installed by Pullman. Material certifications and manufacturer information are available for review in the Records Management Department at the Hatch Plant Site.
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() 3. Piping Supports and Hangers (Classes 1, 2, and 3)
- a. 3ergen-Paterson Pipe Support Corporation Laconia, NH
- b. ITT Grinnell Corporation Providence, Rhode Island
- c. Pacific Scientific Anaheim, CA
- 4. Valves, Pumps, and Heat Exchangers
- a. Byron-Jackson, Inc.
Los Angeles, CA
- b. Crane New York, NY
- c. Wm. Powell Company Cincinnati, OH
- d. General Electric San Jose, CA O
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' DateTof-Inse'rvice Insptction:' ,
' March 1987 - June ~1987 l: Completion Date of Inservice Inspection:
June 25, 1987.-
.Name of Inspector: Charles-F. Toegel, Jr. ( ANI/ANII)-
c Name &-Mailing Address of Inspector's Employer:
The Hartford Steam Boiler Inspection and' Insurance Company-1117: Perimeter Center West Suite E 301 Atlanta, Georgia 30338 1
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ABSTRACT An Inservice Inspection of selected Class 1, 2, and 3 components of Georgia Power Company's Edwin I. Hatch Nuclear Plant Unit 1 was performed during the Spring 1987 flaintenance/ Refueling Outage. The components were examined in accordance with the applicable outage plan, including any changes made during the ISI as approved by Georgia Power Company.
The nondestructive examinations were performed using VT, PT, MT, AND UT examination techniques. SCS personnel and their contractors; LMT, C&L, and GE performed NDE of the selected welds and components. In addition, CTS assisted SCS personnel with VT examinations of selected internal RPV components.
SCS, LHT, and GE personnel performed Class 1, 2, and 3 examinations. SCS and C&L performed Eddy Current Examinations as requested by GPC. SCS, GPC, and C&L procedures were used to perform the NDE Examinations. LMT and GE personnel were qualified to the applicable SCS procedures prior to performance of examinations. EPRI qualified inspectors were utilized for examinations involving IGSCC susceptible materials.
In addition to HDE testing of Class 1 and 2 welds and components, pressure testing, visual examination of Class 1 valve internal surfaces and visual examination of pipe supports and hangers were also performed. Third party review (e.g. an ANII) was utilized for the ISI.
Selected components were examined in accordance with the following documents:
- Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1980 Edition with Addenda through Winter 1981.
United States Nuclear Regulatory Commission, NUREG 0313, Revision 2, (Draft), " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping".
- United States Nuclear Regulatory Commission, NUREG 0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking".
United States Nuclear Regulatory Commission I&E Bulletin 80-13 Visual Examination of Core Spray Spargers.
General Electric Company Service Information Letter-330, Jet Pump Beam Inspection.
United States Nuclear Regulatory Commission I&E Bulletin 80-08, Examination of Containment Liner Penetration Welds.
General Electric Company Service Information Letter-420, Inspection of Jet Pump Sensing Lines.
General Electric Company Service Information Letter-433, Shroud Head Bolting Inspection.
SCS " Modi fied First Ten-Year Inservice Examination Plan for Class 1 Components Edwin I. Hatch Nuclear Plant, Unit 1, Rev.1 through Dev. 009".
SCS " Modified Forty-Year Inservice Examination Plan for Class 2 and 3 Components - Edwin I. Hatch Nuclear Plant, Unit 1, Rev. 1 through Dev.
006.
SCS " Inservice Inspection Outage Plan, Edwin I. Hatch Nuclear Plant, Unit 1 1987 Spring Refueling Outage through Dev. 001".
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. Representative samples of the following systems, comprised of selected Class
'1, 2, and 3 components, were examined using .various NDE techniques, in accordance with the above documents:
O class l Reactor Pressure Vessel (1811)
Main Steam System (1821)
Feedwater System (1821)
Reactor Recirculation System (1831)
Control Rod Drive System (lCll)
Standby Liquid Control System (lC41)
Residual Heat Removal System (1 Ell)
Core Spray System (lE21)
High Pressure Coolant Injection System (lE41)
Reactor Core Isolation Cooling System (lE51)
Valve Internals Class 2 Residual Heat Removal System (lE11)
Core Spray System (1E21)
High Pressure Coolant Injection System (lE41)
Containment Purge and Inerting System (1T48) l Control Rod Drive System (lC11)
Reactor Water Cleanup System (lG31)
Reactor Core Isolation Cooling System (lE51)
Main Steam Auxiliary System Piping (lNil)
Main Steam Relief Valve Discharge Piping (1821)
Turbine Steam Bypass System (lN37) r Class 3 rm) i._ Service Water System (lE11) (lP41)
Core Spray System (lE21)
Fuel Pool Cooling System (lG41)
Other (Non-ASME Related)
Eddy-Current Examinations were performed on the following components:
Unit 1 Feedwater Heaters SA, 58, 7A, 78, 8A, 88,10A,108, and the Unit 1 Main Condenser. A separate report issued by C&L and distributed by SCS will include all eddy-current examinations.
UT thickness measurements were performed on selected components in the Extraction Steam and Condensate Feedwater Piping Systems. A portion of these components were selected due to their similarity in design and operating conditions to components involved with the "Surry pipe break incident". A separate report for these examinations was prepared by SCS and was submitted to GPC engineering.
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7 CLASS 1 EXAMINATIONS Weld Overlays (UT)'
I.O Twenty-five weld overlays were UT examined. Eight of these overlays were found to have recordable indications. Five of these overlays were being re-examined- due to indications found during the previous outage. These five ,
overlays were accepted "as is" after analysis by GPC engineering. The remaining three welds with recordable indications had indications below the overlay thickness and were accepted "as is" after GPC engineering analysis.
Stainless Steel Piping (UT)
Seventy-nine circumferential welds and eleven longitudinal stainless steel pipe welds were UT examined. Eleven of the circumferential wel ds had recordable indications. Eight of these welds were being re-examined due to indications found during previous outages. These welds were found to be acceptable "as is" after analysis by GPC engineering. The remaining three welds (from RWCU system) were reported to the NRC as having unacceptable UT indications and were repaired using a limited service weld overlay technique.
These repair weld overlays were PT examined and found to be acceptable.
Weld Overlays and Stainless Steel Piping (PT)
' Ten piping welds and six weld overlays contained PT indications. These indications were removed or brought to an acceptable size per ASME Section XI by controlled grinding or flapping and the resul ts were verified by re-examination.
Remaining Class 1 Examinations or Components Fifty components were examined utilizing UT, PT, MT, and VT as applicable.
These examinations included; RPV welds, RPV internal s , RINTSA welds, main steam piping welds, feedwater piping welds, and valve internals.
Per GE SIL-433, the moisture separator shroud head hold down bolts were UT examined. Six bolts were found to have reportable indications. These bolts were removed and replaced by GE.
Per GE SIL-330, all twenty jet pump beams were UT examined. No reportable indications were observed.
Per GE SIL-420, the accessible jet pump sensing lines were VT examined. No reportable indications were observed.
The steam dryer and moisture separator were VT examined. This examination revealed one-hundred-thirty-eight crack like indications on the shroud support ledge of the steam dryer. The steam dryer support bracket at azimuth 34 degrees was re-examined due to indications recorded during previous outages.
All of the indications were evaluated by GE and were declared acceptable.
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Per I&E Bulletin 80-13, the core spray sparger and associated piping were VT examined. No reportable indications were observed.
- . fq Per ASME Section XI, selected RPV internals were examined. These examinations V included portions of the vessel interior, interior attachments beyond the beltline region and the core support structure. No reportable indications were observed. See RPV internals section of summary for detailed information.
Nine Class 1 valves were disassembled for maintenance during the outage. The internals of these valves were VT inspected in accordance with a GPC inspection program. Two of these valves were found to have unacceptable indications and were repaired in accordance with MWO instructions. '
CLASS II EXAMINATIONS Thirty-five welds were examined using surface and volumetric NDE techniques.
Six of these welds were examined per NUREG-0619 and the remaining twenty-nine per ASME Section XI requirements. One weld had a reportable indication. . This problem was expected due to problems experienced during operations. She the repairs and replacements section of this report for detailed information.
CONTAINMENT LINER PENETRATION WELDS Per I&E Bulletin 80-08, containment linear penetration welds on the following penetrations were examined: X20, X42, X44, X7A, X78, X7C, and X70.
Examinations consisted of UT, PT, MT, and VT. No reportable indications were observed.
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PRESSURE TESTING Two Class 2 and two Class 3 hydrostatic tests were performed and a Class 1 System Leakage Test was perfonned during the outage. See the pressure test section of this report for detailed information.
COMPONENT SUPPORT EXAMINATIONS (CLASS 1, 2. AND 3) !
l Two hundred and seventy-six component supports were VT examined during the outage. Thirty of these examinations produced unacceptable resul ts.
Twenty-two of the component supports were repaired and re-examined with acceptable results. The remaining eight component supports were accepted "as is" by GPC engineering evaluation, j i
I REPAIRS AND REPLACEMENTS (CLASS 1 AND 2) l A portion of stainless steel piping in the RWCU system was replaced due to a previously identified problem. Three weld overlays were also applied to the RWCU system. See repairs and repl acements section of this report for additional information.
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REPORTABLE INDICATIONS fs
(_) Following is an itemized list of all welds and components which were reported co contain indications or were considered unacceptable. All of these items were either repaired or evaluated and then declared acceptable.
SUMMARY
OF INDICATIONS Class 1 Overlays (UT) 1B31-1RC-22BM-4 1831-l RC-280-4 1B31-1RC-12AR-H-4 1831-lRC-28A-12 1031 -l RC-12BR-B-3 1831-lRC-22AM-1 }
1831-l RC-22AM-4 l El l-l RHR-248-R-12 Class 1 Stainless Steel Piping (UT) 1831-lRC-28A-2 1831-l RC-28A-4 1B31-lRC-288-8 1 B31 -l RC-28B-10 1G31-lRWCU-6-D-6 1G31-lRWCU-6-D-14 1G31-lRWCU-6-D-17
{ Class 1 Overlays / Stainless Steel Piping (PT) 1B31-1RC-12AR-J-2 1B31-1RC-12BR-B-2 1831 -l RC-22AM-3BC-2 1B31-1RC-22AM-3BC-1 1B31-lRC-28A-1 1G31-1RWCU-6-D-20 1831-l RC-288-17 1B31-lRC-12AR-H-2 (0L) 1831-lRC-12BR-E-2 (0L) 1B31-lRC-22AM-4 (0L) 1831-l RC-28B-14 lE11-lRHR-24B-R-12 (0L) l 1G31-lRWCU-6-D-4 (0L1 1G31-1RWCU-6-D-5 (OL) l 1 G31 -l RWCV-6-D-14 1G31-1RWCU-6-D-15A Remaining Class 1 Examinations or Components arator shroud head hold down bolts 6
#9,floisture sep#33, #35, and #36
#13, #25, 138 Crack like indications in steam dryer
,_s Steam dryer support bracket at azimuth - 34 degrees U
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- Class'1 Valve Internals' ]
1E11-F008: !
-q' (j- 1 Ell-F050B Class-II Examinations l
.-- 1 G31 -2RWCU-4-R-4B l
, iComponent Support Examinations-1821-MVVH-3 i
1 El1-RHRH-331 u 1 E11-RHRH-15
' 1 E11 -RHRH '
1E11-RHRH 1E11-RHRH-23 1 E11-RHRH-49 1E11-RHRH-224l 1E11-RHRH-53A 1E11-RHRH-39 1E11-RHRH-148 1 El1-RHRH-240 1 E11-RHRH-400 1E11-RHRH-72 ! 1E11-RHRH-337 1 1E11-RHRH-279 1 E11-RHRH-48 1E11-RHRH-362 1E41-HPSEH-10 1 E41-HPSEH-16 ' 1E41-HPSEH-17 1E41-HPSEH-89 1 E41-HPCIH-16 1E41-HPCIH-17B , 1E41-HPCIH-19A lE41-HPCIH-32 1T48-CPH-54 q 1B21-H222 1821-HVVH-30 O- ,B2,-xvvH-22 i-N- _ _ _ _ _ - - - -
i. The following sections of this NIS-1 Report contain the summary of the NDE Examinations performed, provides additional information and gives results of 3-those examinations. L) l
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SUMMARY
OF CLASS 1 VALVE INTERNALS I I l ss ,l
VISUAL EXAMINATION OF CLASS 1 VALVE INTERNALS This section provides a summation of the ASME required visual examinations of L Class 1 valve . internal surfaces. These examinations were performed on nine valves that were disassembled for maintenance during the 1987 Refueling Outage. .The examinations were performed by. Georgia Power Company Quality Control Inspection personnel in accordance with Inspection Plan D-L-87-02. Copies of -the -inspection : plans cre available at the plant site. The valves inspected were from the following systems: Main Steam (1821), Residual Heat ' Removal (l Ell ) , Feed Water Supply (1821), High Pressure Coolant Injection (lE41), and Reactor Water Cleanup (lG31 ) . Listed below are the valves examined and a brief summary of the results. VALVE NUMBER REf1 ARKS IB21-F0328 No reportable indications. 1821-F010A No reportable indications. 1821-F022A No reportable indications. l Ell-F008 . Examination revealed nicks,- pits and surface cracks on both surfaces of the wedge. Corrosion was al so noted on inside valve body. See Deficiency Report'l-87-509. Q l Ell-F015A No reportable indications. 1 Ell-F050B Examination revealed leakage around cover gasket. See f1W0# 1-87-4014. 1E11-F050A No reportable indications. 1E41-F002 No reportable indications. 1G31-F004' No reportable indications. O ss
1 I
SUMMARY
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.WL __G_HX3___ _ OY. EDS C~a.1
SUMMARY
OF CLASS 1, 2, AND 3 PRESSURE TESTS O 1 l O l22 t
PRESSURE TESTING This section of the report provides a discussion of the pressure tests that b were performed during the Plant Hatch Unit 1 Spring 1987 Refueling Outage. These pressure tests were performed for the purpose of inservice inspection on selected Class 1, 2, and 3 piping systems. The pressure tests and their boundaries are identified in the inservice examination plen prepared by Southern Company Services, Revision 1, Deviation 006 -l 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 ANI/ANII. The completed test reports are available for review in the Records Management Department at the jobsite. TESTING-Class 1 No class 1 Hydrostatic Tests were performed during this outage. A Class 1 System Leakage Test was perfonned prior to unit start-up per ASME XI, Section IWA-5211(a). This test' was performed using GPC Procedure 421T-TET-006-1S under Maintenance Work Order 1-87-1602. Only minor leakage was detected during VT-2 examination and after some repair work the Class 1 System was deemed acceptable by plant engineering. Class 2 ( Two Class 2 Hydros tatic Tests were performed during the outage. These hydrostatic tests were performed per ASME XI, IWA-5211 (d). The tests were performed in accordance with GPC procedure 42IT-TET-001-0S. Listed below are the Class 2 Hydrostatic Tests and accompanying Maintenance Work Orders: 1 E11 -PT-18 MWO # 1-87-1155 s 1E11-PT-19 MWO # 1-87-1146 Only minor leakage was detected during VT-2 examination ami all tests results were deemed acceptable by plant engineerir,g. J Class 3 Two Class 3 Hydrostatic tests were performed during the outage. These hydrostatic tests were perfonned per ASME XI, IWA-5211(d) end in accordance with GPC Procedure 42IT-TET-001-OS. Only minor leakage was detected and after engineering evaluation all tests results were deemed acceptable. Listed below are the Class 3 Hydrostatic Tests and accompanying Maintenance Work Orders: 1C41-PT-1 MWO # 1-87-1138 l 1C41-PT-3 MWO # 1-87-1136 O
/23 1 1
O
SUMMARY
OF VISUAL EXAMINATIONS CLASS 1, 2, AND 3 COMPONENT SUPPORTS O , 1 l l l l-O
/71
COMPONENT SUPPORT EXAMINATIONS o, U This section of the report provides a discussion of the visual examinations performed on selected component supports on Hatch Unit 1. The subject examinations were performed prior to and during the Refueling / Maintenance i Outage. Examinations were perfomed using SCS Procedure VT-H-730 (VT-3). The procedure and all examination data sheets are available for review at the plant site. Examinations Class 1 Eighteen component supports from the RHR and HPCI Systems were visually 'j examined. No repcetable indications were found. Class 2 One hundred sixty eight component supports from the following systems were visually examincd: Residual Heat Removal, Core Spray, liain Steam Auxiliary, and Containment Purge and Inerting. Twenty seven of these Class 2 component supports were found unacceptable. Reasons for unacceptability can be found in the remarks section of the Summary Table. Af ter maintenance or engineering ' evaluation, these component supports were detemined to be acceptable. Class 3
.O_ Ninety component supports from the following Class 3 systems were visually examined: fiain Steam Relief Valve, Fuel Pool Cooling, RHR Service Water, Core Spray, High Pressure Coolant Injection, and Plant Service Water. Three of these Class 3 component supports were found to be unacceptable. Reasons for unacceptability can be found in the remarks section of the Summary Table.
Af ter maintenance or engineering evaluation, these component supports were found acceptable. i l25 l 1
Summary of Visual Examinations This section of the report presents an explanation of the Summary of Component } e Support Examinations (Summary Table). The Summary Table provides information for the visual examinations performed prior to and during the 1987 Unit 1 Refueling /fiaintenance Outage to satisfy the requirements of AStiE Section XI and contains the results of each visual examination performed.
- 1. System Name The purpose of this column is self-explanatory.
- 2. Hanger or Device Mark Number This column is for the number assigned to a particular device on a given system. For example,1821-f1SH-4 indicates that the mark number for that particular Unit 1 main steam device is H4.
- 3. Device Type The type is divided only into spring, snubber (hydraulic or mechanical),
and simple-type hangers.
- 4. ISI Iso. Nu nber i The number given is either the weld / component identification drawing or GPC domestic drawing on which the location of the pipe support or hanger is depicted. These drawings are found or referenced in the Southern
$ Company Services-issued Long-Term Inservice Examination Plans for Class 1, 2, and 3 Components at Edwin I. Hatch Nuclear Plant Unit 1. The Class 3 component drawings can be found in the Records fianagement Department at the plant site.
- 5. Remarks Comments will be made in this column as to the acceptability of the examination, and the itWO# that the examination was perfonned under. In addition, any deficiency identified during the examination will be noted along with the deficiency resolution.
O
/26
4 t* j). 87 HNP-1 COMPONENT SUPPORTS
, CLNSS FIGURE'NO.' SUPPORT RESULTS INF RESULTS REMARKS -a.. ,
1 E11-104 1E11-RHRH-137- A. NA NA ;NA 1- .E11-104 1E11-RHRH-138 A NA NA NA 1 E11-104 ~1F11-RHRH-139 A NA NA' NA 1~ 'E11-104 1E11-S- 1 A NA NA NA 1 E11-104 1E11-S- 2 .A NA NA NA
-l' _E11-104 1E11-S- 4 A' NA NA NA l' E11-104 -1E11-S- 5 A NA NA NA' 1 E11-106 1E11-RHRH-327 A NA NA NA 1 'E11-10 6 - 1E11-RHRH-328 A NA NA NA
. 1~ E11-10 6 1E11-RHRH-329 A NA .NA -NA
'l E11-120 1E11-RHRH-141 A NA NA NA 1 E11-120 1E11-RHRH-142 A NA NA. NA 1 E11-120 1E11-RHRH-143 A' NA NA NA
'l E11-120 1E11-S- 15 A NA NA NA 1 E11-120 1E11-SM- 8 A NA NA NA-1 E41-104 1E41-HPCIH-29A A NA NA NA
'l E41-10 6 1E41-SS- 8 A NA NA NA 1 E41-106 1E41-SS- 22 A NA NA NA i
I I i o
/27
i
^ (
( )- 87 HNP-1-COMPONENT SUPPORTS CLASS FIGURE NO SUPPORT RESULTS INF RESULTS REMARKS 2 'B21-101 IB21-MVVH- 3 U 'I87H1012 A LOOSE NUT 2 E11-100 1E11-RHRH- 1 A NA NA NA 2 E11-100' 1E11-RHRH-187 A NA NA NA 2 E11-100 1E11-RHRH-323 A NA NA NA
.2' 'E11-101 1E11-RHRH- 9 A NA' NA NA 2- E11-101 1E11-RHRH- 11 A NA NA NA 2 E11-101 1E11-RHRH- 12 A NA NA NA 2 E11-101 1 E11-RHRH- 324 A NA NA NA 2 E11-101 1E11-RHRH-325 A NA NA NA 2 E11-101 1E11-RHRH-326 A NA NA NA' 2 'E11-101 1E11-RHRH-330 A NA NA NA 2 E11-101 1E11-RHRH-331 U I87H1025 A IMPROPER LOAD SETTING 2- E11-102 1E11-RHRH- 13 A NA NA NA 2 E11-102 1E11-RHRH- 14 A NA NA NA 2 E11-102 1E11-RHRH- 15 U I87H1003 NA IMPROPER LOAD SETTING /
ACCEPTED i AS IS PER ENG EVAL 2 E11-102 1E11-RHRH- 16 A NA NA NA 2 E11-102 1E11-RRRH- 17 U 187H1003 NA IMPROPER LOAD SETTING / ACCEPTED l
- AS IS PER l ENG EVAL 2 E11-102 1E11-RHRH- 18 A NA NA NA i) 4 2 'E11-102 IEll-RHRH- 19 A NA NA NA 2 E11-102 1E11-RHRH- 20 A NA NA NA
/28 L
() 87 HNP-1. COMPONENT SUPPORTS CLASS FIGURE NO SUPPORT RESULTS INF RESULTS REMARKS-2 E11-102 1E11-RHRH- 21 A. NA NA NA 2 E11-102 1E11-RHRH- 22 U 187H1002 A. LOOSE NUT 2 E11-102 1E11-RHRH- 23 U 187H1027 NA IMPROPER LOAD SETTING / ACCEPTED AS'IS PER ENG EVAL' 2 E11-102 1E11-RHRH- 25 A NA NA NA- ! 2 E11-102 1E11-RHRH- 26 A NA NA- .NA 2 E11-102 1E11-RHRH-153 A NA NA NA 2 E11-102 1E11-RHRH-154 A NA NA NA 2 E11-102 1E11-RHRH-193 A NA NA NA-
) 2 E11-102 1E11-RHRH-194- A NA NA NA
.2 E11-102 1E11-RHRH-115 A NA NA NA 2 E11-102 1E11-RHRH-196 A NA NA NA 2 E11-102 1E11-RHRH-200 A NA NA NA 2 E11-102 1E11-RHRH-207 A NA NA NA 2 E11-102 1E11-RHRH-308 A NA NA NA-2 E11-102 1 E11-RHRH- 309 A NA NA NA 2 E11-102 1E11-RHRH-310 A NA NA NA 2- E11-102 1E11-RHRH-316 A NA NA NA 2 E11-10 3 1E11-RHRH- 28 A NA NA NA 2 E11-10 3 1E11-RHRH- 30 A NA NA NA 2 E11 -10 3 1E11-RHRH- 31 A NA NA NA 2 E11-103 1E11-RHRH- 32 A NA NA NA O 2 E11-10 3 ' 1E11-RHRH- 33 A NA NA NA 2 E11 -10 3 1E11-RHRH-210 A NA NA NA
/29
erm , , ' Y bk s ' , ha L c' ;; ( u '\ 4 l 87 HNP-1 COMPONENT SUPPORTS
~CLASSLFIGURE'NO SUPPORT RESULTS INF- RESULTS REMARKS it
- 2- -E11-103 ' 1E11-RHRH-213 A NA NA NA' 3
2 ' E11-103 1E11~-RHRH-214 A- NA NA NA
'2 -E11-10 3 - 1E11-RHRH-215 A NA NA NA 2- E11-103 1E11-RHRH-411 A -NA NA NA L2 ET 1-104 1E11-RHRH- 4 9 U 187H1003 NA IMPROPER LOAD SETTING /~
ACCEPTED AS IS PER
', ENG EVAL
-2 E11-104 1E11-RHRH- 52 A NA NA NA V1 -2 E11-104 1E11-RHRH- 53 A NA NA- NA 2 E11-104, 1E11-RHRH-136, A NA NA NA
(^S . . X .) 2. E11-104- 1E11-RHRH-219 A NA NA NA 2 -E11-104 1E11-RHRH-220 A NA NA NA
~2' E11-104- 1E11-RHRH-221 A NA NA NA 2- E11-104 1E11-RHRH-222 A NA NA NA 2 E11-104 1E11-EMRH-223 A NA NA NA 2 E11-104 1E11-RHRH-224 U 187H1027 A LOOSE NUTS 2- E11-104 1E11-RHRH-53A U 187H1004 A LOOSE NUT 2- E11-105 1E11-RHRH- 37 A NA NA NA 2 E11-105 1E11-RHRH- 39 U 187H1004 A LOOSE NUT 2 E11-105- 1E11-RHRH- 40 A NA NA - NA 2 E11-105 IE11-RHRH- 41 A NA NA NA 21 E11-105 IE11-RHRH- 42 A NA NA NA 2 E11-105 1E11-RHRH-226 A NA NA NA
(~~) 2 E11-105 1E11-RHRH-233 A NA NA NA 2 E11-105 1E11-RHRH-234 A NA NA NA
- l. -
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,r v .g7-HNP-1. COMPONENT ~ SUPPORTS-p, UCLASSLFIGURE.NOL SUPPORT. cRESULTS INF- RESULTS REMARKS
' D'
, 12? iE11-107L 1E11-RHRH-144' A NA NA NA l
, .2- : E11-107. :1E11-RHRH-145 A- NA- NA' 'NA 2 E11-107 1E11-RHRH-235 A NA. NA NA
- ! 2 ' - E11'-107 1E11'-RHRH-237 A NA. NA NA 4
2 -E11-107. 1E1L-RHRH-397 A' NA' NA NA 2 - El'l-10 8 1E11-RHRH-146 A NA NA NA
.3 -
.2 E11-108 -1El1-RHRH-147 A NA NA NA 2 -E11-108~ 1E11-RHRH-148' U 187H1025 NA' IMPROPER-LOAD SETTING /-
ACCEPTED AS IS PER ENG EVAL 2 ' E11 -10 8 1E11-RHRH-240 V 187H1028 A LOOSE JAM NUT 2 E11-108' 1E11-RHRH-242 A NA NA NA 2- - E11-108 1E11-RHRH-398 A NA NA NA h
- 2. ' E11-10 8 1E11-RHRM-400 U 187H1028 A LOOSE NUTS 2 E11-109 .1E11-RHRH A NA NA NA L 2 E11-109 1E11-RHRH-244 A NA NA NA l 1; .
L 2 El'l-10 9 - IE11-RHRH-245 A NA NA NA 2' ' E11-110 1E11-RHRH-249 A NA NA NA 2 E11-111 IE11-RHRH- 72 U 187H1025 NA IMPROPER LOAD SETTING / ACCEPTED AS IS PER ENG EVAL 2 E11-111 1E11-RHRH-250 A NA NA NA
.O 2 E11-111 1E11-RHRH-251 A NA NA NA 2 E11-111 1E11-RHRH-252 A NA NA NA
/3/ l
.() 87 HNP-1 COMPONENT SUPPORTS CLASS-FIGURE NO SUPPORT RESULTS INF. RESULTS REMARKS 2 El'l-111 1E11-RHRH-413 A NA NA~ NA
~2 E11-112 1E11-RHRH-254 A- NA NA NA 2- E11-113 1 E11-RHRH-24 3 A NA NA NA 2 E11-113. 1E11-RHRH-335A' A -10\ NA 'NA 2 E11-113 1E11-RHRH-337 0 187H1028 A BENT ROD >
2 E11-114 1E11-HPSEH- 42 A NA. NA NA 2 E11-114 1E11-HPSEH- 44 A NA NA NA 2 E11-114 .1E11-HPSEH 67 A NA NA NA
.2 E11-114 1E11-HPSEH- 68 A NA NA NA 2L E11-114 1E11-HPSEH- 69 A NA NA NA 2 E11-114 1E11-HPSEH- 70 A NA NA NA 2 E11-116 1E11-RHRH-279- U 187H1029 A LOOSE JAM NUT 2 E11-117 1E11-RHRH-288 A NA NA NA 2 E11-120 1E11-HPSEH-307 A NA NA NA 2' E11-120 1E11-RHRH- 48 U I67H1025 A IMPROPER LOAD SETTING 2 E11-120 1E11-RHRH-140 A NA NA NA 2 ,E11-120 1E11-RHRH-47A A NA NA NA 2 E11-121 1E11-RRRH-127 A NA NA NA 2 E11-124 IE11-RHRH-175 A NA NA NA 2 E11-124 1E11-RHRH-353 A NA NA NA 2 E11-125 1E11-RHRH-162 A NA NA NA 2 E11-125 IE11-RHRH-362 U 187H1025 A IMPROPER LOAD
()- SETTING 2 E11-127 1E11-RHRH-181 A NA NA NA
/32
(} -87 HNP-1. COMPONENT' SUPPORTS
. CLASS FIGURE NO SUPPORT RESULTS INF; RESULTS REMARKS 2' E21-100 1E21-CSH- 9 A' NA NA- NA 'l i
2 E21-100 1E21-CSH- 10 A NA NA NA 2 E21-100 1E21-CSH- 11 A NA NA NA f 1 2 E21-100 1E21-CSH- 24 A NA NA NA
'2 E21-100 1E21-CSH- 41 A NA NA NA 2 E21-100 1E21-CSH- 43 A NA NA NA 2 .E21-100 1E21-CSH- 45 A NA NA NA >
l 2 E21-101 1E21-CSH- 25 A NA NA NA 2 E21-101 1E21-CSH- 54 A NA NA NA 2 E21-101' 1E21-CSH- 74 A NA NA NA 2 E21-102 1E21-CSH- 26 A NA NA NA
.O 2 E21-102 1E21-CSH- 29 A NA NA NA ,
2 E21-102 1E21-CSH- 32 A NA NA. NA j 2 E21-102 1E21-CSH- 55 A NA NA NA ' i 2 E21-102 1E21-CSH- 56 A NA NA NA 2 E21-102 1E21-CSH- 57 A NA NA NA 2 E21-102 1E21-CSH- 58 A NA NA NA 2 E21-102 1E21-CSH- 60 A NA NA NA 1 2 E41-100 1E41-HPSEH- 21 A NA NA NA > 2 E41-100 1E41-HPSEH- 22 A NA NA NA 2 E41-100 1E41-HPSEH- 25 A NA NA NA 2 E41-100 1E41-HPSEH- 26 A NA NA NA 2 E41-100 1E41-HPSEH- 27 A NA NA NA () 2 E41-100 1E41-HPSEH- 34 A NA NA NA 2 E41-100 1E41-HPSEH- 35 A NA NA NA 2 E41-100 1E41-HPSEH- 69 A NA NA NA
/33 i
.i
(]y 87 HNP-1-COMPONENT SUPPORTS
' CLASS' FIGURE NO SUPPORT 'RESULTS INF RESULTS REMARKS
~-
2 E41-100- '1E41-HPSEH- 92 A 'NA NA NA'
-2 E41-100- 1E41-HPSEH- 93 A NA NA NA' 2 E41-100 1E41-HPSEH- 95 A NA NA NA
;2 E41-100 1E41-HPSEH-810 A NA NA NA 2 E41-102 1E41-HPSEH- 1 A NA NA NA 2 E41-102 1E41-HPSEH- 2 A NA NA NA 2 E41-102 1E41-HPSEH- 3 A NA NA NA 2 E41-102 1E41-HPSEH- 5 A NA NA NA 2 E41-102 1E41-HPSEH- 7 A NA NA NA
-2 E41-102 1E41-HPSEH- 9 A NA. NA NA
- h. 2 E41-102 1E41-HPSEH- 10 U 187H1028 A IMPROPER (J- LOAD SETTING l 2 E41-102 1E41-HPSEH- 14 A NA NA NA i
2' E41-102 1E41-HPSEH- 16 U 187H1028 A LOOSE JAM l , NUT 2 E41-102 1E41-HPSEH- 17 U 187H1028 A LOOSE JAM NUT 2 E41-102 1E41-HPSEH- 89 U 187H1027 A LOOSE NUTS 2 E41-104 1E41-HPCIH- 12 A NA NA NA 2 E41-104 1E41-HPCIH- 15 A NA NA NA 2 E41-104 1E41-HPCIH- 16 U IB7H1004 A LOOSE NUT l 2 E41-104 1E41-HPCIH- 17 A NA NA NA 2 E41-104 1E41-HPCIH- ::6 A NA NA NA E41-104 1E41-HPCIH- 27 A NA NA NA
~
2 E41-104 1E41-HPCIH- 38 A NA NA NA
' () 2 2 E41-104 1E41-HPCIH-11A A NA NA NA
! 2 E41-104 1E41-HPCIH-13A A NA NA NA 1
/34
[l
,t
. ;h 87 HNP-1 COMPONENT SUPPORTS CLASS FIGURE NO^ -SUPPORT RESULTS INF RESULTS. REMARKS i
2 .E41-104 IE41-HPCIH-17B- U' I67H1026 A MISSING SPHERICAL i' BEARING /- LOOSE STUD ASSEMBLY.
-2 E41-104 1E41-HPCIH-19A. U 187H1026 A LOOSE JAM. j NUT
'2 E41-105 1E41-HPCIH- 32 U 187H1027 A LOOSE CLAMP ,
1 2 E41-105 1E41-MPCIH- 33 A NA NA NA 2' . E41-105 1E41-HPCIH- 40 A NA NA NA i
- 2. T46-102- 1T48-CPH- 14 A. NA NA NA -
2 -T48-102 1T48-CPH- 53 A -NA 'NA NA i g 2 T48-102 iT46-CPH- 54 U I87H1002 A LOOSE NUT /
.W - IMPROPER i LOAD l
SETTING 2 T48-103 1T48-CPH- 6 A NA NA NA 1 l l l l l
/35
87'HNP-l' COMPONENT SUPPORTS CLASS FIGURE NO SUPPORT' RESULTS INF RESULTS REMARKS 3 1B21-100 1B21'-H812 A NA NA NA 3 B21-100 1B21--H814 'A NA NA NA 3 B21-100 1B21-H815 A NA NA NA 3 B21-100 1B21-H816 A PUk~ NA NA 3 B21-100 1B21-H818 A 'NA- PUk IUk 3 B21-101 1B21-H822 U 187H1028 A IMPROPER. SETTING / LOOSE JAM NUT 3 B21-101 1B21-SS- 13 A NA NA NA 3 B21-101 IB21-SS- 14 A NA NA NA 3 B21-103 1B21-MVVH- 9 A NA NA NA () '3 B21-304 1B21-H8 A NA NA NA 3 B21-104 1B21-SS- 34 A NA NA NA l 3 B21-113 IB21-MVVH- 30 U I67H1029 A LOOSE NUT 3 B21-113 1B21-MVVH- 34 A NA NA NA 3 B21-113 1B21-MVVH-703 A NA NA NA 3 B21-114, 116 IL21-MVVH- 22 U 187H1029 A MISSING COTTER PIN 3 B21-114, 116 1B21-MVVH- 26 A NA NA NA 3 E11-117 1 E11 -P'4RH- 34 7 A NA NA NA 3 E11-128 1E11-RHRh-385 A NA NA NA 3 E11-128 1E11-RHRH-386 A NA NA NA i 3 E11-128 1E11-RHRH-390 A NA NA NA 3 E11-128 1E11-RHRH-810 A NA NA NA 3 E11-HNGR-1 1E11-ISH- 8 A NA NA NA -({) 3 E11-HNGR-2 1E11-ISH- 1 A NA. NA NA 3 E11-HNGR-2 1E11-ISH- 2 A NA NA NA
/36 l
l 87 HNP-1. COMPONENT SUPPORTS (])l-
-CLASS FIGURE.NO SUPPORT RESULTS INF RESULTS REMARKS
-3 'E11-HNGR-2 1E11-1SH- 3 A- NA NA NA 3 .E11-HNGR-2 1E11-ISH- '7 A NA NA NA 3 E11-HNGR-3 1E11-ISH- 16 A NA. NA NA 3 E11-HNGR-3 1E11-ISH- 17 A NA NA- NA 3 E11-HNGR-3 1E11-ISH- 18 A NA NA NA
' 3- E21-10 3 1E21-CSH- 2 A- NA NA NA 3 E21-10 3 .1E21-CSH- 3 A NA NA NA-3 E21-103 1E21-CSH- 4 A NA NA NA 1
3 E21-103 1E21-CSH- -5' A NA NA NA 3 E21-103 1E21-CSH- 6 A NA NA NA 3' E21-103 1E21-CSH- 7 'A NA NA :NA 3 E21-103 1E21-CSH 47 A NA NA NA 3 E21-10 3 IE21-CSH- 4 8 A 'NA NA. NA 3 E21-10 3 1E21-CSH- 49 A NA NA NA 3 E41 -'10 3 1E41-HPCIH-2A A NA NA NA , '3 E41-104 1E41-HPCIH- 18 A NA NA NA 3 E41-104 1E41-HPCIH-17A A NA NA NA 3 E41-104 1E41-HPCIH-20A A NA NA NA 3 H-16126 1G41-PCH- 14 A NA NA NA 3 H-16126 1G41-PCH- 15 A NA NA NA 3 H-16126' 1G41-PCH- 16 A NA NA NA 3 H-16126 1G41-PCH- 17 A NA NA NA 3 H-16126 IG41-PCH- 18 A NA NA NA 3 H-16126 1G41-PCH- 35 A NA NA NA ({} 3- H-16126 1G41-PCH- 45 A NA NA NA 3 H-16126 1G41-PCH- 48 A NA NA NA i
/57
) 87'HNP-1 COMPONENT SUPPORTS
' CLASS _ FIGURE ~NO' SUPPORT 'RESULTS INF RESULTS REMARKS' 3 H-16126 1G41-PCH- 49 A NA. NA NA 3 H-16126 1G41-PCH- 50 A NA- NA NA 3 'H-16126 1G41-PCH- 51 A NA NA NA- !
3 .H-16126 1G41-PCH- 52 A NA' NA NA 3 H-16126 1G41-PCH- 53 A NA NA NA 3 H-16126 1G4'l-PCH- 69 A NA NA NA 3 ISI-008- 1P41-SWH-X48 A NA NA NA 3 ISI-010' 1?41-SWH-X62 A NA NA NA 3 'ISI-010 1P41-SWH-X63 A- NA NA NA 3 ISI-012 1P41-SWH-X76 A NA NA~ NA 3 P41-101 1P41-SWH-269 A NA- NA NA 3 P41-102 1P41-SWH- 17 A NA NA- NA 3- P41-102 1P41-SWH- 20 A NA NA NA f 3 P41-102 1P41-SWH-274 A NA NA NA 3 P41-102 1P41-SWH-275 A NA NA NA 3 P41-107 1P41-SWH- 84 A NA NA NA 3 P41-HNGR-1 1P41-ISH- 32 A NA NA NA i 3 P41-HNGR-2 1P41-ISH- 38 A NA NA NA 3 P41-HNGR-2 1P41-ISH- 38A A NA NA NA 3 P41-HNGR-2 1P41-ISH- 39 A NA NA NA 3 P41-HNGR-2 1P41-ISH- 50 A NA NA NA 3 P41-HNGR-2 1P41-ISH- 51 A NA NA NA 3 P41-HNGR-2 1P41-ISH- 53 A NA NA NA j () 3 P41-HNGR-2 1P41-ISH-800 A NA NA NA 3 P41-HNGR-2 1P41-ISH-801 A NA NA NA 3 P41-HNGR-5 1P41-ISH- 26 A NA NA NA
/38
k.;.
. . i
[/]- 87 HNP-1 COMPONENT' SUPPORTS CLASS FIGURE-NO SUPPORT RESULTS INF- RESULTS REMARKS' { 1 3 P41-HNGR 1P41-SDGH- 11 A NA. NA NA k 3 P41-HNGR-8 IP41-SDGH- 12 A NA NA' NA~
- 3. P41-HNGR-8 1P41-SDGH- 13 A NA NA NA .
-3 ;P41-HNGR-8 1P41-SDGH- 14 A NA NA NA-3 P41-HNGR-8 1P41-SDGH 15 A NA NA 'NA 1 1
3 P41-HNGR-8 1P41-SDGH- 16 A NA NA ' NA . -l 3 P41-HNGR IP41-SDGH- 17 A NA -NA NA 3 P41-HNGR-8 1P41-SDGH- 18 A NA NA' NA 3 P41-HNGR-8 1P41-SDGH- 19. A NA NA 'NA ; 3 P41-HNGR-9 1P41-DSW-A19 A NA NA NA 3 P41-HNGR-9 1P41-DSW-R21 A NA NA NA
-3 P41-HNGR-9' 1P41-DSW-R22 A NA NA' NA 3 P41-HNGR-9 1P41-SDGH- 31 A NA NA NA 3 'P41-HNGR-9 1P41-SDGH- 41 A NA NA NA-t O
/39
1 O 1 1
SUMMARY
OF REACTOR PRESSURE YESSEL , 1 1 INTERNAL INSPECTIONS O . l I
\
i l l
)
l l l 1 1 1
/40
Peactor Pressure Vessel Internals This section of the report provides a summary of the remote visual and
, ultrasonic examinations performed by SCS and CTS Power Services on selected RPV internals. The visual examinations were performed utilizing SCS Procedure VT-H-750. This procedure incorporates requirements for ASME Section XI, GE Service Information letters and NRC IEB 80-13. SCS procedures were also used !
to perform the required UT examinations. ' l All visual examination tapes were reviewed by SCS or LMT certified Level II visual examiners to determine the acceptability of the various RFV internal components. All procedure data sheets and video tapes are available in the Document Control Department at the plant site. Core Spray Sparger Inspection Per the requirements of NRC IED 80-13, the core spray spargers and associated piping were examined. Underwater video equipment recorded the examinations to the resolution of a 001 inch diameter 'tisual acuity standard. The examinations on the lower sparger ring B revealed a surface scratch which was determined to be nonreportable. No other reportable indications were found on the upper or lower Core Spray Spargers or the Core Spray Headers at 90 degrees and 270 degrees. Jet Pump Sensing Lines Inspection A remote visual examination of the accessible Jet Pump Sensing Lines was performed per the recommendations of GE SIL - 420 Linear indications on sensing lines 9,14, and 19 were initially recorded. Af ter re-examination, I Q the indications were determined to be non-significant. No other reportable , indications were recorded on the accessible sensing lines, support brackets l and welds. t RPV Internals Inspections A representative vessel cladding sample (10%) was visually examined and no l recordable indications were found. The Steam Dryer Support Bracket at azimuth ! 34 degrees was visually examined and no recordable indications were found. I O l
/4/
Steam Dryer Inspections A remote visual examination was performed on various components of the Steam s Dryer which consisted of; lifting eyes, stiffeners, stiffener welds, vertical surfaces at azimuths 45 degrees,135 degrees, 225 degrees, and 315 degrees, vertical welds numbered 1 through 40, steam dryer support brackets and seal skirt weld. A total of one-hundred-thirty-eight linear indications were recorded. Listed below are the affected areas and number of associated indications:
- 1. Stiffener Welds Broken Tack Welds
- 2. Vertical Weld #19 15 Cracks
- 3. Vertical Weld #22 62 Cracks
- 4. Vertical Weld #39 22 Cracks
- 5. Support Dracket at Azimuth 146 degrees 8 Cracks
- 6. Seal to Support Ring at Azimuth 34 -146 29 Cracks
- 7. Seal Skirt to Support Ring at Azimuth 146 -214 2 Cracks GE reviewed the indications and after engineering analysis determined them to be acceptable for continued operation with additional monitoring requested during the next scheduled refueling outage. No other reportable indications were observed.
Jet Pump Beam - UT
' Per GE SIL - SJ0, all twenty Jet Pump Geams were UT examined using SCS Procedure UT-H-414. No reportable indications were observed.
Shroud Head Bolt - UT Per GE SIL - 433, all thirty-six moisture separator head hold down bolts were UT examined using SCS Procedure UT-H-418. Six bolts were observed to have reportable indications. SCS initiated INF 187H1005 to report the six bolts and GPC elected to replace all six. Listed below are the replacement bolts.
#9 #33
#13 #35
#25 #36 No other reportable indications were observed.
l O
/42
O.
SUMMARY
OF CLASS 1 AND 2 REPAIRS AND REPLACEMENTS O l l l l I O l
/43
I I REPAIRS AND REPLACEMENTS j Class 1 ('v) ; During UT examination, three RWCU welds were determined to contain IGSCC indications. The examination results were reported to Structural Integrity l Associates, Inc. of San Jose, California. A complete engineering analysis of I the indications was performed by Structural Integrity and was submitted to GPC i in report titled " Flaw Evaluation and Repair Design for Plant E.I. Hatch Unit 1 - Spring 1987 Outage", SIR 014, Revision 1, June 11,1987. Based on the analysis and recommendations of the Structural Integrity Report, three welds in the RWCU System were repaired using a limited service overlay weld design. The repaired welds were: 1G31-RWCV-6-D-17 1G31-RWCU-6-D-6 l 1G31-RWCU-6-D-14 : After repair welding, these weld overlays were PT examined and no recordable indications were found. The ANI/ANII was utilized to the extent possible per the ASME code for the overlay repairs. Class 2 (% ( A portion of the stainless steel piping downstream of the CRD to RWCU Thermal Tee was replaced with carbon steel pipe due to a thennal cracking problem I which had been previously identified. This piping replacement was performed per DCR 1-87-19. The existing welds which were removed are: 1G31-2RWCU-4-R-4B , 1 G31 -2RWCU-4-R-5* i These welds were replaced with welds: 1G31-2RWCU-4-R-4C 1G31-2RWCU-4-R-5A* All required Section XI post ropair examinations were performed and were found to be acceptable. 4 Weld 1G31-2RWCU-4-R-4C will be re-examined per the frequency commitments of NUREG-0619. No further examination of weld 1G31-2RWCU-4-R-5A is required. , t
- This weld is not affected by NUREG-0619.
m , N 14 4
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