ML17263A725
| ML17263A725 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1994 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A724 | List: |
| References | |
| NUDOCS 9407190384 | |
| Download: ML17263A725 (173) | |
Text
ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER, NY 14649 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE THIRD INTERVAL (1990 - 1999)
SECOND PERIOD, SECOND OUTAGE (1994)
AT R. E.
GINNA NUCLEAR POWER PLANT REVISION 0 JUNE 30, 1994 07190>BP
<<)40712 9007 DOCK 05000244 I
PDR PDR g
R. E.
GINNA NUCLEAR POWER PLANT NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT THIRD INTERVAL (1990
- 1999)
SECOND PERIOD, SECOND OUTAGE (1994)
OWNERS DATA SHEET Date:
30 June, 1994 Owner:
Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Plant Location and Unit No.:
R.
E. Ginna Nuclear Power Plant Unit One 1503 Lake Road
- Ontario, New York 14519 Commercial 0 eratin Date:
July 1970 A
licable Code:
ASME Section XI, 1986 Edition, No Addenda
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
TABLE OF CONTENTS Introduction and Synopsis Summary of Work Accomplished Class 1 Components Class 2 Components Class 3 Components Class Q Components High Energy Components Design Break Weld Examinations Consequential Break Weld Examinations Component Support Examinations Steam Generators System Pressure Testing Hydrostatic Testing Leakage Testing Service Induced Rejectable Components Snubbers Visual Examinations Functional Testing Seismic Support Program Erosion/Corrosion (Minwall) Program Attachment I ISI Program Summary Attachment II
- Repair, Replacement
& Modification Program Summary Attachment III Erosion/Corrosion (Minwall) Program Summary
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GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second'utage (1994)
INTRODUCTION AND SYNOPSIS
~
Inservice Inspection (ISI) activities during the 1994 Refueling Outage were performed on components within Class 1, 2, 3, High Energy Piping, Class Q,
- Tubes, Seismic Supports and Snubbers.
ISI examinations were initiated on February 28, 1994 and concluded on April 18, 1994.
Examination methods included Visual (VT), Liquid Penetrant (PT),
Magnetic Particle (MT), Ultrasonic (UT),
Radiographic (RT),
and Eddy Current (ET). Functional Testing (FT) and System Pressure Tests were also performed.
Erosion/Corrosion examinations were also performed during the Refueling Outage timeframe.
Personnel involved included the RG&E Materials Engineering and Inspection Services
- Section, Sonic Systems Incorporated, Master Lee Services Corporation, ABB Combustion Engineering Corporation, Ginna Station Quality Control and the Ginna Station Results/Test Group.
Additional Support Personnel included individuals from the following departments:
Ginna Station Insulators, Maintenance, Electricians, Pipe
- Fitters, Health
- Physics, Turbine Maintenance, RGEE General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering Services Department.
ASME SECTIO XI
SUMMARY
OP WORK ACCOMPLI BED:
~
Upon conclusion of the 1994 Outage, 47.2-. of ASME Section XI Code required examinations for the Third Interval ISI Program have been completed.
A detailed component summary of all outage ISI activities with their associated results can be found within "Attachment I".
CLASS 1
COMPONENTS A total of 91 ASME, Augmented and Owner Elected components were examined during the 1994 Outage.
The examinations for these components consisted of 18 VT-1's, 15 VT-3's, 19 PT's, 33 MT's and 32 UT'st A total of 117 examinations were performed on Class 1 Components.
R.
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GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 ; 1999 Interval, Second Period, Second Outage (1994)
CLASS 1
COMPONENTS:
Cont.
Class 1 examinations were performed and/or credit taken on the following items/systems and/or plant lines:
Item S stem Descri tion Plant Line Reactor Pressure Vessel:
- Interior
- Closure Nuts, Studs S Washers Pressurizer, Nozzles Inside Radius:
Reactor Coolant System Lines:
31-RC-2501-A 29-RC-2501-B Pressurizer Lines:
4A-RCS-2501-A 3A-RC8-2501 3C-RCS-2501 3A-RCS-2501-B 2A-RCS-2501 Residual Heat Removal Lines:
H.P. Safety Injection Lines:
4A-RCO-2501-A 2C-SI2-2501 2B-SI2-2501 Letdown Lines:
2A-CH4-2501 2B-CH4-2501 2A-CH-601 Alternative Charging Lines:
2C-CH5-2502 2A-RCO-2501-A 2C-CH5-2502 2F-CH5-2502 Reactor Coolant Pump:
- "A" Components
- "B" Components, Flywheel
- "Spare" Flywheel 6 Pawls Pawls
R. E.
GINNA NUCLEAR'OWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
CLASS 2
COMPONENTS:
A total of 67 ASME and Owner Elected Components were examined.
The examinations for these components consisted of 6 VT-1's, 30 VT-3's, 22 PT's, 11 MT's, 3 RT's, and 16 UT's, for a total of 88 examinations.
Class 2 examinations were performed on the following items
/ systems and/or plant lines:
Item S stem Descri tion Plant Line Pulse Dampener:
Seal Water Injection Filter B:
Residual Heat Exchanger
- B:
Residual Heat Removal Pump A:
Containment Spray Pump A:
H.P. Safety Injection Pump B:
30A-MS-600-1A 30B-MS-600-1B 6F-MS-600-1B Feedwater Lines:
14A-FW-900-1A 14B-FW-900-1B H.P. Safety Injection Lines:
8B-SI-301A 8H-SI-301 8J-SI-151 4 -SI-301 4B-SI-301 4D-SI-1501 4E-SI-1501 3A-SI-1501 2A-SI-1501 2R-SI-2501 2S-SI-2501
R.
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GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
CLASS 2
COMPONENTS:
Cont.
Item S stem De cri ti n Residual Heat Removal Lines:
Plant Lin 10GG-AC-151 10C -AC-601 8FF-AC-601 8E -AC-601 6A -AC-601 Service Water Lines:
8C"SW-125 8E-SW-125 8K-SW-125 Standby Auxiliary Feedwater Lines:
3C-FW-902S-1A 3C-FW-902S-1B Pressurizer Lines:
2 -CH5-2501 2A-RC8-2501 2E-CH5-2501 Alternative Charging Lines:
2B-RCO'-2501-B 2F-CH5-2501 Charging Line:
2D-CH5-2501 CLASS 3
COMPONENTS:
A total of 82 ASME and Owner Elected Components were examined utilizing the VT-3 visual technique.
Examinations were performed on the following items /
systems and/or plant lines:
Item S stem Descri tion Non-Regenerative Heat Exchanger:
Diesel Generators A s B Exhaust Lines:
Plant Lin 20B-DG-150-4A 20B-DG-150-4B 20A-DG-150-4B
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
CLASS 3
COMPONENTS:
Cont.
Item S stem Descri tion Component Cooling Lines:
Auxiliary Cooling Lines:
Service Water Lines:
Plant Line 14C-AC5-152 10H-ACS-152 10L-AC5-152 8A-AC5-152 SB-AC5-152 8B-AC6-152 6G-AC6-152 20I-SWO-125-1 14A-SWO-125-1 14B-SWO-125-1 14E-SWO-125-1 14F-SWO-125-1 14H-SWO-125-1 10B-SWO-125-1 Auxiliary Feedwater Lines:
5A-FW7-900-1 4A-SW -125-1A 3A-FW7-900-1A 3A-FW7-900-1B 3D-FW7-900-1 3E-FW7-900-1 3G-FW7-900-1 3J-FW7-900-1 3K-FW7-900-1 2C-FW7-900-1A Standby Auxiliary Feedwater Lines:
Main Steam Line:
4A-FWS-152S-A 4K-SWO-152S 3A-FWS-902S-A 3A-FWS-902S-B 3C-FWS-902S 6B-MS-600-1
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
CLASS COMPONENTS:
A total of 2
Owner Elected Components were examined utilizing Ultrasonic (UT) techniques.
Examinations were performed on the following items /
systems and/or plant lines:
Item S stem Descri tion Plant Line Letdown Demineralizer Filter HIGH ENERGY COMPONENTS:
Augnented and Owner Elected Components associated with the High Energy Program were examined during the 1994 Outage.
The examinations for these items consisted of 16 VT-1's, 2 VT-3's, 16 MT's, 10 RT's, and 7 UT's for a total of 51 examinations.
High Energy component examinations were performed on the following items / systems and/or plant lines:
Item S stem Descri tion Main Steam Lines:
Plant Line 30A-MS-600-1A 30B-MS-600-1B 30A-MS-600-1 30B-MS-600-1 24B-MS-600-1A Feedwater Lines:
20 -FW-900-1 14A-FW-900-1A 14B-FW-900-1B 14A-FW-900-1 8 -FW-900-1
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
STEAM GENERATOR TUBING:
Eddy Current ASME and Owner Elected Examinations were performed on tubes in the "A" and "B" Steam Generators.
The following Eddy Current examinations were performed during the 1994 Outage:
Open Generator
- Tubes, Previous indications greater than or equal to 20% were examined'to the extent of degradation as a minimum.
2.
3.
Open Generator
- Tubes, 20%
Random Sample of all open unsleeved tubes were examined Full Length (F/L).
Open Generator Tubes, 100% of all open unsleeved tubes were examined to the first Support Plate on the Hot Leg side as a minimum.
4.
Sleeved Generator
- Tubes, 20'-.
Random Sample of each type of sleeved generator tubes were examined from the sleeve end as a minimum.
5.
MRPC of all Row 1 U-Bends and Row 2 U-Bends.
6.
MRPC of Roll Transition Region in all open, unsleeved tubes.
7.
Wear Indications Cold Leg, Tubes R1C10-R1C12, R2C10 R
- R2C12, R3C10-R3C12.
Steam Generator Eddy Current Examination details are documented in the Rochester Gas S Electric 1994 Steam Generator Eddy Current Final Report.
SYSTEM PRESSURE TESTS:
H ros atic Testin No 10-Year ISI (ASME) Hydrostatic tests were performed during the 1994 Outage.
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GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
SYSTEM PRESSURE TESTS:
Cont.
Leaka e Testin A total of fifteen (15)
ASME and Augmented Leakage Examinations were performed during the 1994 outage.
The leakage tests included; one (1) Class 1, Reactor Coolant System (PT-7) examination, thirteen (13)
Class 2 or 3 examinations, and one (1)
High Energy Feedwater examination.
One (1)
Class 3
examination was partially completed during this refueling outage.
ASME Section XI Re ired Com onents Service Induced Re ectable E
anded Examinations:
During the 1994 Ginna Station Refueling Outage, no ASME Section XI required components were classified as "Service Induced Rejectable" needing Code expanded examinations.
SNUBBER PROGRAM "
Visual Examinations:
A total of 149 Snubber component supports were examined during the 1994 outage.
These Augmented examinations were performed to satisfy Ginna Station Technical Specification recpxirements.
Snubber visual examinations were performed on the following items /systems and/or plant lines:
Item S stem Descri tion Steam Generator "A":
Steam Generator "B":
Plan Line P
Auxiliary Feedwater Pump Discharge Intermediate Building Lines:
3K-FW7-900-1 3A-FW7-900-1A 3J-FW7-900-1 3B-FW -900-1B 3A-FW7-900-1B 3A-FW -900-1A 3B-FW -900-1A
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
SNUBBER PROGRAM:
Cont.
Visual Examinations:
Item S stem Descri tion Turbine Driven Auxiliary Feedwater Pump Suction Line:
Steam Generator B, Blowdown Line:
Auxiliary Cooling Lines:
2-IN. Letdown Lines:
2-IN. Charging Line:
2-IN. Alternate Charging Line:
CVCS Relief Line:
Plant Line 4A-CD-150-1C 2C-MS-600-1B 4S-AC6-152 3E-AC6-152 4T-AC6-152 2A-CH4-2501 2H-CH -601 2A-CH4-151 2Q-CH5-2502 2F-CH5-2501 2E-CH-601 Reactor Coolant Pump "1B" Seal Water Line:
Reactor. Coolant Pump "1A" Seal Water Line:
Feedwater Loop "A" 6 "B" Lines:
2H-CHS-2501 2P-CH-2501 14A-FW-900-1A 14A-FW-900-1 14B-FW-900-1B 14B-FW-900-1 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1A 6B-MS-600-1A 6B-MS-600-1B 6A-MS-600-1 6B-MS-600-1
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
SNUBBER PROGRAM:
Cont.
Visual Examinations:
Item S stem D seri tion Safety Injection Lines:
Plant Line 10A-SI2-2501-A 10A-SI2-2501-B 10 -SI -151 8J-Sl
-151 4 -SI -301 Residual Heat Removal Lines:
10
-AC 10A -AC7 10A -AC7 10D -AC 10E
-AC 10G -AC 10GG-AC 8B -AC 6
-AC 6D -AC 6K -AC
-601
-2501-B
-2501-A
-601
-601
-601
-151
-601
-601
-601
-151 Service Water Lines:
Standby Auxiliary Feedwater Lines:
Pressurizer Relief Lines:
10B-SWO-125-1 8A-SWO-125-1 8L-SW -125 3C-FW-902S-1A 3C-FW-902S-1B 6AP-RC -602 6BP-RC -602 3BP-RC -602 3B -RC8-2501 3A -RC8-2501 Seal Water Return Lines:
2X-CH-2501 10
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Repox t 1990
- 1999 Interval, Second Period, Second Outage (1994)
SNUBBER PROGRAM:
Cont.
Functional Testin A total of twenty-one (21) snubbers were Functionally Tested (FT) during the 1994 outage.
From this total number, one hydraulic snubber was required due to successive/augmented testing.
Two (2)
- snubbers, one hydraulic and one mechanical, were tested due to unacceptable visual examinations.
From the eighteen (18) snubbers that were originally scheduled, fourteen (14) were mechanical snubbers and four (4) were hydraulic snubbers.
Snubber Functional Testing (FT) were performed on the following items and/or system lines during the 1994 Outage.
N Item S
tern Descri tion Steam Generator "A":
Auxiliary Feedwater Line:
CVCS-Letdown Line:
Feedwater, Loop "A" Line:
Plant Line 3A-FW7-900-1A 2A-CH4-2501 14A-FW-900-1A 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1 6B-MS-600-1B Residual Heat Removal Lines:
10-AC-601 6-AC-601 Safety Injection Line:
Standby Auxiliary Feedwater Lines:
Pressurizer Relief Lines:
4-SI-301 3C-FW-902S-1A 3C-FW-902S-1B 6AP-RC-602 3BP-RC-602 11
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
SEISMIC SUPPORT PROGRAM:
A total of Fourteen (14) Augmented or Owner Elected Seismic Supports were examined utilizing the VT-3 visual technique.
Seismic Support examinations were performed on the following items/systems and/or plant lines:
Item S stem Descri ti n Auxiliary Feedwater Line:
CVCS-Letdown Line:
Feedwater Lines:
Plant Line 2A-FW7-900-1B 2-WD-151R 14A-FW-900-1 14B-FW-900-1 Main Steam Lines:
36-MS-600-1 6C-MS-600-1A 6C-MS-600-1B 6D-MS-600-1A 6D-MS-600-1B 6E-MS-600-1A 6E-MS-600-1B 6F-MS-600-1A 6F-MS-600-1B EROSION CORROSION MINWALL PROGRAM:
A total of 115 components were examined during the 1994 Outage.
The breakdown of this total number are as follows:
Com onent e
Pipes Elbows Reducers Tees Heater Shells Total Number 55 24 12 18 6
12
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
EROSION CORROSION MINWALL PROGRAM:
Cont.
Component thickness measurements were performed on the following systems:
DWG.
NO.
M-2 M-5 M-6 M-7B M-21 M-22 M-45 M-46B M-75 M-81 M-82 M-83 M-84 M-89A M-89B M-92 M-105 S-57 SYSTEM 5A/B FW Heaters to FW Header.
Heaters 4A/B to Feedwater Suction.
Feedwater Suction to Pumps A/B.
Condensate Pump
& Heater Drain Tank Discharge to Feedwater Suction.
Steam Extraction to Preseparator Tank B
& 4B LP Heater.
Steam Extraction to Preseparator Tank A E 4A LP Heater.
Preseparator A/B to Heater Drain Tank Condenser.
Preseparator A/B to Heater Drain Tank.
Steam Extraction to 5A & SB Heaters.
Feedwater Discharge (Turbine Building).
Feedwater Discharge (Intermediate Building).
Feedwater Discharge (Intermediate Building 5.
Facade).
Feedwater to S/G 1A.
S.G.
1A Blowdown Line (Inside Containment).
S.G.
1B Blowdown Line (Inside Containment).
Main Feedwater Pump Recirculation.
Heating Steam.
Gland Steam from HP Turbine through LGS05 LGS08 to 12" Line through Valve 3881 3834.
RHR System near Valves 624
& 625.
4A k 4B Low Pressure Heater Shell.
13
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
The statements made in this report and attachments are correct and the examinations and corrective measures taken conform to the Rules of the ASME Code,Section XI.
Prepared by:
Frank A. Klepacki ISI Engineer Date Approved By:
Michael J. Saporito Manager, MaterialsEngineering and Inspection Services NDE Level III Certificate of Inservice Ins ection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspections and the State or Province of
~N w York and employed by The Hartford Steam Boiler Ins ection and Insurance Com an have inspected and/or verified the.
components described within this report and associated Attachments during the stated reporting time frame, and state to the best of my knowledge and belief, the Owner has performed examination and corrective measures described in this Report in accordance with the requirements of the ASME C'ode,Section XI.
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.
Reviewed By:
A~~( d ill~
~ zdSz-ANII's Signature Date
FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As rcquircd by thc Provisions of thc ASME Code Rules 1.Owner Roche r
6 El ri Cor E
Av R
h r NY 14 4
- 2. Plant (Name and Address of Owner)
R E
Ginna N l r Power Plant 1
Lake R
(Name and Address of Plant) n ri NY 14519
- 3. Plant Unit
- 5. Commercial Service Date ul 1 70
- 7. Compon<<nts Inspected
- 4. Owner Ccrtificatc of Authorization (ifrequired)
- 6. National Board Number for Unit N A N A Component or Appurtenance Manufacturer or Installer Manufacturer or Installer Serial No.
State or Province No.
National Board No.
(*) SEE "ATTACHMENT I" Note: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8-1/2 in. x11 in.,(2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of shccts is rccordcd at thc top of this form.
(12/86)
Mis form (E0029) may be obtained from thc Order Dept., ASME, 22 Law Drive, Box 2300,Fairficld, NJ07007-2300
8.
Examination Dates 2 28 4
to 4
1 4
- 9. Inspection Interval from lp.
APPlieenle Ndilione of deepen Xf 1666 Addenda ~N Il.
Abstract of Examinations, Include a list of examinations and a statement concerning status ofwork required for current interval.
(N )
12.
Abstract of Conditions No!cd.
(~)
13.
Abstract of Corrective Measures Recommended and Taken.
Wc certify that statements made in this report are correct and the examinations and corrective measures taken conform to thc rules ofthc ASME Code, Section XL Certificate of'uthorization No. (ifapplicable)
N A Expiration Date N A Date 19~4 Signed Rochester Gas dZ Electric Co ration Owner CERTIFICATE OP INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and thc State or Province of New York and employed by IIartford Steam Boiler Ins ection ds Insurance Cnm an of Ilartford CT.
have inspected the components dcscribcd in this Owner 's Report during the period to XW and state that to thc best of'my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner 's Report in accordance with the inspection plan and as required by the ASME Code, Section XL By signing this certificate neither the Inspector nor his employer makes any warranty, cxprcsscd or implied, conccming thc examinations and corrective measures described in this Owner 's Report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner lor any personal injury or property damage or a loss ol'any kind arising from or connected with this inspection.
4A~D 4 cVd C
Inspector
's Signature Commissions rl M45'd National Board, State, Province, and Endorscmcnts Date
(*) SEE nATTACHMENT In
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner R che r
6 El c ri r
E st Av R
h st r NY 14 4
- 2. Plant R.E.Ginna N
lear P wer Plant 150 L ke Road Ontario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N B.commercial service Date Julvulvo S.National Board Number for Unit ~NA ATTACHMENT Z A.
CLASS 1 COMPONENTS:
Al.
REACTOR PRESSURE VESSEL DRAWINGS: A-1 Summary Exam Number Categ CC CC CC 000502 B-A item Number Component CC-=amma aCCCCtCCCCC CCCCCCCCC:=aCCCCa
=aaa B1.30 RPV-A (16-32)
VESSEL-TO-FLANGE CIRC WELD NDE Component Type Exam rcfmcc
&cccccc M&
NO RECORDABLE INDICATIONS -ACCEPTABLE.
000701 B-N-1 B13.10 RPV INTERIOR VESSEL INTERIOR ASME 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE. TAKING CREDIT FOR EXAMINATION PERFORMED IN '93.
001017 B-G-1 B6. 10 NUT ¹17 CLOSURE NUTS, REMOVED(48TOT)
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001018 B-G-1 B6.10 NUT ¹18 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS
-ACCEPTABLE.
001019 B-G-1 B6. 10 NUT ¹19 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001020 B-G-1 B6.10 NUT ¹20 ASME CLOSURE-NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
"COMPONENT TYPE" ZS DEFINED AS FOLLOWS:
NASMENcc ITEM REQUIRED BY ASME SECTION XI CODE AUGN AUGMENTED PROGRAM ITEM REQUIRED BY NRC COMMITMENT "OE" ec OWNER ELECTED -
NON MANDATORY EXAMINATIONS
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 interval, Second Period, Third Outage (1994)
- l. Owner R ch r G El ri Cor E
Ave.
R h
r NY 14 4
- 2. Plant R.E.Ginna Nu l ar Pow r Plan 1
3 Lake Road Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date
~cul l 70 S.National Board Number for Unit NjA ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Number 001021 Exam Categ m
B-G-1 Item Number B6.10 Component
---mamas-=mamaam-afNS:tNSB NUT ¹21 CLOSURE t
NUTS, REMOVED(48TOT)
NDE Component Type Exam
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001022 B-G-1 B6. 10 NUT ¹22 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001023 B-G-1 B6. 10 NUT ¹23 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001024 B-G-1 B6. 10 NUT ¹24 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE 1NDZCATIONS -ACCEPTABLE.
001025 B-G-1 B6. 10 NUT ¹25 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001026 B-G-1 B6.10 NUT ¹26 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001027 B-G-1 B6.10 NUT ¹27 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h s r Gas
& El c ric Cor 8
E s Av R ch ster NY 14 4
- 2. Plant R.E.Ginna Nu l r P
w r Plan 1
Lak Road On ario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date 9~1~170 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Number 001028 Exam Categ CCCRS B-G-1 Item Number Component B6.10 NUT ¹28 CLOSURE NUTS, REMOVED(48TOT)
NDE Component Type Exam
==-a@a-saaaaaaaa aasa ASME MT 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001029 B-G-1 B6. 10 NUT ¹29 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
001030 B-G-1
~ B6.10 NUT ¹30 ASME CLOSURE P
NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001031 B-G-1 B6.10 NUT ¹31 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001032 B-G-1 B6.10 NUT ¹32 ASME CLOSURE NUTS, REMOVED(48TOT) 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
MT MT MT MT 001117 B-G-1 B6.30 STUD ¹17 CLOSURE STUD, REMOVED(48TOT)
-MT Ec UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r G
& Electri r
8 East Av Roches r NY 14649
- 2. Plant R.E.Ginna Nu lear P wer Plan 1503 Lak R ad On ari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date ~i~l 1970 6.National Board Number for Unit
~N A ATTACHMENT Z CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Exam Number Categ 001118 B-G-1 Ztem Number Component B6.30 STUD ¹18 CLOSURE STUD, REMOVED(48TOT)
Component Type ASME NDE Exam UT MT 94
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001119 B-G-1 B6.30 STUD ¹19 CLOSURE STUD, REMOVED(48TOT)
-MT
&. UT:
NO RECORDABLE ZNDICATIONS -ACCEPTABLE.
001120 B-G-1 B6.30 STUD
¹20'LOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001121 B-G-1 B6.30 STUD ¹21 CLOSURE STUD, REMOVED(48TOT)
NO RECORDABLE INDICATIONS -ACCEPTABLE. MT:
INSIGNIFICANT; TWO (2)
DZNGS IN THREADS, 7-1/8"
& 7-1/4" DOWN FROM TOP OF STUD.
APPROXIMATELY 1/16" ROUNDED << 1/64"
-ACCEPTABLE.
001122 B-G-1 B6.30 STUD ¹22 CLOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Roch r
a
& Elec ric Cor 8
East Ave Rochester NY 1464
- 2. Plant R.E.Ginna Nu lear P wer Plant 150 L k R
d n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~ul 1 70 S.National Board Number for Unit
~N ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Exam Number Categ 001123 B-G-1 Item Number Component Component Type aaatmtmtmfm amaammmamm=mammaamamma ammatttmfmfmtmfmttamtmatm B6.30 STUD ¹23 ASME CLOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001124 B-G-1 B6.30 STUD ¹24 CLOSURE STUD, REMOVED(48TOT) 94
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
UT MT 00112"5 B-G-1 B6.30 STUD ¹2S CLOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001126 B-G-1 B6.30 STUD ¹26 CLOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001127 B-G-1 B6.30 STUD ¹27 CLOSURE STUD, REMOVED(48TOT)
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001128 B-G-1 B6. 30 STUD ¹28 CLOSURE STUD, REMOVED(48TOT) 94
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h ster Gas E Electric C r 8
Eas Ave R
h r NY 1464
- 2. Plant R.E.
irma N l r P
w r Pl n 1
0 L k R a n ri NY 14 1
- 3. Plant Unit 1
- 4. owner certificate of Authorization (If Req.)
~N A S.Commercial Service Date
~Jul 1
7 S.National Board Number for Unit jNA ATTACHMENT I CLASS 1
COMPONENTS CONT.
f REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Number 001129 Exam Categ B-G-1 Item Number Component Niaa R
CRRNQICCR RCRRCRRRRR B6.30 STUD ¹29 CLOSURE STUD, REMOVED(48TOT)
NDE Component Type Exam ASME UT MT 94
-MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001130 B-G-1 B6.30 STUD ¹30 CLOSURE STUD, REMOVED(48TOT)
-MT Sc UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
00113d.
B-G-1 B6. 30 STUD ¹31 CLOSURE STUD, REMOVED(48TOT)
-MT Sc UT:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
001132 B-G-1 B6.30 STUD ¹32 CLOSURE STUD, REMOVED(48TOT)
-MT
&. UT:
NO RECORDABLE INDICATIONS
-ACCEPTABLE'01206 B-G-1 B6.40 THREADS IN FLANGE ASME STUD HOLES 16 THRU 32 94
-UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001317 B-G-1 B6.50 WASHER ¹17 ASME CLOSURE WASHERS (48TOT) 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
VT-1
R ~
E ~
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roche er
& El ri r
8 E s Av Rochester NY 1464
- 2. Plant R.E.Ginna N
lear P
w r Pl n 150 Lak R
d On ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial Service Date tulvu17 I S.National Board Number for Unit
~N ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Number 001318 Exam Categ B-G-1 Item Number B6.50 Component
&Bafmrefmfm BB
&&BN ZN&&&
WASHER ¹18 CLOSURE WASHERS (4 8TOT)
NDE Component Type Exam
?mern&
&BB6NMMW
& &&M ASME VT-1 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001319 B-G-1 B6.50 WASHER ¹19 CLOSURE WASHERS (48TOT)
ASME VT-1 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001320 B-G-1 B6.50 WASHER ¹20 CLOSURE WASHERS (48TOT)
ASME 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001321 B-G" 1 B6.50 WASHER ¹21 CLOSURE WASHERS (48TOT)
ASME 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001322 B-G-1 B6.50 WASHER ¹22 ASME CLOSURE WASHERS (48TOT) 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001323 B-G-1 B6.50 WASHER ¹23 CLOSURE WASHERS (48TOT)
ASME 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001324 B-G-1 B6.50 WASHER ¹24 CLOSURE WASHERS (48TOT)
ASME 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner R
h ster as
& El ri r
8 East Ave.
Roches r NY 1464
- 2. Plant R E.Ginna Nuclear Power Plant 1
L k Road Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date Q~l~17 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Exam Number Categ 001325 B-G-1 Item Number Component B6.50 WASHER ¹25 CLOSURE WASHERS (4 STOT)
NDE Component Type Exam QRRRSQCSCRCIR RCR RRCS ASME VT-1 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001326 B-G-1 B6.50 WASHER ¹26 CLOSURE WASHERS (48TOT)
ASME VT-1 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001327 B-G-1 B6.50 WASHER ¹27 CLOSURE WASHERS (48TOT) 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001328 B-G-1 B6.50 WASHER ¹28 CLOSURE WASHERS (4 8TOT)
ASME 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001329 B-G-1 B6.50 WASHER ¹29 CLOSURE WASHERS (48TOT)
ASME VT-1 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001330 B-G-1 B6.50 WASHER ¹30 CLOSURE WASHERS (4 STOT)
ASME VT-1 94 -VT-1:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
001331 B-G-1 B6.50 WASHER ¹31 CLOSURE WASHERS (48TOT)
ASME 94 -VT-1: NO RECORDABLE INDZCATIONS
-, ACCEPTABLE.
10
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Ro hes er s
& El c ric Cor 8
East Av R
h s r NY 14 4
- 2. Plant R.E irma Nucl r Pow r Plan 1
L k R
d On rio NY 14 1
- 3. Plant Unit 1'.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date ~Jl l vo S.National Board Number for Unit ~A ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR PRESSURE VESSEL (CONT.)
DRAWINGS: A-1 Summary Number 001332 Exam Categ B-G-1 Item Number B6.50 Component aaaaaaaaaaaaaaaaaaassaa WASHER ¹32 CLOSURE WASHERS (48TOT)
NDE Component Type Exam aassass assss ASME VT-1 94 -VT-1: NO RECORDABLE INDICATIONS -ACCEPTABLE.
001602 B-A Bi.40 RVP-HFW (16 "32)
ASME CLOSURE HEAD-TO-FLANGE CIRC WELD MT UT 94
-MT Ec UT; TAKING CREDIT THIS OUTAGE, NO RECORDABLE INDICATIONS -ACCEPTABLE. 96%'F CODE REQUIRED COVERAGE ACHIEVED.
A2.
PRESSURIZER DRAWINGS: A-4 Summary Exam Number Categ 004900 B-D Item Number Component aaaaaaa assassa aaaaaaaaaaa ssaaa B3.120 SAFNOZ ¹1 SAFETY NOZ ¹1-ZNS RAD SECT NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa ASME UT 94 -UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE. NOTE:
UT 17 DEGREE SCAN WHEN TRANSDUCER IS SKEWED FAR IN TOWARDS NOZZLE, THE INNER RADIUS IS SEEN.
005100 B-D B3.120 SAFNOZ ¹2 ASME SAFETY NOZ ¹2-INS RAD SECT 94 -UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE. NOTE:
UT 17 DEGREE SCAN WHEN TRANSDUCER IS SKEWED FAR IN TOWARDS NOZZLE, THE iNNER RADIUS GEOMETRY IS SEEN.
11
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch er as Elec ri r
8 Ea Ave R
hes r NY 14 4
- 2. Plant R.E irma Nucl ar P wer Plan 1
L ke Road Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~J l
- l. 70 S.National Board Number for Unit
~N A ATTACHMENT I CLASS 1
COMPONENTS CONT.
A3.
REACTOR COOLANT SYSTEM-LOOP A DRAWINGS: A-3B Summary Exam Number Categ 011810 B-J Item Number Component Component Type RR accRRRRa RRRR lcacRRRaaRRRcaaaRRa aaa a
ctciaatacRRRaaRRa aaa B9.12 PL-FW"XII-LT ASME LONGITUDINAL SEAM WELD NDE Exam UT PT 94 -PT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
LOWER AND UPPER 12" OF INSIDE RADIUS WAS PERFORMED.
011820 B-J B9.12 PL-FW-XII-LR LONGITUDINAL SEAM WELD'SME UT PT 94 -PT
& UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
LOWER AND UPPER 12" OF OUTSIDE RADIUS WAS PERFORMED.
A4.
REACTOR COOLANT SYSTEM-LOOP B DRAWINGS: A-3E Summary Number a
012600 Exam Categ aa B-J Item Number Component Component Type acR aa aaa aaaaRRaaaaaaaaaRR RRRRRR aRRaa'aaaa aaa B9.31 PL-FW-IV/10-RC8-2501 OE 10" BRANCH WELD NDE Exam PT UT 94 -PT:
INSIGNIFICANT; La 8 7/8",
Wa 1/2",
LINEAR 1/8" IN CAP.
L= 28 1/2, Wca 1/4, ROUND 1/16".
Lte 40 1/2, Wea 1 1/4, ROUND 1/16".
-ACCEPTABLE. UT: OTHER; NOT PERFORMED, SCHEDULE
SUMMARY
g 011000 FOR THE '95 OUTAGE.
A5.
3-IN. PRESSURIZER SPRAY LINE DRAWINGS) A-9 Summary Number 019700 Exam Categ B-J Item Number B9.21 Component NDE Component Type Exam aa-aa aaaaaaaaaaa aaaaaaaaaaaaaaaa aaaa M
ASME PT REDUCER-TO-SAFE END 94 -PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
12
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
hester Gas
& Electric r
Eas Ave R
hes r NY 1464
- 2. Plant R.E inn Nucl r
P w r Plan 150 Lake Roa nt ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul i9vo S.National Board Number for Unit NjA ATTACHMENT X CLASS 1
COMPONENTS CONT.
3-XN.
PRESSURIZER SPRAY LINE (CONT.)
DRAWINGS: A-9 Summary Exam Item Number Categ Number 021200 B-J B9.21 Component aaaaaaaaaaaaaraaaaaa a
DSW-4 ELBOW-TO-PIPE NDE Component Type Exam acara aaaaaaaaaaa aaa-ASME PT 94 -PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
021800 B-J B9.21 ESW-1 ASME PIPE-TO-ELBOW 94 - PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
PT A6.
2-ZN.
PRESSURIZER SPRAY LINE DRAWINGS s A-11 Summary Exam Number Categ cc ccr 023100 F-A Item Number Component aaaaaaa aaaaaaaaaaaaaaaaaaaara F1.10R CVU-69 RIGID HANGER NDE Component Type Exam a cc a ar cc cc cc cc ASME VT-3 SUCCESSIVE 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
023300 F-A F1.10R CVU-70 RIGID RESTRAINT ASME SUCCESSIVE 94 -VT-3: NO RECORDABLE INDZCATIONS -ACCEPTABLE.
025825 B-K-1 B10.10 CVU-1 (IA)
INTEGRAL ATTACHMENT OE PT 94 -PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
025830 F-A F1.10V CVU-1 OE VARIABLE SPRING (IA) 94 -VT-3: NO RECORDABLE INDICATIONS 6c INSIGNIFICANT; TEMP.
71 DEG. F.,
SETTING 1.4" r 231 O'S, PAINT ON SPRING CAN COVER -ACCEPTABLE.
VT-3 13
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
hester Ga 6 Ele ric Cor 8
E t Ave Roch r NY 1464
- 2. Plant R.E.Ginna Nuclear Power Plan 1
0 L k Road Ontari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N S.commercial service Date Ju~vufvo S.National Board Number for Unit N~A ATTACHMENT Z CLASS 1
COMPONENTS CONT.
A7 ~
3-IN. PRESSURIZER RELZEF LINE DRAWINGS: A-12 a
026600 B-J Summary Exam Number Categ Item Number Component aaaaaaa aaaaaaacsaaaaaaaaaaaaaa B9.21 C
REDUCER-TO-VALVE(515)
NDE Component Type Exam aaaaccaaa aaaaaaa aaaa ASME PT 94 -PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE. BASELINE EXAM., SEE M94122 ACCEPTABLE.
026700 B-J B9.21 D
VALVE(515) -TO-PZPE OE PT 94 -PT:
BASELINE EXAM., SEE M94122
-ACCEPTABLE.
A8.
4-IN.
PRESSURIZER RELIEF LINE DRAWINGS: A-13 028500 B-J Summary Exam Number Categ Item Number Component Component Type Rccc aaaaa aaaaaa aaasc aacscccscsa aacccca B9.11 M
ASME ELBOW-TO-PIPE NDE Exam UT PT 94
-PT 6c UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
A9.
4-IN. RESZD HT REMOVAL TO RPV (LHSZ)
DRAWINGS: A-14 Summary Number a
038100 Exam Item Categ Number Component aacsamcacc cccscccc aa aa aaccscacs aaccccaaaacsacs B J B9 11 F
ELBOW-TO-PIPE NDE Component Type Exam aaaaaaccscaaccmcccsc a
NO RECORDABLE INDICATIONS, INSIGNIFICANT Ec OTHER; ZD
& OD GEOMETRY, UT THICKNESS AFTER SURFACE CONDITIONING,
-ACCEPTABLE. PT:
INSIGNIFICANT & REJECT; LINEAR INDICATIONS NOT SERVICE INDUCED.
PT AFTER SURFACE CONDITIONING
-ACCEPTABLE.
14
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ch er a
& Electric r
8 Eas Av R
h r NY 1464
- 2. Plant R
E Ginna Nuclear P
w r Plan 1
03 Lake R a n ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.commercial service Date ~Jul l 70 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1
COMPONENTS CONT.
A10.
H.P.
SAFETY ZNJECTZON LINE DRAWINGS: A-20 Summary Exam Number Categ 040025 F-A Item NDE Number Component Component Type Exam atZSZZZSSZZZZ
=SZ==-=Samaria
=trna-SSZZZZSZZZ am=------aaZZSSSZZZSZ ZSZZSZZZ F1. 10R SIU-27 ASME VT-3 U-BOLT 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
041725 F-A F1.10R SIU-28 RIGID HANGER 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
A11.
2" LETDOWN TO REGEN HTX DRAWINGS: A-23 Summary Exam Ztem Numbe= -Categ Number 045800 B-J B9.40 Component
=======ZZa SZ ZZ SZ ZZ ZZ ZZ SZ SZ ZZ 26 PIPE-TO-ELBOW NDE Component Type Exam ZZ ZZ ZZ ZZ ZZ ZZ ZZ ZZ ZZ OE PT 94 -PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
045900 B-J B9.40 27 ASME ELBOW-TO-PIPE 94 PT INSIGNIFICANT S PATTER 6 WELD UNPRE PPED ACCEPTABLE PT A12.
2" LETDOWN FROM REGEN HTX DRAWINGS: A-24 Summary Exam Item Number Categ Number ZZ ZZ ZZ ZZ SZ Zt 048202 B-J B9.40 Component ZZ ZZ ZZ ZZ ZZ ZZ ZZ ZZ ZZ SS SS SS 2
PIPE-TO-TEE NDE Component Type Exam SZZZZS WMMMMZZZZZZSS ZSSSMM ASME PT 94 -PT; NO RECORDABLE INDICATIONS -ACCEPTABLE.
15
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h r
6 Ele ric Cor 8
East Ave Roches er NY 14 4
- 2. Plant R.E.Ginna Nucl ar P
w r Plan 1
0 L k Road n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.) ~A S.commercial service Date Julvul 70 S.National Board Number for Unit NjA ATTACHMENT I CLASS 1
COMPONENTS CONT.
2" LETDOWN FROM REGEN HTX (CONT ~
)
DRAWZNGS: A-24 Summary Exam Number Categ 048210 F-A Ztem Number Component SSSBBSSCSN'0CSC F1.10V CVU-133 VARIABLE SPRING NDE Component Type Exam
&&BS &
OE VT-3 EXPANDED 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE. TEMP.
72 DEG F
6 SETTING 1 1/8 ea 299g Sf BERGER PATTERSON VS1 SIZE 5.
RESOLUTION OF NCR94-021, EXPANDED EXAM FOR CVU-140 ON CLASS 2 ASME EXEMPT LINE.
048236 F-A Fl. 10R CVU-134 OE RIGID RESTRAINT EXPANDED 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE. RESOLUTION OF NCR94-021, EXPANDED EXAM FOR CVU-140 ON CLASS 2
ASME EXEMPT LINE.
048260 F-'A F1.10R CVU-135 RIGID RESTRAINT OE EXPANDED 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE. RESOLUTION OF NCR94-028, EXPANDED EXAM FOR CVU-142 ON CLASS 2 ASME EXEMPT LINE.
A13.
2" ALTERNATE CHARGZNG TO LOOP A COLD LEG DRAWINGS: A-26 e
Summary Number 052525 Exam Categ B-K-1 Item Number Component
&aa&&&
&<<am&&
&SBBSM B10.10 CVU-24 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam fmaaafmafmaatmaa=ma:aa saafmfm OE PT 94 -PT:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
052530 F-A Fl. 10A CVU-24 ASME ANCHOR (IA) 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
VT-3 16
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ches er a
& Electric r
Eas Av R
he er NY 1464
- 2. Plant R
E Ginn N l ar P wer Plant 1503 Lake Ro d n ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.Commercial Service Date
~Jul f970 6.National Board Number for Unit jN A ATTACHMENT I CLASS 1
COMPONENTS CONT.
A14.
2" ALTERNATE CHARGING TO LOOP A COLD LEG DRAW1NGS: A-26 Summary Exam Number Categ Item Number Component rS SS SS Component Type SS SS SS NDE Exam 053300 B-J B9.40 38 VALVE(383A) -TO-PIPE AUG PT UT 94 -PT 6c UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
A15.
2is ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Number Categ 055100 B-J Item Number Component SSSS SSSSSSSS4SSSSSSSSSSSS RRRRRSN B9.40 11 VALVE(393)-TO-PIPE NDE Component Type Exam AUG PT UT 94
-PT Ec UT:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
A16.
REACTOR COOLANT PUMP A DRAWINGS: A-7 Summary Number 057100 Exam Item Categ Number F-A F1.40 Component Sf&am&&
SS SS WMMMMSSSSSS EBA-1 EYEBAR NDE Component Type Exam SSSSSSSSSSSS MSSSSISSS SSSSSSSS OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS 6c INSIGNIFICANT; OIL ON EYEBAR FROM WORK ABOVE -ACCEPTABLE.
057150 F-A F1. 40 EBA-2 EYEBAR OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
17
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Electric Cor 8
E Av R
h r NY 14 4
- 2. Plant R.E.Ginna Nuclear Power Plan 1
03 Lak R
n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N B.commercial service Date
~cul l vo 6.National Board Number for Unit
~N A ATTACHMENT Z CLASS 1
COMPONENTS CONT.
REACTOR COOLANT PUMP A (CONT.)
DRAWINGS: A-7 Summary Number 057200 Exam Categ FLYWHEL Item Number Component MMB MBS&BB M&B'G-1.
14 RCP-A FLYWHEEL, BORE
& KEYWAY ID¹ 775 NDE Component Type Exam AUG PT UT 94 -UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE. PT:
INSIGNIFICANT; LINEAR PARTING LINE INDICATION TOP
& BOTTOM.
MACHINING CHATTER MARKS ON KEYWAYS. -ACCEPTABLE.
057205 FLYWHEL RG-1.14 RCP-A FLYWHEEL, EXPOSE OE AREAS ID¹ 775 94 -UT:
NO RECORDABLE INDICATIONS "ACCEPTABLE. PT:
OTHER; NOT PERFORMED, NOT REQUIRED, ONLY FOR 10 YEAR EXAMINATION.
057210 FLYWHEL RG-1.14 RCP-A ANTI-ROTATION AUG PAWLS PAWLS (11) 94 -PT: ¹1-¹8,
¹10
& ¹11 NO RECORDABLE INDICATIONS
-ACCEPTABLE.
PAUL ¹9, LINEAR INDICATION (0.35")
IN PREVIOUSLY EXCAVATED AREA ON SHAFT SURFACE SHOULDER -REJECT.
PAUL ¹9 REPLACED.
BASELINE PERFORMED.
PT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
PT UT PT 057300 RCP"A ANCHOR BOLTS OE BOLTS EXPANDED 94 -UT:
NO RECORDABLE INDICATIONS. EXPANDED EXAMINATIONOF NCR94-056.
ALEs BOLTS IN "A" RCP PADS (E,
F
& G)
WERE EXAM1NED. STUDS E-2
& G-1 ARE 12".
REST OF STUDS ARE 23 1/2N.
BACKWALL AMPLITUDE OF G-1 WAS 22 DB LESS THAN E-2
-ACCEPTABLE.
057310 F-A F1.40 LEG E SUPPORT COMPONENTS OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; CORROSION, LIGHT SURFACE RUST IN CORNER BY CROSSOVER
-ACCEPTABLE.
18
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& El c ric r
East Ave.
Roche r NY 1464
- 2. Plant R.E.Ginna Nuclear P
w r Plan 1
03 L k R
d Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N B.commercial service Date ~J1 l 70 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1
COMPONENTS CONT.
REACTOR COOLANT PUMP A (CONT.)
DRAWZNGSf A-7 Summary Number 057320 Exam Categ F-A Ztem Number F1.40 Component LEG F SUPPORT COMPONENTS OE VT-3 NDE Component Type Exam 94 -VT-3: NO 057330 F-A RECORDABLE INDZCATIONS -ACCEPTABLE.
F1.40 LEG G
OE SUPPORT COMPONENTS VT-3 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
A17
~
REACTOR COOLANT PUMP B
DRAWZNGSf A-6 Summary Exam Numbe=
Categ aaaa aaszzsaass 058120 Item Number Component aaaaaaa aaaassaaaaaaaaaaaaaaaass RCP-B ANCHOR BOLTS BOLTS NDE Component Type'xam ssssaaaaaaaaaaaazzss
NO RECORDABLE INDICATIONS, REJECT Ec OTHER;ALL STUDS ARE 23 1/2" LONG EXCEPT L-4, ll 1/2".
STUD N-2, INTERMZTTENT INDICATION AT 19.3",
BACKWALL REFLECTION AT 23.5".
NON-CODE SERVICE INDUCED REJECT AT 19.3" NCR94-056 GENERATED. USE-AS-IS PER ENGINEERING, RELOOK IN '95.
A18.
2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Number Categ aazsss ss 070300 Item Number Component aaazsssszssaaaaaaassssmzzmazsaa V-392A (BOLTING) 2" COPES-VULCAN CONTROL VALVE NDE Component Type Exam a ss ss a a ss zz OE VT-1 94 -VT-1: STUDS
& NUTS BASELINE, NO RECORDABLE INDICATIONS
-ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner R
h s er
& El ric r
8 E s Ave.
R ches r NY 1464
- 2. Plant R
E Ginna Nuclear Power Plant 1503 Lak R
Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial Service Date
~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1
COMPONENTS CONT.
A19.
2" ALTERNATE CHARGING TO LOOP A COLD LEG DRAWINGS: A-26 Summary Exam Number Categ 070400 Item Number Component asisiss aaaa V-392B (BOLTING) 2" COPES-VULCAN CONTROL VALVE NDE Component Type Exam ssssaa aassaaaa aass OE VT-1 94 -VT-1: STUDS
& NUTS BASELINE EXAM, NO RECORDABLE INDICATIONS -ACCEPTABLE.
B.
CLASS 2
COMPONENTS:
B1.
2-ZN.
PRESSURIZER SPRAY LINE DRAWINGS: A-11 Summary Exam 022400 Item NDE Number Component Component Type Exam aaaaaaa aaaaaaaaaaassaaaaaaaaaa aaaaaaaaaaaassassa aaaa 6A OE PT ELBOW-TO-PIPE 94 PT INSIGNIFICANTa POROSITY
¹1) 'a8 9
Wa 1/4 UP a ROUND 1/32"
- DIAMETER, 3
PORES.
¹2)
LalONN Wa 1/4" UP, ROUND 1/16"
- DIAMETER, 1
PORE.
ALL ACCEPTABLE.
022425 CVU-64 GUIDE 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; 6 HILTI
- BOLTS, DRAWING INDICATES ONLY 4 -
DCR GENERATED -ACCEPTABLE.
022600 CVU"66 OE GUIDE 94 -VT-3:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
20
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner Roches er a
El ri r
8 Eas Av R
h r NY 1464
- 2. Plant R
E irma Nuclear Power Plan 1
0 L k Road n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date Julvuivo 6.National Board Number for Unit ~NA ATTACHMENT Z CLASS 2
COMPONENTS CONT.
B2.
2" LETDOWN FROM REGEN HTX DRAWINGS: A-24 Summary Exam Number Categ 048278 Item Number Component Component Type CVU-140 U-BOLT OE aaaaaa a
aa aaaaaaaaaa aaaaaaaaaaaa aaa NDE Exam VT-3 94
- VT-3: REJECT; NUT MISSING ON U-BOLT, NCR 94-021 GENERATED.
NUT REPLACED UNDER WO ¹ 19401108.
VT-3: RE-EXAM; NO RECORDABLE INDICATIONS -ACCEPTABLE.
SUPPORT ON ISI EXEMPT LINE.
PERFORMED OWNER ELECTED EXPANSION FOR NON-CODE SERVICE INDUCED REJECT.
B3.
2a ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Ztem 054200 NDE Component Component Type Exam aaaaaaaaaaaaaaaassaassssa aaaaassaaaaaaaaaa aaaa CVU-51 OE VT-3 VARIABLE SPRING SUCCESSIVE 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE. TEMP.
74 DEG. F.,
SETTING 62 ¹'S.
B4.
PULSE DAMPENER DRAWINGS: B-6 Summary Exam Item Number Categ Number assaaa assssssssssss 074900 C-A C1.10 NDE Component Component Type Exam assa aaassaaaaaaaaaaaaa aaaaaaaaaaaaaaaa aaa-CF-2 ASME UT INLET SHELL-TO-BAFFLE WELD 94
-UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
83%
CODE COVERAGE OBTAINED. RELIEF REQUEST ¹ 22 GENERATED.
21
R ~ E.
GZNNA NUCLEAR POWER PLAHT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Rochester Ga Electric r
8 East Ave.
Roch er NY 1464
- 2. Plant R
E irma Nuclear Pow r Plant 1
0 Lake R ad Ontari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date
~Jul 1
7 6.National Board Number for Unit N~A ATTACHMENT I CLASS 2
COMPONENTS CONT.
B5.
SEAL WATER INJECTION FILTER B DRAWINGS'-7 Summary Exam Number Categ 078620 Item Number Component SUPPORT LEG 81 SUPPORT (IA)
HDE Component Type Exam aasm==--ssmatmtms--s aassa OE VT-3 94 -VT-3:
NO RECORDABLE IND1CATIONS -ACCEPTABLE.
078700 SUPPORT LEG S1 (IA)
OE INTEGRAL ATTACHMENT PT 94 -PT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; S.W.
FILLET HAS A 1/8" PORE 3 1/2" FROM TOP OF FILTER & A 1/16" PORE 3
3/4" FROM TOP OF FILTER -ACCEPTABLE. N.E. FILLET WELD, NO RECORDABLE INDICATIONS
-ACCEPTABLE'6.
RESIDUAL HEAT REMOVAL PUMP A DRAWIHGS: B-28 Summary Exam Number Categ 078930 Item Number Component Component Type SS&&
&SSASN SN&M& SSSSMfNM&&
RHR PUMP A SHELL OE BOLTING END SHELL BOLTING (20)X(1.125")X(5 3/4")
NDE Exam VT-1 MT UT 94 -VT-1: NO RECORDABLE INDICATIONS & INSIGNIFICANT; 20 STUDS IN PLACE APPEAR TO BE CARBON STEEL AS PREVIOUSLY NOTED IN '85
-ACCEPTABLE. MT:
PERFORMED WHEN REMOVED-NOT REMOVED,,
NOT PERFORMED.
UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
B7.
MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Number atmar 079700 Exam Ztem Categ Number F-A F1.20S Component MSU-3 MECHANICAL SNUBBER (IA)
NDE Component Type Exam OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; VISUAL INSPECTION OF 8
LUGS WELDED TO MAIN STEAM LINE -ACCEPTABLE.
22
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Ga
& El ri or 8
Ea Av R
h ster NY 1464
- 2. Plant R
E Ginna Nuclear Power Plan 1503 L k R
d n ario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial service Date ~cl 1
70 6.National Board Number for Unit jNA ATTACHMENT I CLASS 2
COMPONENTS CONT.
MAIN STEAM LOOP A INSIDE CV (CONT.)
DRAWINGS: B-8 Summary Number 079750 Exam Categ C-C Item Number C3.20 Component Component Type M ta MM BB BB BftB BB BB&
MSU-3 (IA)
ASME INTEGRAL ATTACHMENT NDE Exam MT 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
B8.
MAZN STEAM LOOP A OUTSIDE CV DRAWZNGSv B-9 Summary Number 080650 Exam Categ C-F-2 item Number Component a-a--a-
-==aamaaaaaBBBBaaaBBBBBBBfafB C5.52 DL1 NDE Component Type Exam ASME UT VT-1 MT ELBOW LONGITUDINAL WELD 94 -VT-1, MT & UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
082025 F-A F1.20S MSU-40 OE MECHANICAL SNUBBER (ZA)
VT-3 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
082030 C-C C3.20 MSU-40 (ZA)
ASME INTEGRAL ATTACHMENT 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
MT B9.
MAIN STEAM LOOP B OUTSZDE CV DRAWINGS: B-10A 086825 F-A Summary Exam Number Categ Item Number Component Component Type
5:aaa=
==-=-aafBBBBBafmaaaaaaaaaaa aaaaaBBBBafaaBBBBfmaaa F1.20S MSU-16 OE MECHANZCAL SNUBBER (IA)
NDE Exam VT-3 94 -VT-3:
NO RECORDABLE ZNDZCATZONS & INSIGNIFICANT; LIGHT RUST
& PIGEON FECES
-ACCEPTABLE.
23
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Electri r
8 East Ave Roches r NY 1464
- 2. Plant R E.Ginn Nuclear Pow r Plan 1
0 L ke Road Ontari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date
~ul
~1 70 6.National Board Number for Unit
~N A ATTACHMENT I CLASS 2
COMPONENTS CONT.
MAZN STEAM LOOP B OUTSZDE CV DRAWINGS: B-10A 086830 C-C Summary Exam Number Categ Item Number C3.20 Component MSU-16 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam
&&XX&MMCt
&CRM M
-MT:
NO RECORDABLE INDICATIONS & INSZGNIFZCANT; HEAVY RUST ON PIPE,
> 90%'OVERAGE OBTAINED DUE TO CLAMP
-ACCEPTABLE.
086900 F-A F1.20V MSU-17 OE VARIABLE SPRING SUCCESSIVE 94 -VT-3: NO RECORDABLE INDICATIONS & ZNSIGNIFZCANT;- PIGEON
- FECES, TEMP.
> 250 DEG. F.,
SETTING 8616 ¹'S,
-ACCEPTABLE.
VT-3 087200 F-A F1.20V MSU-20 OE VARIABLE SPRING SUCCESSIVE 94 -VT-3:
NO RECORDABLE INDICATIONS, INSIGNIFICANT & OTHER; DEFLECTION TAG HELD ON BY 1/16" WIRE & PIGEON FECES.
LACK OF THREAD ENGAGEMENT (1/2" TO 3/4")
ON LOCKING NUT. ACCEPTABLE PER '91 EXAM & NCR91-032, TEMP.>150 DEG. F.,
SETTING 10K LBS
-ACCEPT.
087425 F-A F1.20S MSU-22 MECHANICAL SNUBBER (IA)
OE 94 -VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
087430 C-C C3.20 MSU-22 (IA)
INTEGRAL ATTACHMENT 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch s
r a
El ri r
E s Av R chester NY 1464
- 2. Plant R.E Ginna Nuclear Power Pl n 1503 Lak R
ntari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date $~1~17 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2
COMPONENTS CONT.
B10.
MAIN STEAM LOOP B 6-ZN.
RISERS DRAWINGS'-10 Summary Exam Number Categ 090810 Item Number Component L3-BC-4A-BT BOLTZNG ((2ss)
NDE Component Type Exam aaaaaaassssssssssssa OE VT-1 MT UT 94 -VT-1 5: UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. MT:
OTHER; MT TO BE PERFORMED WHEN BOLTS ARE REMOVED, BOLTING NOT REMOVED.
Bll.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B"11 Summary Exam Number Categ ac 091250 F-A Item Number F1.20R Component Component Type aaaaaaaaaaaaaaaassaaaass aaassaaaassaa aaaa FWU-14 OE RIGID RESTRAINT NDE
~
Exam VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS-ACCEPTABLE.
812.
FEEDWATER LOOP A INSIDE CV DRAWINGS s B-12 Summary Exam Ztem Number Categ Number 092450 F-A F1.20S NDE Component Component Type Exam aaaaaaaaaaaaaaaaaaaaaa aa aaassaaaaaaaaa aaa FWU-5 OE VT-3 HYDRAULIC SNUBBER (IA) 94 -S/N 2500-10-152, TEMP.
74 DEG. F.,
SETTING 2 5/8"s HSSA-10. VT-3:
NO RECORDABLE INDZCATIONS -ACCEPTABLE.
092455 C-C C3.20 FWU-5 (IA)
ASME INTEGRAL ATTACHMENT MT 94
-MT: NO RECORDABLE INDICATIONS -ACCEPTABLE.
25
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Xnspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h s er Ga Electri r
8 Eas Av R
hes r NY 14 4
- 2. Plant R.E irma N
1 r
P w r Pl n 1
L k R ad Ontario NY 14 1
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul l vo S.National Board Number for Unit ~NB ATTACHMENT I CLASS 2
COMPONENTS CONT.
PEEDWATER LOOP A INSIDE CV (CONT.)
DRAWINGS: B-12 Summary Number 093400 Exam Categ C-F-2 Item Number Component
$$a $$ ci $$a C5.51 DD3 PIPE-TO-ELBOW NDE Component Type Exam a$ $ $$ $$aaaaa
$$ $$ aic ASME RT VT-1 MT 94 -VT-1 & MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. RT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; MINOR EROSION UPSTREAM AND DOWNSTREAM -ACCEPTABLE.
093900 C-F-2 C5.51 DD7 ASME RT VT-1 MT PIPE-TO-ELBOW 94 -'vi-l, MT & RT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B13.
PEEDWATER LOOP B OUTSZDE CV DRAWXNGS: B-14 Summary Exam Ztem Number Categ Number aa$ $ a a
aarraaaa 094800 C-F-2 C5.51 Component Component Type aa$ $ $$ ceacaa aaaaaa aca ac$ $$ aa$ $
ASME N1 NDE Exam RT VT-1 MT ELBOW-TO-PIPE 94 -VT-1, MT & RT:
NO RECORDABLE ZNDICATIONS; -ACCEPTABLE.
B14. H.P.
SAFETY XNtTECTION LZNE 8B-SZ-301A DRAWINGS: B-15 Summary Exam Number Categ a $$ a 101400 C-F-1 Item Number Component Component Type NDE Exam 6M OE PIPE-TO-PIPE (BA TANK 1)
PT UT aaaaaaa aaaaaaaaaaaaaaaaaaaaaa aaaaaaaaaaa$
$ $$ $$aa aaaa 94 -PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. NOTE:
UT LAM PERFORMED IN '85.
26
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Rochest r a
& El ctric Cor E
Av R
h r NY 1464
- 2. Plant R.E.Ginna N clear Power Plant 1503 Lak R a n ario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date gy~11~70 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2
COMPONENTS CONT.
B15 ~ 6-ZN.
RESZD HT REMOVAL TO RPV (LHSZ)
DRAWINGS: B-18 Summary Exam Number Categ 112900 F-A Ztem Number Component a@a aaaaar aalu aaaa---aa F1.20R RHU-21 RIGID SUPPORT (IA)
NDE Component Type Exam
--maaaam=maaammss ssaa OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
112905 C-C C3.20 RHU-21 (IA)
ASME INTEGRAL ATTACHMENT PT 94 -PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B16. H.P.
SAFETY INJECTION LINE 8J-SZ-151 DRAWINGS: B-19 Summary Number 125300 Exam Categ F-A Item Number Component
-=amam-
=mmammzxssamsass ammm==mm Fl. 20R RHU-124 RIGID SUPPORT (IA)
NDE Component Type Exam aaaassa
=aaaa---
massa OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
125305 C-C C3. 20 RHU-124 (IA)
ASME INTEGRAL ATTACHMENT 94 -PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
PT B17. H.P.
SAFETY INJECTION LINE 8H-SZ-301 DRAWINGS: B-16B Summary Exam Number Ca teg
@san==
aasamss 126200 C-F-1 1tem Number Component
--aaaaa maaaaaaaaaaasaaaaaaaama 12R (WELD 38D)
NDE Component Type Exam MMMMRRIRRRRSW MMM M
&&ISSS OE PT UT TEE-TO-TEE 94 -PT Sc UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
27
R, E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994)
- 1. Owner R ches ex Gas
& El ri r
8 E
Av R
h st r NY 1464
- 2. Plant R E.Ginn Nuclear Power Plant 1503 Lake R ad Ontario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul 1
7 6.National Board Number for Unit N~a ATTACHMENT 1 CLASS 2
COMPONENTS CONT.
B18.
RESIDUAL HEAT REMOVAL LINE 8FF-AC-151 DRAWINGS: B-20 Summary Exam Number Categ 126900 Item NDE Number Component Component Type Exam Dararaaa RR CSSSSRSDCDDDDCCDSRDRRDDDRS RRCDRSDRSCDDRSRSDCRSDRS DDDRS RHU-66 OE VT-3 VARIABLE SPRING 94 -VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT -
NO SPACER ON BOTTOM PIPE CLAMP - NOT REQUIRED BY CATALOG & MECH.
ENG.
LOCK NUT ON UPPER CLAMP DOES NOT REQUIRE FULL THREAD ENGAGEMENT -ACCEPTABLE. TEMP.
65 DEG. F.,
SETTING 3/8".
B19.
RHR PUMP A SUCTION LINE DRAWINGS: B-20A Summary Exam Item Number Categ Number aaaaaa aaassaa aaaraaa 129500 NDE Component Component Type Exam DCCDDRIDDDRRDDRRDRSRRDRSCCDD DRSRSRSRRRRRRDDDRSRSCDDD C
RHU-73 OE VT-3 RIGID RESTRAINT 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
129700 RHU-72 OE MECHANICAL SNUBBER 94 -VT-3:
NO RECORDABLE ZNDICATZONS; SETTING 3 1/16" TEMPERATURE 62 DEG. F.,
-ACCEPTABLE.
B20.
RESIDUAL HEAT REMOVAL LINE 10C-AC-601 DRAWINGS: B-20A Summary Exam Number Categ 137000 C-F-1 Item Number Component Component Type PIPE-TO-TEE aaaaaa aaaassasa aasmaaaaaaa aaa aaaaaaraaaaaaaaa 1
NO RECORDABLE INDICATIONS -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & GEOMETRY; INDICATION 360 DEGREES ZS COUNTERBORE GEOMETRY -ACCEPTABLE. OTHER:
UT LAM; PERFORMED IN '85
-ACCEPTABLE.
28
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Elec ric Cor 8
E s Ave R
h s r NY 1464
- 2. Plant R
E irma Nu lear P
w r Plan 150 Lake Road Ontari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial service Date
~Jul l v S.National Board Number for Unit NjA ATTACHMENT I CLASS 2
COMPONENTS CONT.
RESIDUAL HEAT REMOVAL LINE 10C-AC-601 (CONT.)
DRAWINGS: B-20A Summary Exam Item Number Categ Number Component mme mss mmssssesma mmmmmmm
=mmmmmmfmtmtssmssfmmmtsssfmmmum 137100 F-A F1.20V RHU-67 VARIABLE SPRlNG NDE Component Type Exam SSBSSSM SSSS MSSM OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; TEMP.
69 DEG. F.,
SETTING 1.1" em 2760¹'S, CHIPPED PAINT, PAINT ON SCALE.
SPRING CAN ROD IS 1/4" FROM MOTOR ON VALVE 704A.
PAINT REMOVED FROM ROD, NO APPARENT WEAR AT THIS TIME
-ACCEPTABLE.
137800 F-A F1.20V RHU-68 VARIABLE SPRING (IA)
OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT; TEMP.
62 DEG. F.,
SETTING 1.1".
BORON CONTAMINATION ON BASE PLATE.
BORON CONTAMINATION AND SLIGHT CORROSION ON SPRING
-ACCEPTABLE.
137805 C-C C3.20 RHU-68 (IA)
INTEGRAL ATTACHMENT ASME PT 94 -PT:
REJECT; INNER CROTCH AREA OF INTEGRAL ATTACHMENT IS NOT WELDED FOR 1", ORIGINAL CONSTRUCTION, NOT SERVICE INDUCED. NCR94-016 GENERATED.
PT:
RE-EXAM. WELD AT Lem 4-4 1/2, AND Lem 8-9 1/2, SUFFICIENT PER ENG.,
NO RECORDABLE INDICATIONS; -ACCEPT.
B21.
RESZDUAL HEAT REMOVAL LINE 8E-AC-601 DRAWINGS: B-24 Summary Exam Number Categ 158400 C-F-1 Item Number Component Component Type 8
OE ELBOW-TO-NOZZLE (RHR HTX A)
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT; NO RECORDABLE INDICATIONS & GEOMETRY; INTERMITTENT ROOT GEOMETRY -ACCEPTABLE.
e
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interva1, Second Period, Third Outage (1994) 1.
Owner Rochester Ga
& Elec ric r
E t Ave Roch ster NY 1464
- 2. Plant R
E Ginna Nuclear Pow r Pl nt 1
L k R
n rio NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial service Date Julvulvc S.National Board Number for Unit jNA ATTACHMENT I CLASS 2
COMPONENTS CONT B22. H.P.
SAFETY INJECTION PUMP C SUCTION LINE DRAWINGS: B-16B Summary Exam Number Categ Cmt CC C SIC 160570 C-F-1 Item Number Component C5.21 7
SXSX4 TEE-TO-90 ELBOW Component Type OE NDE Exam PT UT 94 -PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & GEOMETRY; COUNTERBORE GEOMETRY
-ACCEPTABLE. AVERAGE COVERAGE OBTAINED 85%',
OWNER ELECTED EXAMINATiON.
160670 C-F-1 C5.21 21 PIPE-TO-RFWN FLANGE (SI PUMP C
XN)
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT; NO RECORDABLE INDXCATXONS; -ACCEPTABLE. UT60 SCAN NOT POSSIBLE DUE TO ADJACENT WELD BEING TOO CLOSE, AVERAGE COVERAGE ACHIEVED WAS 63%'UE TO LIMITATIONS. OWNER ELECTED EXAMINATION -ACCEPTABLE.
B23. H.P.
SAFETY INJECTION PUMP A SUCTION LINE DRAWINGS: B-16B Summary Exam Number Categ CCCC SN 160750 F-A Item Number Component CCCCCCC BBCCCCCCCCCCCCCCCCCCCCC F1. 20V RHU-118 VARIABLE SPRING NDE Component Type Exam SSCCBBCCCCCCCCCC BBC OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS & REJECT; EYE ROD IS BENT 3/4N FROM NORMAL, NOT SERVICE INDUCED. NCR94-024 GENERATED.
INTERIM USE AUTHORIZED. NO EVIDENCE OF CRACKING
&. IS EXPECTED TO CARRY DESIGN LOAD OF 154 O'S.
RE-EXAM IN
'95
-ACCEPTABLE.
160860 C-F-1 C5.21 31 90 ELBOW-TO-RFWN FLANGE (SI PUMP A IN)
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & GEOMETRY; ID GEOMETRY, COUNTERBORE.
AVERAGE COVERAGE OBTAINED IS 92%
-ACCEPTABLE.
30
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ches r
a
& El ri r
8 E
Av Ro h ster NY 1464
- 2. Plant R E.Ginna Nuclear Power Plant 1
03 L ke Road On rio NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~61 f 70 6.National Board Number ior'nit N~A ATTACHMENT I CLASS 2
COMPONENTS CONT.
B24. H.P.
SAFETY ZNECTZON LINE 3A-SZ-1501 DRAWINGS: B-37 Summary Exam Number Categ 161190 F-A Item Number Component CS SSSC CRBCSSRSSSRRSSSCSCSS RCDQ CSCS F1.20R SIU-79 RIGID RESTRAINT (IA)
NDE Component Type Exam AC=-aaSSRCSSfmamamaaa imp=a OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
161191 C-C C3. 20 SIU-79 (IA)
ASME INTEGRAL ATTACHMENT PT 94 -PT:
INSIGNIFICANT; INDICATION ¹1, 1/16" ROUND BOTTOM EAST LUG, NORTH SIDE 1 1/2" FROM GUIDE. INDICATION ¹2, 3/32" ROUND BOTTOM WEST LUG, NORTH SIDE 1 1/2" FROM GUIDE.
-ACCEPTABLE.
b25. H.P.
SAFETY IMECTZON LINE 4D-SI-1501 DRAWINGS: B-38 Summary Exam Item Number Categ Number RSSS CS SSCS MMMMMSSSC 161630 F-A F1.20R Component SC&M&MM&
SC&&
>>SR&&MMCSSS S1U-38 RIGID RESTRAINT (IA)
NDE Component Type Exam SCRSCSRSSRR SSSSSSSSSR CS SSCSCD OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
161631 C-C C3.20 SIU-38 (IA)
ASME INTEGRAL ATTACHMENT PT 94 -PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B26. H.P.
SAFETY ZNECTZON LINE 2A-SI-1501 DRAWINGS: B-39 Summary Exam Item Number Categ Number SSSS CSSS SSMMWMSSSC 162030 C-F-1 C5.30 NDE Component Component Type Exam SC fma S aIIa CS SC SC a a a a SS SC SS SR SR a a a a SS SC SC CS SS a aIIa a a = SC a a =a 23 ASME PT PIPE-TO-VALVE(878A) 94
-PT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
31
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches er Ga 6 Electric r
8 Ea Ave.
Ro hester NY 1464
- 2. Plant R
E inn N
1 r
P w r Plan 150 Lake R
n ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5 Uo.mmercial service Date
~Jul l vo S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2
COMPONENTS CONT.
B27. H.P.
SAFETY INJECTION LINE 4E-SI-1501 DRAWINGS: B-42 Summary Exam Number Categ aaaaa-aaaaaaa 163930 C-F-1 Ztem Number Component aaaassaa aaaassisss assssssa assassss C5.21 31 ELBOW-TO-PEN 101 (OUTCV)
NDE Component Type Exam ssass a
assssssaaaa aassa OE PT UT 94 -PT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; CONSTRUCTION LINE-UP LUG PORES, ( 1/64" 6c 1/32"
-ACCEPTABLE.
UT:
NO RECORDABLE INDICATIONS 6 GEOMETRY; INTERMITTENT ROOT
- GEOMETRY, 360 DEGREES
-ACCEPTABLE. UT THICKNESS -ACCEPTABLE.
163940 C-F-1 C5.21 32 PEN(101)-TO-ELBOW
( INCV)
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS &. GEOMETRY; ROOT GEOMETRY
-ACCEPTABLE.
164050 F-A F1.20R SIU-21 RIGID HANGER ASME VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B28. H.P.
SAFETY INJECTION LINE 2S-SZ-2501 DRAWINGS: B-44 Summary Exam Ztem Number Categ Number 164680 C-F-1 C5.30 NDE Component Component Type Exam aaaaaaaaaaaaassaaaaaaaa aassaaaaaaassaaaaa aaaa 17 OE PT PIPE-TO-ELBOW 94 -PT; NO RECORDABLE INDICATIONS; -ACCEPTABLE.
32
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner R ch ster Gas
& El ri r
Ea t Ave.
R h
er NY 1464
- 2. Plant R
E irma Nu lear Power Pl n 1
03 L k R
d On ario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date $~1~170 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2
COMPONENTS CONT B29. H.P.
SAFETY INJECTION LINE 2R<<SI-2501 DRAWINGS: B-45 Summary Number 165000 Exam Categ C-F-1 Ztem Number Component Component Type CCS R
RCCCQR XR CSS C
SZSCOC
'COOSCRRCCDSXQ C5.30 20 OE VALVE 878E TO PIPE NDE Exam PT 94 -PT; NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B30.
RESIDUAL HEAT EXCHANGER B DRAWINGS'-109 Summary Exam Number Categ 169220 C-A Item Number Component mmmmmmm mmmarszs mmmmmmm=mmmmzs-C1.20 LHLSWRHE-1B LOWER HEAD-TO-LOWER SHELL CIRC WELD NDE ASME UT 94 -UT:
NO RECORDABLE INDICATIONS & GEOMETRY; GREATER THAN 90~o COVERAGE OBTAINED ROOT GEOMETRY ACCEPTABLE, B31.
CONTAINMENT SPRAY PUMP A DRAWINGS: B-46 Summary Exam Item Number Categ Number ZC CS XR&
172000 F-A F1.40 Component Component Type CRRNQC$ 3 RCRCRQCCC QRSQQ CSRS?XSSRRRQCCRt SIAPSC1-B1 ASME WELDED BASE - LINEAR TYPE SUPPORT NDE Exam VT-3 94 -VT-3: NO RECORDABLE INDZCATZONS & INSIGNIFICANT; CORROSION, LIGHT SURFACE RUST
& WELD SPATTER - INTERMITTENT.
NO PRINTS AVAILABLE, EVALUATION DONE "AS FOUND" -ACCEPTABLE'.
33
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Elec ric Cor E
Av R ch t r NY 1464
- 2. Plant R
E irma Nu lear P
w r Pl nt 150 Lake Road n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date ~1~17 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2
COMPONENTS CONT.
B32. H.P.
SAFETY INJECTION PUMP B DRAWINGS: B-42 Summary Exam Number Categ aass ssaaa 172400 F-A Ztem NDE Number Component Component Type Exam aaaaaa assaaa aaaaaaaaaaaaaass aaaaaaaaaa aaaaa ssaaa F1.40 SIAPSI-3 ASME VT-3 WELDED BASE - LINEAR TYPE SUPPORT 94 -VT-3; NO RECORDABLE INDICATIONS & INSIGNIFICANT, LIGHT SURFACE RUST - INTERMITTENT, NO DRAWINGS AVAZLABLE, EVALUATION WAS DONE "AS FOUND" -ACCEPTABLE.
B33.
SERVICE WATER LINE 8K-SW-125 DRAWINGS: B-51 Summary Exam Z tern Number Categ Number a a a a a a Rs 173610 C-C C3.20 NDE Component Component Type Exam aaaaaassassassssassaaa aaaa RRRsassssaaaa a
aa ssssssa SWU-367 (IA)
ASME PT INTEGRAL ATTACHMENT 94 -PT:
NO RECORDABLE INDICATIONS) -ACCEPTABLE.
173620 F-A F1.20R SWU-367 OE RZGID RESTRAINT (IA)
VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B34.
SERVICE WATER LINE 8E-SW-125 DRAWINGS: B-52B Summary Exam Number Categ a a a ss 174840 C-F-2 Item Number Component Component Type aaaaaaa aassaaaaaaaaaaaaaaaaaaa aaassaaaaaaaaaaaa 29 OE NDE Exam aaaa PT UT TEE-TO-REDUCER 94
-PT
& UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. GREATER THAN 90%'ODE REQUIRED COVERAGE ACHIEVED.
175130 C-F-2 45 OE PT UT ELBOW-TO-PIPE 94
-PT & UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. GREATER THAN 90%'ODE REQUIRED COVERAGE ACHIEVED.
34
R.
E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h r Gas
& El ri Cor E
Av R
h r NY 14 4
- 2. Plant R.E irma Nucl r
P w r Plan 1
Lake Road ntario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date
~J 1
1997 I 6.National Board Number for Unit
~N A ATTACHMENT 1 CLASS 2
COMPONENTS CONT.
~
B35.
SERVICE WATER LINE 8C-SW-125 DRAWINGS: B-53 Summary Exam Number Categ CC 175280 C-C Item Number Component
?Z C3. 20 SWU-371
( IA) 1NTEGRAL ATTACHMENT NDE Component Type Exam KDDCSSCK
&&DR5CS CCRt&%
-MT: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
175290 F-A F1.20R SWU-371 OE RIGID RESTRAINT (IA)
VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
B36.
STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV'RAWINGS: C-20 Summary Exam Numbe=
Categ 176100 Item Number Component Component Type aaasaaa a===-aaaaasaaaaazcaaaaa asaaaa==-ssaaaaa AFU-216 (AFW-18)
OE GUIDE NDE Exam VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
==mama
,raaa 176480 Item Number Component AFU-202 (AFW-07)
GUIDE (IA)
NDE Component Type Exam RSZEC5CCMMW MRS&&& 25ZRWM OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
176481 AFU-202 (AFW-07)
(IA)
-MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
35
R. E.
GZNNA NUCLEAR POWER PLANT Xnservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner R
h r
s
& Elec ri r
8 Eas Ave.
R he r NY 14 4
- 2. Plant R
E Ginna Nuclear Power Plan 1
0 Lak R
d Ontari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date Qi~l 1970 6.National Board Number for Unit
~N A ATTACHMENT Z C.
CLASS 3
COMPONENTS:
Cl.
NON-REGENERATIVE HEAT EXCHANGER DRAWINGS'-2 Summary Exam Number Categ 072200 Ztem Number Component aaaaaaa aaaaaaaaaaaaaaaaaaraaa SSFWNRHX FLANGE-TO-SUPPORT
~
SKIRT WELD - IA NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa OE VT-1 94 -VT-1; NO RECORDABLE INDICATIONS & INSIGNIFICANT, LIGHT SURFACE RUST -
ENTXRE WELD - ACCEPTABLE.
C2.
Dl'ESEL GENERATOR A INTAKE DRAWXNGS: C-39 Summary Exam Number Categ 50010')
J3-B Item Number D2. 20 Component Component Type aaaaaaaaaaaaaaaaaaaar ar aaaaaaaa aa DGZN-1A (IA)
ASME INTEGRAL ATTACHMENT NDE Exam VT-3 94 -VT-3: NO RECORDABLE INDICATIONS & REJECT; ORIGINAL CONSTRUCTION POOR WORKMANSHIP ON BOTTOM WELDS. NCR94-054 GENERATED. USE-AS-IS PER ENGINEERING VIA DESIGN ANALYSXS DA-ME-94-045 RO,
-ACCEPTABLE. REJECT NOT SERVICE INDUCED.
500105 F-A F1.30R DGIN-1A ASME RIGID SUPPORT (IA) 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; WORKMANSHIP ON A FEW OF THE ANGLE IRON SUPPORT TO BUILDING WELDS ARE POOR.
SUPPORT IS IN GOOD CONDITION, -ACCEPTABLE.
C3.
DZESEL GENERATOR B INTAKE DRAWINGS'-40 Summary Exam Ztem Number Categ Number aaraaa aaraaaa aaaaaaa 500110 D-B D2.20 NDE Component Component Type Exam rara aaaar rara araaa aaaaa aaaaaaaaa raa DGIN-1B (IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 -VT-3: NO RECORDABLE INDICATIONS & ZNSZGNZFZCANT; THIS SUPPORT IS ACCEPTABLE FOR WORKMANSHIP AND NO INDICATIONS
'ROM SERVICE.
NO DRAWING IS AVAILABLE FOR ACCEPTANCE TO DRAWING, -ACCEPTABLE.
36
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h er a
& Elec ri r
Ea t Av R
h s r NY 14 4
- 2. Plant R
E Ginna Nucl ar P
w r Pl nt 1
3 Lake Ro d On ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date
~J l
~1 7
6.National Board Number for Unit
~N A ATTACHMENT Z CLASS 3
COMPONENTS CONT.
DZESEL GENERATOR B INTAKE (CONT.)
DRAWINGS: C-40 Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 500115 F-A F1.30R DGIN-1B OE RIGID SUPPORT (IA) 94 -VT-3: NO RECORDABLE ZNDICATIONS & INSIGNIFICANT; WORKMANSHIP ON ANGLE IRON SUPPORT TO BUILDING WELDS ARE
- POOR, SUPPORT ZS IN GOOD CONDITION, -ACCEPTABLE.
C4.
COMP. COOL. PUMPS DISCH.TO COMP. COOL.HT EX DRAWINGS: C-2 Summary Exam Number Categ 500200 D-B Item Number Component D2.20 CCU-86 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. BASELINE EXAMINATION FOR MODIFICATION UNDER EWR 5284.
500205 F-A F1. 30R CCU-86 RIGID SUPPORT (IA)
OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. BASELINE EXAMINATION FOR MODIFICATION UNDER EWR 5284.
500230 D-B D2.20 CCU-89 (IA)
INTEGRAL ATTACHMENT OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE. BASELINE EXAMINATION FOR MODIFICATION UNDER EWR 5284.
500235 F-A F1.30R CCU-89 RIGID SUPPORT (IA)
OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. BASELINE EXAMINATION FOR MODIFICATION UNDER EWR 5284.
37
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R chester as
& El ri r
Eas Ave Rochester NY 1464
- 2. Plant R.E.
irma N Cl ar Ppwer Plan 1
Lak RO d On ari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul r 70 S.National Board Number for Unit ~NB ATTACHMENT I CLASS 3
COMPONENTS CONT.
CS.
COMP. COOL. HT. EXCHS
. TO RES ZDUAL HT. EXCHS.
DRAWINGS: C-4 Summary Exam Item Number Categ Number aaa ass aa aa ssaaa 500520 D-B D2.20 NDE Component Component Type Exam aaaaaaaaaaaaaaaaaaaaaa aassaaaassaaaaaaaa aaaa CCU-137 (IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; LZGHT RUST ON WELD & ATTACHMENT, -ACCEPTABLE.
500525 F-A F1.30R CCU-137 OE RIGID RESTRAINT (IA) 94 -VT-3:
NO RECORDABLE INDICATIONS & ZNSIGNIFICANT; I-BEAM DENTED, APPROXIMATELY 6" LONG X 1/4" DEEP.
NOT SERVICE INDUCED - CONSTRUCTION - ACCEPTABLE PER ENGINEERING.
CS.
COMP. COOL.PMPS.,SUC.FM RES.HT.EX.& SG.TK DRAWINGS: C" 6 Summary Exam Number Categ 500760 D-B Item NDE Number Component Component Type Exam aaaaaaa aaaaaaaassaaaaaaaaaaaaa aassaassassssaaaa aa aaaa D2.20 CCU-156 (IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
500765 F-A F1.30R CCU-156 ASME RIGID SUPPORT (IA) 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
500820 D-B D2.40 CCU-167 (ZA)
ASME INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; SURFACE RUST ON INTEGRAL ATTACHMENT SURFACE,
-ACCEPTABLE.
500825 F-A F1. 30V CCU-167 OE VARIABLE SPRING (IA) 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE. TEMP.
58 DEG. F.,
SETTING 1 1/8",
2918 ¹'S.
VT-3 38
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner R
h r
& El c ri r
E Av Ro h r NY 14 4
- 2. Plant R
E Ginna Nu lear Power Plant 1
0 L k R
d n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.commercial service Date
~Jul l 70 6.National Board Number for Unit NjA ATTACHMENT I CLASS 3
COMPONENTS CONT.
C7.
AUX.COOL.IN & OUT FOR BORIC ACID EVAPOR.
DRAWINGS: C-7 Summary Exam Number Categ 500960 D-B Item Number D2.20 Component SS SS SS SS SS SS SS CCU-218
( IA)
INTEGRAL ATTACHMENT Component Type SS SS NDE Exam VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; UNDERCUT ( 1/32N DEEP -
RANDOM, - ACCEPTABLE.
500965 F-A F1.30R CCU-218 ASME RIGID HANGER (IA) 94 -VT-3: NO RECORDABLE ZNDICATIONS; -ACCEPTABLE.
C8.
AUX.COOL.WTR. FROM PEN 124,125,126
& 130 DRAWINGS: C-5 Summa ~ Exam Item Number Categ Number ssssssss sm ss ss sssms ssss 501110 D-B D2.20 Component Component Type CCU-228 (IA)
ASME INTEGRAL ATTACHMENT NDE Exam VT-3 94 -VT-3: REJECT; POOR WORKMANSHIP ON WELDS, ORIGINAL CONSTRUCTION NOT SERVICE INDUCED. NCR94-029 GENERATED.
RE-EXAMINED AFTER REPAIRS. VT-3:
NO RECORDABLE INDICATZONS
-ACCEPTABLE.
501115 F-A F1.30R CCU-228 GUIDE (IA)
OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C9 ~
~ FUEL PZT HT EXS ~ s DISCH DRAWINGS) C-11 Summary Exam Number Categ aa=
am=a+a=
501630 D-C Item NDE Number Component Component Type Exam aaa==aa aaaaaa=amm=aaammaaaaaa aaaaaaa=rmaa=aaa aaam D3.20 SWU-161 (IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
39
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Elec ric C r East Ave. Roch r NY 1464
- 2. Plant R.E.Ginna N
lear Pow r Plant 1503 L k R a On ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date $~1~170 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3
COMPONENTS CONT
~
SW COMP. COOL.& SP.FUEL PZT HT EX'DISCH (CONT.)'RAWINGSs C-11 Summary Exam Number Categ Ztem Number Component NDE Component Type Exam
--=a sa
======= =aa=aaaaaaaaaaa=aaaaaa aaaaa-aa-===---a asaa 501635 F-A F1.30R SWU-161 OE RIGID HANGER (IA)
VT-3 94 -,VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C10.
SVC.WTR.-TO COMP. COOL.& SP.FL.PZT HT.EXS.
DRAWINGS: C-12 Summary Number 501900 Exam Item Categ Number D-C D3.20 NDE Component Component Type Exam
=aazsasaaasaaaaaamaaaaa aaaaaaaaaa-aaaaa aaaa SWU-194 (IA)
OE VT-3 INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; LIGHT RUST -ACCEPTABLE.
501905 F-A F1.30R SWU-194 RIGID HANGER (IA)
OE 94 -VT-3: NORECORDABLE, INDICATIONS; -ACCEPTABLE.
501910 F-A F1.30R SWU-195 GUIDE OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
Cll. SVC.WTR.-TO A & B DZESEL GEN.WTR.COOLERS DRAWINGS: C-13 Summary Exam Number Categ 502280 D-B Item Number Component cxmmmmm=
mmmxsmsssaammmmm-----mscmm D2.20 SWU-252 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam ASME VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
40
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
hester Gas 6 El ri C r E
- Ave, Roch r NY 1464
- 2. Plant R
E Ginna Nu l r Power Plan 1
0 L k R ad On ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A 5.Commercial Service Date $~1~170 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3
COMPONENTS CONT.
SVC.WTR.-TO A & B DZESEL GEN.WTR.COOLERS (CONT.)
DRAWINGS: C-13 Summary Number 502285 Exam Categ F-A 1tem Number F1.30R NDE Component Component Type Exam aaaaaaaaaa aa aaaa aaaaaaaaa a
a aa aaaa SWU-252 OE VT-3 RIGID SUPPORT (IA) 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C12.
SVC.WTR.-ZNTERMED ~ BLDG.16" R 20" HDRS.
DRAWINGS: C-16 Summary Exam Number Categ ss ss ss ss ss ss ss 502840 D-B Item Number D2. 20 NDE Component Component Type Exam aaaaaaassassaaaa aaaaaaa aaassassssssaaaaaaaa aassa SWU-328 (IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS 6c INSIGNIFICANT; SURFACE CORROSION,
-ACCEPTABLE.
502845 F-A F1.30R SWU-328 RIGID RESTRAINT (IA)
OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C13.
SVC.WTR.-ZNTMD.BLDG.16"HD.TO PEN 312-320 DRAWINGS: C-16B Summary Exam Number Categ 502930 D-B Ztem Number Component D2. 20 SWU-337 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam ASME VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
502935 F-A F1. 30R SWU-337 OE RIGID RESTRAINT (IA) 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
41
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Roch r
a S Ele tri r
8 Ea Av R
hester NY 14 4
- 2. Plant R E.
irma Nu lear Power Plan 1503 Lak R
d n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial Service Date
~Jul
- l. 7 S.National Board Number for Unit N~A ATTACHMENT I CLASS 3
COMPONENTS CONT.
C14.
SVC.WTR.-PUMPS ABB,C Ec D DZSCH.SCR.HOUSE DRAWINGS: C-17 Summary Number 503415 Exam Ztem NDE Categ Number Component Component Type Exam aaaaassa aaaaaa aaaassassaaaaaaaaaaaaaaa aaaaaaaaaaaaassaa aaaa F-A F1.30R SWU-627 (N738)
OE VT-3 GUIDE 94 -VT-3: NO RECORDABLE INDICATIONS Sc INSZGNIFZCANT; COMPONENT GAP DIMENSIONS DOES NOT CONFORM TO DRAWING. GAP IS ACCEPTABLE USING TOLERANCES OF ME-121 FOR GUIDES.
503425 F-A F1.30R SWU-628 (N739)
OE GUIDE 94 -VT-3:
NO RECORDABLE INDICATIONS Ec INSIGNIFICANT; COMPONENT GAP DIMENSIONS DOES NOT CONFORM TO DRAWING. GAP ZS ACCEPTABLE US1NG TOLERANCES OF ME-121.
VT-3 503450 D-B D2.20 SWU-631 (N742)
(IA)
ASME INTEGRAL ATTACHMENT 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE. ALL BASE ANCHORS ARE BENT, ORIGINAL CONSTRUCTION,
-ACCEPTABLE PER FCRg 2512-1553.
BASELINE EXAMINATION"FOR MODIFICATION UNDER EWR 5284B.
503455 F-A F1.30R SWU-631 (N742)
RIGID SUPPORT (IA)
OE 94 -VT-3: NO RECORDABLE INDZCATIONS & INSIGNIFICANT; ALL BASE ANCHOR BOLTS ARE BENT, ORIGINAL CONSTRUCTION,
-ACCEPTABLE PER FCR
() 2512-1553.
BASELINE EXAMINATION FOR MODIFICATION UNDER EWR 5284B.
503460 D-B D2.20 SWU-632 (N743)
(IA)
ASME INTEGRAL ATTACHMENT 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE. BASELINE EXAM1NATION PERFORMED UNDER EWR 5284B.
42
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roche r Gas 6 El tric Cor East Ave. Roche ter NY 1464
- 2. Plant R
E Ginna N l r Power Plan 1
03 Lake R
n rio NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul 1
70 S.National Board Number for Unit Njn ATTACHMENT I CLASS 3
COMPONENTS CONT.
Summary Exam Number Categ Item Number SVC. WTR. - PUMPS AfBf C
& D DZSCH ~ SCR HOUSE (CONT )
DRAWINGS C 17 I
NDE Component Component Type Exam a saa as a aaaass aaa ssaaaaaa asa aaaaaafm aaa 503465 F-A Fl. 30R SWU"632 (N743)
'IGID SUPPORT (IA)
OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS 6 OTHER; HILTI BOLTS BENT DURING INITIAL INSTALLATION, NOT SERVICE INDUCED AS ACCEPTED BY FCN 2512-1570.
BASELINE EXAMINATION FOR MODIFIED SUPPORT TO VALVE UNDER EWR 5248B,
-ACCEPTABLE.
C15.
AUX. FW PUMPS DZSCH - INTERMED. BLDG.
DRAWINGS: C-1F Summary Exam Number Categ sa 505020 F-A Item Number Component
ass aimasaafsaaaa=a
=afsafssa F1.30R AFU-10 U-BOLT (NRC 50%')
NDE Component Type Exam aaaaaa aasaaaa a
aa OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505040 F-A Fl.30R AFU-12 OE RIGID RESTRAINT (NRC 50%)
94 -VT"3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505140 F-A F1.30R AFU-22 OE RIGID RESTRAINT (NRC 50%')
VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505220 D-B D2.20 AFU-99 (IA)
ASME INTEGRAL ATTACHMENT 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505225 F-A F1.30A AFU-99 ANCHOR
( IA)
J OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
43
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roche er Gas
& El ri r
8 East Ave Rochester NY 1464
- 2. Plant R
E irma Nuclear P
w r Plan 1
L k R
n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date ~Jul l 70 6.National Board Number for Unit jNA ATTACHMENT I CLASS 3
COMPONENTS CONT-AUX. FW PUMPS DISCH - INTERMED. BLDG.
(CONT.)
DRAWINGS: C-1F Summary Number 505310 Exam Categ D-B Item Number Component RDQR RR CRRRRSSSNSSSNSNSNSNSNOO D2.20 AFU-33 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam
==-SS-SNSSSSSSSSSSSNaaaa aSSSSSS ASME VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505315 F-A F1.30R AFU-33 OE RIGID RESTRAINT (IA) 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505350 F-A F1.30R AFU-37 U-BOLT (NRC 50%')
OE 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505380 F-A F1.30R AFU-40 OE RIGID RESTRAINT (NRC 50%)
VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505395 F-A F1.30R AFU-41 OE GUIDE
( IA)
(NRC 50%')
94 -VT-'3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505440 F-A F1.30V AFU-46 OE VARIABLE SPRING (NRC 50%)
94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505530 F-A F1.30R AFU-55 GUIDE (NRC 5094')
OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505545 F-A F1.30R AFU-56 OE GUIDE
( IA)
(NRC 50%')
VT-3 94 -VT-3: NO RECORD~LE INDICATIONS; -ACCEPTABLE.
44
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h ster Gas
& El ri r
8 East Ave.
R h ster NY 1464
- 2. Plant R E.
irma Nu l r Power Plant 1
Lak Road Ontari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date Q~1~17 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3
COMPONENTS CONT.
AUX. FW PUMPS DZSCH - INTERMED. BLDG.
(CONT.)
DRAWINGS: C-1F Summary Exam Number Categ 505670 F-A Ztem Number Component Component Type F1.30R AFU-67 OE RIGID HANGER (NRC 50%')
NDE Exam VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505775 D-B D2.20 AFU-78 (IA)
ASME INTEGRAL ATTACHMENT VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505780" F-A F1.30R AFU-78 OE RIGID RESTRAINT (IA)
VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505820 F-A F1.30R AFU-91 GUIDE (NRC 50%')
OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
505980 F-A F1.30R AFU-114 GUIDE (NRC 50%')
OE 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C16.
STANDBY AUX FW FRM PEN 119 - AUX FW PUMP C
DRAWINGS: C-21 Summary Exam Z tern Number Categ Number RR&ClMM MMCSCX&&
507220 F-A F1.30R Component
&5CCR
&Ct&Cf&MM AFU-259 (AFW-72)
U-BOLT (NRC 50%')
NDE Component Type Exam maraca mmssmmm=mmes's=--
OE VT-3 94 -VT-3:
NO RECORDABLE INDZCATIONS; -ACCEPTABLE.
507360 F-A F1.30R AFU-273 (AFW-86)
OE RIGID HANGER (NRC 50%')
VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS & REJECT; THREADED ROD GOES THROUGH EYE
& HITS TOP BOLT ON CLAMP, NOT SERVICE ZNDUCED. TROUBLE CARD (W/R 002486)
GENERATED. VT-3 RE-EXAM; NO RECORDABLE INDICATIONS - ACCEPTABLE.
45
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h st r as
& Electric C r 8
Ea Ave Roch er NY 1464
- 2. Plant R.E.Ginna N l r P
w r Pl nt 1503 L k Roa ntario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A B.commercial service Date ~J1 1 70 S.National Board Number for Unit N~A ATTACHMENT Z CLASS 3
COMPONENTS CONT.
STANDBY AUX FW FRM PEN 119 - AUX FW PUMP C
(CONT.)
DRAWINGS'-21 Summary Exam Number Categ 507430 F-A Item Number Component N:S----m atNBBaaaataatdfNSBNtna=aafctNNttN F1.30R AFU-155 (AFW-96)
GUIDE (NRC 50%')
NDE OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
507460 F-A F1.30R AFU-151 (AFW-93)
GUIDE (NRC 50%')
OE 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
507490 F-A F1.30R AFU-160 (AFW-97)
GUIDE (NRC 50%')
OE 94 -VT-3: NO RECORDABLE INDICATIONS;
-ACCEPTABLE'07540 F-A Fl.30R AFU-192 (AFW-102)
GUIDE (NRC 50%')
OE 94 -VT-3:
NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; DRAWING DOES NOT SHOW 1/8" SHIM TO ACHIEVE "0" CLEARANCE ON BOTTOM OF PIPE/GUIDE.
ACCEPTABLE PER MECHANICAL ENGINEERING.
GENERATED DCR TO DOCUMENT THE PRESENCE OF THE SHIM.
C17.
STANDBY AUX PW FRM PEN 123 - AUX FW PUMP D
DRAWZNGSs C-25 Summary Exam Number Categ 508148 F-A Ztem Number Component GUIDE (NRC 500)
NDE Component Type Exam IRRNBBtNBNONRSC QBNOC Catentn OE VT-3 94 -VT-3; NO RECORDABLE INDICATIONS; -ACCEPTABLE.
46
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r
El ric C r 8
E Av Ro h r NY 14 4
- 2. Plant R
E irma Nu lear P
w r Pl n 1503 L k R
n ri NY 14 1
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul l 70 6.National Board Number for Unit N~A ATTACHMENT I CLASS 3
COMPONENTS CONT.
STANDBY AUX FW FRM PEN 123 - AUX FW PUMP D
(CONT.)
DRAWINGS: C-25 Summary Exam Number Categ 508149 D-B Item Number Component aaaaaaa assssassa ssaassssa aaa D2. 20 AFU-233 (AFW-52)
(ZA)
INTEGRAL ATTACHMENT NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa ASME VT-3 94 -VT-3; NO RECORDABLE INDICATIONS; -ACCEPTABLE.
508420 F-A F1.30R AFU-185 (AFW-109)
OE GUIDE (NRC 50%')
94 -VT-3; NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C18.
MOTOR DRIVEN AUX. FW PUMP SUCTION DRAWINGS: C-33 Summary Exam Numbe=
-Categ assaa aaaaisssa 508630 F-A Item Number Component aaaa aaaaaa aaaaaaaaaaaass F1.30R SWU-287 RZGZD RESTRAINT (NRC 50%')
NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa OE VT-3 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
C1 9 ~
STANDBY AUX FWB SW SUPPLY TO SAFW PUMP C
DRAWINGS: C-28 Summary Exam Ztem Number Categ Number Component aaaaaa aaaaaaa aaaassaa aaaaaassaaaaaaaaaaaaaaa 508835 F-A F1.30R SWU-594 (SW-126)
GUIDE (NRC 5015)
-SHIM BLOCK SHOWN ON DRAWING NOT IN PLACE.
EXISTING GAP IS ACCEPTABLE.
FUNCTION OF SUPPORT VERIFZED AS ACCEPTABLE.
INITIATED DCR TO DOCUMENT ABSENCE OF SHIM BLOCK. VT-3:
NO RECORDABLE INDZCATIONS; -ACCEPTABLE.
47
R ~ E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester as
& Elec ri or 8
Eas Av R ch er NY 1464
- 2. Plant R
E irma Nuclear Power Plan 1
Lake Road On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (lf Req.)
~N A S.Commercial Service Date Julvu17 } S.National Board Number for Unit
~N ATTACHMENT Z CLASS 3
COMPONENTS CONT.
C20.
SAFW PUMPS C
& D SW SUCTION CROSSOVER DRAWINGS: C-29 Summary Exam Item Number Categ Number Wet MMmame 508990 D-B D2.20 NDE Component Component Type Exam
=aamefmtmtmaa=-sastmaaaaaaam tmaaaamamaeeeeamaaas-a amamaa SWU-517 (SW-134 )
( IA)
ASME VT-3 INTEGRAL ATTACHMENT 94 - VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
508993 F-A F1.30R SWU-517 (SW-134)
NO RECORDABLE INDICATIONS & OTHER; BACKING STRIPS INSTALLED BEHIND ANGLE IRON - NOT IDENTIFIED ON SUPPORT
- DRAWING, DCR GENERATED -ACCEPTABLE.
VT-3 C21.
MAIN STEAM LOOP B TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Ztem Number Categ Number 509050 D-B D2. 20 Component RCDCQBfm imiNSENS>>CCRSN MSU-67 (IA)
INTEGRAL ATTACHMENT NDE Component Type Exam Nffeee&M MMMBB}NBB
&&SS&
ASME VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
509055 F-A F1. 30R MSU-67 OE GUIDE
( IA) 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
509110 D-B D2.20 MSU-73 (IA)
ASME INTEGRAL ATTACHMENT 94 -VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT; MODERATE CORROSION
-ACCEPTABLE.
VT-3 509115 F-A FI. 30R MSU-73 RZGID RESTRAINT (IA)
OE VT-3 94 -VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
48
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner Roche er
& El ri r
E Av R
h r NY 14 4
- 2. Plant R
E irma Nuclear P
w r Pl n 1
03 Lake R
On ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul l 70 S.National Board Number for Unit ~NB ATTACHMENT I CLASS 3
COMPONENTS CONT.
C22
~
AUX FW PUMP A FLOW CONTROL BYPASS DRAWINGS: C-1G Summary Exam Number Categ 510030 F-A Item Number Component F1.30R AFU-59 GUIDE (NRC 5096)
NDE Component Type Exam 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
D.
CLASS COMPONENTS:
Dl..
LETDOWN DEMZN FILTER DRAWINGS) B-3 Summary Exam Number Categ 074100 Item Number Component COSY RRRRC RRRR RRBSfmfmfNStmaatm LHSWRCF LOWER HEAD-TO-SHELL NDE Component Type Exam OE 94
-UT:
NO RECORDABLE INDICATIONS Ec GEOMETRY; ROOT GEOMETRY.
OWNER ELECTED EXAM, 53%'F WELD EXAMINED DUE TO LIMITATIONS
-ACCEPTABLE.
074350 FB 5/8N DIA. BOLTS 94 -VT-1 & MT: OTHER; BOLTS NOT REMOVED, NOT EXAMINED. UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
R.
E.
GINHA HUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r Ga 6 Elec ri or Eas Av R
h r NY 1464
- 2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake R ad n ario NY 1451
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A 6 Co.mmercial service Date
~Jul l 70 S.National Board Number for Unit ~NA ATTACHMENT I E.
HIGH ENERGY COMPONENTS:
El.
MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9 Summary Exam Number Categ 200015 HE-DB Item Number Component Fl ELBOW-TO-PIPE NDE Component Type Exam AUG VT-1 RT MT 94 -VT-1 6c MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. RT:
NO RECORDABLE INDICATIONS Ec INSIGNIFICANT; 10-20 SLAG I 15-1/2" (3/16"), 80-90 POROSITY 8 80 1/4,
-ACCEPTABLE.
E2.
MAZH STEAM LOOP B OUTSIDE CV DRAWZHGS: B-10A Summary Numbe=
200035 Exam Categ HE-DB Item Number Component CCQO RCBBCBN Rat RR Hl PIPE-TO-ELBOW NDE Component Type Exam AUG VT-1 RT MT 94
-MT 8c RT:
NO RECORDABLE INDICATIONS; ACCEPTABLE. VT-1:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; LlNE-UP LUG GOUGES, Lta 1 a Wee 1 1/4 DOWNSTREAMa 1/8 n X 1/8" ( 1/32 DEEP Lee 1 1/2 6 Weal 1/2 UPSTREAM, 1/16" DIA. ( 1/32 DEEP
-ACCEPTABLE. UT THICKNESS )1.15".
200040 HE-DB Jl AUG VT-1 MT RT PIPE-TO-ELBOW 94 -VT-1, MT Ec RT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE;>>
50
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r
as
& El ric r
8 E
Av R
h r NY 14 4
- 2. Plant R
E Ginna Nucl r
P wer Pl n 1
0 Lak Road On ario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~ul
~1 70 6.National Board Number for Unit
~N A ATTACHMENT I HIGH ENERGY COMPONENTS CONT.
E3.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-5 Summary Exam Item Number Categ Number ss ss a ss ss 200060 HE-DB Component aaaaassass aassssssaaa Ul NDE Component Type Exam aaaaaaaaaaaaaaaa ssassa AUG VT-1 MT UT ELBOW-TO-PIPE 94 -VT-1, MT & UT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
200065 HE-DB U2 PIPE-TO-ELBOW AUG VT-1 MT UT 94 -VT-1 & MT: NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; ZNDICATION gl IS LESS ~l 10'AC NO APPARENT CHANGE SINCE LAST EXAMINATION
-ACCEPTABLE.
E4.
REEDWATER LOOP B OUTSIDE CV Summary Exam Item Number Categ Number Component 200085 3994 VALVE-TO-ELBOW aaaaaaa aaaaaaa aaaassaaaaaaaaaaaaassaaa HE-DB N
DRAWZNGS: B-14 NDE Component Type Exam ssa aaaassssaa assa aaaa AUG VT-1 MT RT 94 -VT-1 & MT:
NO RECORDABLE INDZCATIONS-ACCEPTABLE. RT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; POROSITY,
- IUC, SLAG, CASTING SHRINKAGE
&, TUNGSTEN (SEE REPORT)-ACCEPTABLE.
NOTE:
EROSlON IN BASE MATERIAL FROM 11 TO 33". MIN. THICKNESS
.880"
-ACCEPTABLE.
51
R.
E ~
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochest r
& El ri r
Eas Ave R
h r NY 1464
- 2. Plant R E.Ginna Nuclear Power Plant 150 Lak R ad n
rio NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial service Date
~Jul l vo S.National Board Number for Unit ~NA ATTACHMENT I HIGH ENERGY COMPONENTS CONT.
~
E5.
MAIN STEAM LOOP A OUTSIDE CV DRAWINGSf B-9A Summary Number 200155 Exam Categ HE-CB Item Number Component ss ss ss ss ss ss sc a a PIPE-TO-VALVE 3519 NDE Component Type Exam aaaaaaaaaaaaaaaa ssssssa AUG VT-1 RT MT 94 -VT-1 & MT: NO RECORDABLE INDICATIONS'ACCEPTABLE. RT:
INSIGNIFICANT; SLAG AND POROSZTY,-ACCEPTABLE.
m E6.
MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10 Summary Exam Number Categ aaaaaa aaaaaaa 200215
.HE-CB Item Number Component aaaaaaa aaaaaaaaaaaaaaaaaaaaaa 0
PIPE-TO-VALVE 3518 NDE Component Type
NO RECORDABLE INDICATIONS; -ACCEPTABLE. RT:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; SLAG & POROSITY
-ACCEPTABLE.
E7.
MA1N STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Number aaaaaa 200270 Exam Ztem Categ Number Component aaaaaaa aaaaaaa aaassassssaaaaaaaassaaassaa HE CB B1 ELBOW-TO-PIPE NDE Component Type Exam aaaaaaaaaaaaaaass aaaa AUG VT-1 UT MT 94 -VT-1 & MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & GEOMETRY; COUNTERBORE
& LOW AMPLITUDE ID GEOMETRY -ACCEPTABLE.
52
R ~
E ~
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r
& El ric r
8 E
Ave Rochester NY 1464
- 2. Plant R
E irma Nucl r Pow r Plan 1503 Lake Road On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date ~J1 1
70 S.National Board Number for Unit N~A HIGH ENERGY COMPONENTS CONT.
MAIN STEAM TURBINE BUILDING (CONT.)
DRAWINGS: HE-7A Summary Exam Item Number Categ Number Component mmaa-m aammama mmaaafaa aasaaaaaaasmaafamammmamaammaem 200275 HE-CB C
PIPE-TO-ELBOW NDE Component Type Exam M&BB Ba AUG VT-1 UT MT RT 94
-MT: NO RECORDABLE INDICATZONS-ACCEPTABLE. VT-1:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; INTERMITTENT UC (1/32N 360 DEG.-ACCEPTABLE. UT:
GEOMETRY & OTHER; ROOT GEOMETRY
&. SLAG-ACCEPTABLE. AUGMENTED RT:
CONFIRMATION SLAG
& NO CHANGE-ACCEPTABLE.
E8.
FEEDWATER TURBINE BUILDING DRAWINGS: HE-6 Summary Number IN 200315 Exam Item Categ Number Component NICK&%%%
KK&&KBB&KBBKBBBBBBRN'E-CB Ml PIPE-TO-ELBOW NDE Component Type Exam AUG VT-1 UT MT 94 -VT-1
& MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS, GEOMETRY & OTHER; COUNTERBORE GEOMETRY AND ROUGH ROOT -ACCEPTABLE.
200360 HE-CB H
PIPE-TO-VALVE AUG VT-1 RT MT I
94
-MT: NO RECORDABLE INDICATIONS; -ACCEPTABLE. RT:
INSIGNIFICANT; SLAG, POROSITY
& TUNGSTEN -ACCEPTABLE. VT-1:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; CLUSTER POROSITY LBB7" 15 PORES (ml/64I L~19.5N 35 PORES (al/64, ACCEPTABLE PER RT (1N IN 6" OF WELD.
53
R.
E.. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Ele ric Cor Ea Ave.
Roch r NY 14 4
- 2. Plant R.E.Ginna Nucl ar P
w r Pl nt 1503 Lake Road Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date jul 199/. 6.National Board Number for Unit
~N A ATTACHMENT Z HIGH ENERGY COMPONENTS CONT.
E9.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-11 Summary Number 200445 Exam Item Categ Number CR SC K&&ZR M HE-CB Component aaamaamaaaamaaaaaaaaam Z1 PIPE-TO-ELBOW NDE Component Type Exam MCSRS&RS&CS&&&
NO RECORDABLE INDICATIONS & ZNSIGN1FICANT; MODERATE RUST -ACCEPTABLE. MT & UT:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
200450 HE-CB Z2 ELBOW-TO-PIPE AUG VT-1 RT MT 94 -x'-1 & MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. RT:
NO RECORDABLE INDICATIONS & INSIGNZFZCANT; 0 POROSITY 8 3 1/4"(0.020"),
27-36
& 29 1/2 "31 3/4 ROOT OF WELD WASHED OUT, 36 POROSITY 8 38 1/2"(0.050"),
-ACCEPTABLE.
E10.
FEEDWATER LOOP B OUTSIDE CV DRAWINGS: B-14 Summary Exam Item Number Categ Number Component SSSSQ?5 SCCSS RC RRR RRCSRCBCRCRDOQECC52585OOSS 200565 HE-CB N1 ELBOW-TO-PIPE NDE Component Type Exam CRM&M&MMM AUG VT-1 RT MT 94 -VT-1, MT & RT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
LIMITATIONS: NO EXAMINATIONS FROM L~42-1/2" TO L~3" DUE TO LUGS LOCATED WITHIN EXAMINATIONAREA. GREATER THAN 90%'OVERAGE OBTAINED -ACCEPTABLE.
200570 HE-CB 0
PIPE-TO-ELBOW AUG VT-1 UT MT 94 -VT-3 & MT:
NO RECORDABLE INDICATIONS; -ACCEPTABLE. UT:
NO RECORDABLE INDICATIONS & GEOMETRY; ROOT GEOMETRY AND COUNTERBORE,
-ACCEPTABLE.
54
R.
E ~
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h ster as Electric r
E t Av R
h r NY 14 4
- 2. Plant R
E Ginna N cl ar P
w r Plan 150 L k R ad On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date $~1~170 6.National Board Number for Unit ~NA ATTACHMENT 1 HIGH ENERGY COMPONENTS CONT.
E11.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-5 Summary Exam Number Categ 201620 HE-CS Ztem Number "F1. 20V NDE FWU-22 VARIABLE SPRING 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE. TEMP.
72 DEG. F.,
SETTINGS (BOTH) 1241 ¹'S, BP VS-2.
E12.
REEDWATER RECZRC LINE DRAWINGS: HE-6 Summary Number 202320 Exam Categ HE-CS Ztem NDE Number Component Component Type Exam assssaaaaaaassssssssaaaaassssa aassaaaassssassssassass assssa
- F1.20R CD-168 (S36)
OE VT-3 RIGID HANGER 94 -VT-3: NO RECORDABLE INDICATIONS -ACCEPTABLE.
F.
LEAKAGE TESTING:
F1.
LEAKAGE EXAMINATIONS CLASS 1
DRAWINGS: NA Summary Exam Number Categ 411000 B-P Item NDE Number Component Component Type Exam aaaaaaa aaaaassaaaaaaaaaaaaaaaa aaassaaaaaaaaaaaa aaass IWB5221 PT-7 LEAKAGE TEST OF ASME VT-2 REACTOR COOLANT SYSTEM 94 -VT-2: TEST ACCEPTABLE, V721 LEAKING 1 DROP/5 MIN.
6c V427 HAD BODY TO BONNET LEAK. SPECIAL VT-2 TEST PERFORMED TO CLEAR MAINTENANCE ITEMS ON CON-O-SEAL, V535s V721 6c V427, TEST ACCEPTABLE.
55
R.
E ~
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- 1. Owner Roche r
a E El ri r
8 Eas Ave R chester NY 1464
- 2. Plant R.E Ginna Nuclear Power Plan 1
Lake Road on ario NY 14519
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A 5.Commercial Service Date ~1
~1 IO 6.National Board Number for Unit
~N A ATTACHMENT Z LEAKAGE TESTING CONT.
s P2.
LEAKAGE EXAMZNATZONS CLASS 2s3 DRAWINGS: NA Summary Number 411200 Exam Ztem Categ Number Component ssmssssssssss ssssmmmmss ssssssssmssssssmssssmssssssssssssssmssss C-H IWC5221 MAINSTEAM OUTSIDE CONTAINMENT NDE Component Type Exam ASME VT-2 94 -VT-2: INSIGNIFZCANT: V3505 Ec 3504A, PACKING LEAK-GLAND IS WET. V3448B, PACKING LEAK 30 DROPS/MZN, PACKING GLAND NEEDS TO BE CLEANED UP.
UNION BETWEEN V3411
& LMSO1 IS LEAKING-NEEDS TO BE TIGHTEN.
WORK ORDERS WRITTEN
-ACCEPTABLE.
411500 C-H IWC5221 FW INSIDE CONTAINMENT ASME 94 -VT-2:
NO RECORDABLE INDICATIONS( V3415 HAS A BAD PACKING LEAK. V293B HAS A PACKING LEAK BUT IS OUTSZDE THE SCOPE OF THIS 'I'EST -ACCEPTABLE.
411800 D-B IWD5221 AUX FW "B" PUMP ASME 94 -VT-2:
NO RECORDABLE INDICATIONS; FUNCTIONAL TEST
-ACCEPTABLE.
412000 D-B IWD5221 STANDBY AUXILIARY FEEDWATER PUMP "C" ASME 94 -VT-2:
NO RECORDABLE ZNDICATIONS -ACCEPTABLE. NOTE: THIS EXAM ALSO COVERS SM-4658C.4.
412200 HE-LK HE FEEDWATER AUG 94 -VT-2: NO RECORDABLE INDICATIONS -ACCEPTABLE.
412400 C-H IWC5221 STEAM GEN BLOWDOWN ASME OUTSIDE CONTAINMENT 94 -VT-2: NO RECORDABLE INDICATIONS -ACCEPTABLE.
56
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Ro hester Gas Elec ric C r 8
E st Av Roch s
r NY 1464
- 2. Plant R
E Ginn Nuclear P
w r Plan 150 L k Road On ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.) ~A S.commercial service Date Julvul70 S.National Board Number for Unit ~NA LEAKAGE TESTING CONT.
s P2.
LEAKAGE EXAMINATIONS CLASS 2,3 DRAWINGS: NA Summary Exam Item Number Categ Number 412700 C-H IWC5221 Component
&SSSBMMMMM&miaaaa SAFETY INJECTION "C" PUMP OUTSIDE CONTAINMENT NDE Component Type Exam OQQRRRtaaaemaNRR BS NamtRQ ASME VT-2 94 -VT-2:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; 1)
BORON RESIDUE AROUND BOLTING OF V2811.
- 2) V1815A MISSING MOTOR OPERATOR
& PIPE PLUG GREASE FITTING - REPORTED TO PLANT. 3) 1ST FLANGE OUT OF FWD PUMP SEAL-BORIC ACID RESIDUE-T/C GEN.-ACCEPTABLE.
412900 C-H IWC5221 SAFETY INJECTION ACCUMULATOR 2 (B)
ASME 94 -Vl'-2: NO RECORDABLE INDICATIONS & INSIGNIFICANT.
V835B/892B - PACKING LEAK WET-DECON.
FLANGE NEXT TO V892B-DRY DECON. V865-PACKING LEAK WET. V840A/B-PACKING LEAK, VT-3 REQUIRED ON BOLTING. CHECKED ALL SMALL & LARGE BORE NOZZLES FOR CRACKING-OK.
413300 C-H IWC5221 RHR LOW PRESSURE "B" PUMP ASME VT-2 94 -VT-2:
NO RECORDABLE INDICATIONS; SYSTEM INSERVICE-ACCEPTABLE. NOTE:
PT-4 INVOLVES A PRESSURE TEST OF BOUNDARY PIPING TO 100 PSI (NOT REQUIRED ZWC-5222 PRESSURE)
TAKING CREDIT FOR SYSTEM FUNCTIONAL TEST.
413500 C-H ZWC5221 RHR PUMP "B" IN/OUT CONT.
ASME 94 -VT-2:
NO RECORDABLE INDICATIONS, SEE REPORT FOR DETAILS.
FOLLOWING ITEMS CONTAINS LEAKS, BORIC ACID RESIDUE OR ADDITIONALVT-3; V624,
- PI629B, FT931A, V857B, V857C,
- V716, B
RHR HX V709D a V704B a V850Af B
PUMP COOLER 6 AND V850B
-ACCEPTABLE.
57
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner Roch r
s
& El ri r
8 E t Av R
h s r NY 14649
- 2. Plant R
E Ginna Nuclear P wer Plant 1
Lake Road Ontari NY 14
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~cul l vo 6.National Board Number for Unit jNA ATTACHMENT I LEAKAGE TESTING CONT.
R2.
LEAKAGE EXAMINATIONS CLASS 2,3 DRAWINGS: NA Summary Exam Number Categ 413900 D-A Item Number Component SDCSSSNSNSNSSSSNRR SSS'SSSN IWD5221 SERVICE WATER INSZDE CONTAINMENT NDE Component Type Exam SSSSSSSS MMMMSSSSSSSSSN ASME VT-2 94 -VT<<2:
NO RECORDABLE INDICATIONS, NB" FAN UNIT (COOLING COILS)
APPEARS TO HAVE A LEAK ON THE SUPPLY AND RETURN FLANGES-INSULATION MAY NEED TO BE REMOVED FOR A BETTER LOOK-T/C GENERATED, ACCEPTABLE.
414200 D-A IWD5221 SERVICE WATER TO AUX FW PUMP "B" ASME VT-2 94 -VT-2: NO RECORDABLE INDICATIONS, FUNCTIONAL TEST
-A CEPTABLE.
NOTE: SM-4658C.2 ALSO WITHIN EXAM SCOPE.
414900 C-H IWC5221 BORIC ACID TANKS PIPING ASME VT-2 94 -VT-2:
NO LEAKS LOCATED SYSTEM INSERVICE TEST.
SYSTEM HAS BEEN INSERVICE FOR GREATER THAN 4 HOURS - ACCEPTABLE.
415550 D-B IWD5221 SPENT FUEL POOL COOLING-B ASME 94 -VT-2: NO RECORDABLE ZNDICATIONS; INSERVICE TEST
-ACCEPTABLE. RESIDUAL BORIC ACID ON 1)
PACKING OF VALVES
- 8667A, 8667D, 8669A Ec 8657.
2)
FLANGED AREA OF FE-8667.
3)
BONNET NUTS OF VALVE 8635G.
58
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994)
- l. Owner Rochester a
& Electric or 8
E Av R
h ster NY 1464
- 2. Plant R
E inn N l ar Pow r Plan 1
Lake R
n ri NY 14 1
- 3. Plant Unit 1
- 4. owner certificate of Authorization (zf Req.)
~N B.Commercial Service Date
~Jul l 7 6.National Board Number for Unit N~A G.
SNUBBER PROGRAM COMPONENTS:
Gl ~
STEAM GENERATOR A DRAWINGS: A-7P Summary Number SS 600080 Exam Categ SN-VT Item Number NDE Component Component Type Exam SSSSSSSSSSSSSSRRR SSSSSSSSSSSSSSSSSSSN RR SSSS SSSSSSSSSQ SGA-7 AUG VT-3 HYDRAULIC SNUBBER 94 -S/N 77-28073-A, TEMP.
66 DEG. F.,
SETTING 3'-1/2"
~
VT-3:
NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; RESIDUAL OZL ON SNUBBER AND FLUID LEVEL 7/8 FULL -ACCEPTABLE.
600081 SN-FT SGA-7 AUG HYDRAULIC SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER - FAILED. NCR 94-061 GENERATED. DISPOSITION USE-AS-IS, SNUBBER IS OPERABLE ACCEPTABLE.
WO 5 9400481.
FT 600090 SN-VT SGA-8 HYDRAULIC SNUBBER AUG 94 -S/N 77-28073-A, TEMP.
66 DEG. F.,
SETTING 3'-3/4".
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; RESIDUAL OIL ON SNUBBER -
NO EVIDENCE OF LEAKAGE -ACCEPTABLE.
G2.
STEAM GENERATOR B DRAWINGS: A-7P Summary Exam Number Categ 600120 SN-VT Item Number Component SGB-3 HYDRAULIC SNUBBER NDE Component Type Exam MWMMSSSSSSSSSSSSSS SS&&&
AUG VT-3 94 -S/N 77-28073-A, TEMP.
70 DEG. F.,
SETTING 3'-3 3/8",
ANKER-HOLTH. VT-3: NO RECORDABLE INDICATIONS INSIGNIFICANT; LIGHT OIL FILM ON BOTTOM OF SNUBBER, FLUID 3/4 FULL -ACCEPTABLE.
600130 SN-VT SGB-4 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 77-28073-A, TEMP.
70 DEG. F.,
SETTING 3'-3 5/16NS ANKER-HOLTH. VT-3:
NO RECORDABLE INDICATIONS 6c INSZGNZFXCANT, LIGHT OIL FILM ON BOTTOM, FLUID 3/4 FULL
-ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch s
r a
& Elec ri r
8 E
Ave R
hester NY 1464
- 2. Plant R.E irma Nu lear P wer Pl nt 15 3 Lake Road n ri NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A 5.Commercial Service Date ~ulY 19~7 6.National Board Number for Unit
~N A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G3.
TURBINE DRIVEN AUX. FW PUMP SUCTION DRAWZNGS: C-16 Summary Number 600200 Exam Categ SN-VT Item Number Component MMCRSSl5CS M
WCR&&SCCi&&
AFU-3 MECHANICAL SNUBBER NDE Component Type Exam
&&Z5l5 AUG VT-3 94 -S/N 20925, TEMP.
81 DEG. F.,
SETTING 2",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G4.
AUX. FW PUMPS DISCH - INTERMED. BLDG.
DRAWINGS: C-1E Summary Number 600220 Exam Categ SN-VT Item Number Component AFU-31 MECHANICAL SNUBBER NDE Component Type Exam
&RRZS&&&WMMWMESSS SECS'UGVT-3 94 -S/N 24452, TEMP.
87 DEG. F.,
SETTING 2",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600240 SN-VT
AFU-34 MECHANICAL SNUBBER AUG 94 S/N 16379 TEMP 87 DEG F
SETTING 2 15/16 i
PSA 1
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600260 SN-VT AFU-52 AUG MECHANICAL SNUBBER 94 -S/N 24453, TEMP.
71 DEG. F.,
SETTING 1 3/4",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600261 SN-FT AFU-52 AUG MECHANICAL SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
600280 SN-VT AFU-75 MECHANICAL SNUBBER AUG 94 -S/N 20924, TEMP.
295 DEG. F.,
SETTING 1 3/4",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
60
R. E.
GXNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h er Ga
& Electric or 8
Eas Ave.
Roches r NY 1464
- 2. Plant R E.
irma N l r P
w r Pl n 1
0 L k R a On ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Xf Req.)
~N A B.Commercial Service Date
~cul l 7 S.National Board Number for Unit ~NA ATTACHMENT SNUBBER PROGRAM COMPONENTS CONT.
AUX. FW PUMPS DZSCH -
ZNTERMED ~
BLDG.
(CONT.)
DRAWZNGS: C-1E Summary Exam Number Categ 600300 SN-VT Item Number Component fmfmfmaaamaa.
raa:fmfmfmtaaarafma=aataatatatafmfmta AFU-98 MECHANXCAL SNUBBER NDE Component Type Exam
&SN fm&M AUG VT-3 94 -S/N 24454, TEMP.
100 DEG. F.,
SETTING 1-5/8",
PSA-1.
VT-3: NO RECORDABLE XNDICATZONS; -ACCEPTABLE.
600320 SN-VT AFU-101 AUG MECHANICAL SNUBBER 94 -S/N 15751, TEMP.
180 DEG. F.,
SETTING 3-1/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600339 SN-VT AFU-103 (EAST)
AUG MECHANICAL SNUBBER 94 -S/N 18184, TEMP. 200 DEG. F.,
SETTING 3N 5 PSA-3. VT-3:
NO RECORDABLE ZNDICATIONS; -ACCEPTABLE.
600340 SN-VT AFU-103 (WEST)
AUG MECHANXCAL SNUBBER 94 -S/N 18185, TEMP. 200 DEG. F.,
SETTING 3-1/4",
PSA-3.
VT-3:
NO RECORDABLE INDZCATIONS; -ACCEPTABLE.
600360 SN-VT AFU-109 AUG HYDRAULIC SNUBBER 94 -S/N 30986, TEMP. 200 DEG. F.,
SETTING 2-1/8" GRZNELL SIZE 1.5, VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600380 SN-VT AFU-111 AUG MECHANICAL SNUBBER 94 -S/N 16377, TEMP. )100 DEG. F.,
SETTING 2-1/8N, PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600400 SN-VT AFU-123 AUG MECHANICAL SNUBBER 94 -S/N 16378, TEMP.
180 DEG. F.,
SETTING 1-5/8",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
VT-3 61
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Rochester Ga El c ric r
8 East Ave.
Ro h s r NY 1464
- 2. Plant R
E irma N
1 ar Power Pl n 1
0 L k R
Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.Commercial Service Date
~Jul l
7 6.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
AUX. FW PUMPS DZSCH - INTERMED. BLDG.
(CONT. )
DRAWINGS: C-1E Summary Exam Number Categ 600420 SN-VT Item NDE Number Component Component Type Exam aaaassa aaaaaaasaaaaaaaaaaaaaa aaaaaaaaaaaaaaaa sass AFU-124 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 24451, TEMP.
180 DEG. F.,
SETTING 2",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G5.
STEAM GENERATOR B BLOWDOWN LINE DRAWINGS: B-31 Summary Exam Number Categ 600460 SN-VT Item NDE Number Component Component Type Exam aaasass asaaaszsaszszza ssssasasa aasssssasaassasa ssazs BDU-16 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 10182, TEMP.
70 DEG.
Fea SETTING 2-1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G6.
AUX.COOL LINE 4S-AC6-152 DRAWINGS s B-29 Summary Exam Number Ca teg 600530 SN-VT Item Number Component SSSSSSSS SZ SSSSSSSSZZSS CCU-43 MECHANICAL SNUBBER NDE Component Type Exam aaazssszssssaaa sass AUG VT-3 94 -S/N 11462, TEMP.
71 DEG. F.,
SETTZNG 1-1/2N a
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G7.
AUX.COOL SYS.RRM.PUMP COOL OUT. TO PEN126 DRAWINGS e C-34 Summary Exam Number Categ a s zs s 600610 SN-VT Item CCU-57 MECHANICAL SNUBBER NDE Component Type Exam AUG VT-3 94 -S/N 18194, TEMP.
68 DEG. F.,
SETTING 2 1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
62
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roche r
a
& Elec ric Cor 8
E Av Roche r NY 1464
- 2. Plant R.E Ginna Nuclear Pow r Plan 1
03 Lake Road Ontari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.Commercial Service Date
~Jul l 7 S.National Board Number for Unit ~NB ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT.
G8.
AUX.COOL LINE 4T-AC6-152 DRAWINGS'-30 Summary Exam Ztem Number Categ Number CO 600710 SN-VT Component ta MM&SS &Ni SB Nt M BS M CCU-71 MECHANICAL SNUBBER NDE Component Type Exam AUG VT-3 94 S/N 18193 TEMP 74 DEG F
SETTING 2 5/8 if PSA 3
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G9.
2" LETDOWN TO REGEN HTX DRAWINGS: A-23 Summary Number 600880 Exam Categ SN-VT Ztem Number Component CVU-26 MECHANICAL SNUBBER NDE Component Type Exam
-ataafsaaasaaaaaa=a aatNSB AUG VT-3 94 -S/N 20880, TEMP,.
62 DEG. F.,
SETTING 2",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600881 SN-FT CVU-26 MECHANICAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400469.
G10.
2" CHARGING TO REGEN HTX DRAWINGS: A-30 Summary Exam Ztem Number Categ Number
==a==a aaaaaaa
=aaatnaa 600900 SN-VT NDE Component Component Type Exam SSMWtSMM&
Nfta&&BNSN&&&&MM MMMMM&&tafS&SS&M&
&BS&&
CVU-46 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 38555, TEMP.
72 DEG. F.,
SETTING 2", PSA-1/4. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
63
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r Ga Elec ri Cor Eas Ave R
hes r NY 1464
- 2. Plant R.E.Ginna Nuclear Pow r Plan 1
0 Lak R ad Ontario NY 1451
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date Julvu170 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
~
G11. 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Item Number Categ Number Component aaaaaa aaaaaaa aaaaaaa aaaaaaaaaaaaaaaassaaaaa 600920 SN-VT CVU-49 MECHANICAL SNUBBER NDE Component Type Exam aastassaaaaassssss aassa AUG VT-3 94 -S/N 9483, TEMP.72 DEG. F.,
SETTING 1-1/2N s PSA-1/2.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G12.
2is CVCS RELIEF LINE TO PRT DRAWINGS: B-32 Summary Exam Item Number Categ Number aaaaaisss a
assssssss 600940 SN-VT NDE Component Component Type Exam aassaassssaa aaaaaaaaaaass aaaassssaaaaaaaaaa aaaa CVU-80 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 38556, TEMP.
74 DEG. F.,
SETTING 1-1/2NA PSA-1/4.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G13.
SEAL WATER TO RCP-B DRAWINGS: A-32 Summary Exam Number Categ 600960 SN-VT Ztem Number Component a
aassssa aaaaa aaaassaassaassa CVU-103 MECHANICAL SNUBBER NDE Component Type Exam ssassaaa assaaa aassss AUG VT-3 94 -S/N 24450, TEMP.
72 DEG. F.,
SETTING 2NN PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
600980 SN-VT CVU-104 MECHANICAL SNUBBER AUG 94 -S/N 24449, TEMP.
72 DEG. F.,
SETTING 2",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
64
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ch s er
& El ri r
8 East Av R
h er NY 1464
- 2. Plant R
E Ginna Nuclear P wer Plant 1
0 L ke Road Ontario NY 14 1
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A S.commercial Service Date
~Jul l 70 S.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
~
G14.
SEAL WATER RETURN FROM RCP-A DRAWINGS: B-34 Summary Exam Number Categ aaaaaa aaassaaa 601000 SN-VT Item Number Component aaaaaaa aaaaassaaaaaaaaaaaaaaaa CVU-186 MECHANICAL SNUBBER NDE Component Type Exam imssassssaaassssaa ass AUG VT-3 e
94 -S/N 16541, TEMP.
73 DEG. F.,
SETTING 1-3/4N, PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G15. 2" LETDOWN LINE TO NON-REGEN HTX DRAWINGS: B-35 Summary Exam Item Number Categ Number assssass aaassaa aaassa 60104 s)
SN-VT Component Component Type NDE Exam aaaaaaaaaassssaa aaaaaa aaaaaaaaaaaaaaass aa CVU-345 AUG MECHANICAL SNUBBER 94 -S/N 9491, TEMP.
255 DEG. F.,
SETTING 1-1/4",
PSA-1/2.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601060 SN-VT CVU-351 AUG MECHANICAL SNUBBER 94 -S/N 9472, TEMP.
288 DEG. F.,
SETTING 3/4", PSA-1/2",
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G16.
CVCS LETDOWN LINE TO MIX BED DEMZN DRAWINGS: B-36 Summary Exam Number Categ 601080 SN-VT Item Number Component assssaa aassaa assssaaaaassaassssssa CVU-372 MECHANICAL SNUBBER NDE Component Type Exam aaaaaaaaaaaaa aa aaaa AUG VT-3 94 -S/N 9490, TEMP.
83 DEG. F.,
SETTING 1", PSA-1/2. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
65
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ch er a
& Ele ri r
Eas Av R
hes r NY 1464
- 2. Plant R
E Ginna Nu 1 ar P
w r Plant 1503 Lak Road Ontario NY 1451
- 3. Plant Unit 1
- 4. owner certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~ul
~1 7
6.National Board Number for Unit
~N ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G17.
PEEDWATER LOOP A INSIDE CV DRAWINGS: B-12 Summary Exam Number Categ 601100 SN-VT Item Number Component CR RRR OCCSR FWU-3 HYDRAULIC SNUBBER NDE Component Type Exam aaas=saazaaaasaa=
= aa AUG VT-3 94 -S/N 2500 10 153, TEMP.
74 DEG. F.,
SETTING 4", HSSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601101 SN-FT FWU-3 AUG HYDRAULIC SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
FT 601110 SN-VT FWU-5 HYDRAULIC SNUBBER AUG 94 -S/N 2500-10-152, TEMP.
74 DEG. F.,
SETTING 2 5/8",
HSSA-10. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G18.
PEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Number 601120 Exam Categ SN-VT Item NDE Number Component Component Type Exam
--aa--a aaaaaaasc=aaaaaaaaaaaa aaaa asssas aasaaa aasa FWU-8 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 8033, TEMP.
70 DEG. F.,
SETTING 3-1/8",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601130 SN-VT FWU-12 AUG MECHANICAL SNUBBER 94 -S/N 8034, TEMP.
78 DEG. F.,
SETTING 3-1/8",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
66
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Ro hester as
& Elec ric C r E
Ave Roches er NY 1464
- 2. Plant R
E Ginn Nu l r P
w r Pl n 1
3 Lak Road ntari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A s,commercial service Date Julvul70 S.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT
~
G19.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-11 Summary Exam Number Ca teg 601140 SN-VT Item Number NDE Component Component Type Exam ma==-fmaa==-aaa=-fmafaaaa amaaaafmfmatmr=aamaa=
aaaa FWU-15 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 9358, TEMP.
260 DEG. F.,
SETTING 2 7/8NN PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601150 SN-VT FWU-17 AUG MECHANICAL SNUBBER 94 -S/N 9392, TEMP. 260 DEG. F.,
SETTING 4 3/4Na PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601160 SN-VT FWU-18 AUG MECHANZCAL SNUBBER 94 -S/N 7067, TEMP.
260 DEG. F.,
SETTING 4 1/8NN PSA-35
'T-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601170 SN-VT FWU-20 AUG MECHANICAL SNUBBER 94 -S/N 7049, TEMP. 260 DEG. F.,
SETTING 2 1/4",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601180 SN-VT FWU-21 AUG HYDRAULIC SNUBBER 94 -S/N 2500-20-38, TEMP.
260 DEG. F.,
SETTING 3 3/4",
B-P SIZE 20, FLUID LEVEL 8 50<. VT-3: NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
VT-3 601190 SN-VT FWU-23 MECHANICAL SNUBBER AUG 94 -S/N 8630, TEMP. 260 DEG. F.,
SETTING 3 1/4", PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601200 SN-VT FWU-24 AUG MECHANICAL SNUBBER 94 -S/N 10061, TEMP.
260 DEG. F.,
SETTING 2 3/4",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
VT-3 67
R.
E ~
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches r
s
& Electric Cor 8
E t Ave Roches r NY 1464
- 2. Plant R.E Ginna N
lear P
w r Plant 1503 L ke R a On ario NY 14519
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~1~1')~7 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT
~
FEEDWATER LOOP A OUTSIDE CV (CONT.)
DRAWINGS: B-11 Summary Exam Number Categ 601209 SN-VT Ztem Number Component aaaaaaa aaaaaaaaaaaaaaaaaaaaaa FWU-26 (EAST)
MECHANICAL SNUBBER NDE Component Type Exam a
aaaaaaassa aaa aa AUG VT-3 94 -S/N 18179, TEMP.
260 DEG. F.,
SETTING 2 3/4",
PSA-3.
VT-3:
NO RECORDABLE INDZCATZONS; -ACCEPTABLE.
601210 SN-VT FWU-26 (WEST)
AUG MECHANICAL SNUBBER 94 S/N 18 180 I TEMP ~
260 DEG F ~
SETTING 2 3/4 PSA 3
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
VT-3 G20.
REEDWATER LOOP B OUTSIDE CV DRAWINGS: HE-5 Summary Exam Item Number Categ Number aa aaa aaaa a
ssaaaaass 601220 SN-VT Component ssaaaaaa=assssa=
assssaaaaa FWU-32 MECHANICAL SNUBBER NDE Component Type Exam aassaassaaaaaaaaaa aaaa AUG VT-3 94 -S/N 7053, TEMP.
260 DEG. F.,
SETTING 3 1/8",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS &. INSIGNIFICANT; ID TAG HAS A TEAR IN IT, STROKE
& DESIGN LOAD CANNOT BE READ
-ACCEPTABLE.
601230 SN-VT FWU-38 MECHANICAL SNUBBER AUG 94 S/N 93 95 s TEMP 260 DEG F
s SETTING 3
PSA 35 VT 3 NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601240 SN-VT FWU-39 MECHANICAL SNUBBER AUG 94 -S/N 9354, TEMP.
72 DEG. F.,
SETTING 3 1/2",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; GREASE ON SUPPORT END OF SNUBBER -ACCEPTABLE.
68
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester as
& El ric Cor 8
E Ave.
R chester NY 14649
- 2. Plant R
E irma N clear P
w r Pl n 1503 Lak R a n
rio NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date +>~11'170 6.National Board Number for Unit ~NA ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT REEDWATER LOOP B OUTSIDE CV (CONT.)
DRAWINGS: HE-5 Summary Number 601250 Exam Categ SN-VT Item Number Component FWU-40 MECHANICAL SNUBBER NDE Component Type Exam
&$5 &&MM MMRt &&ZS &
AUG VT-3 94 -S/N 7066, TEMP.
266 DEG. F.,
SETTING 3",
PSA-35. VT-3:
NO RECORDABLE ZNDZCATIONS; -ACCEPTABLE.
601260 SN-VT FWU-42 MECHANICAL SNUBBER AUG 94 -S/N 6159, TEMP.
260 DEG. F.,
SETTING 3 1/2",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601270 SN-VT FWU-44 AUG HYDRAULIC SNUBBER 94 S/N G43864 02 20 TEMP 260 DEG F
SETTING 4 1/2n HSSA-30. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; OIL LEVEL AT 3 DIVISIONS -ACCEPTABLE.
601280 SN-VT FWU-47 AUG MECHANICAL SNUBBER 94 -S/N 7474, TEMP.
200+
DEG. F.,
SETTING 2.375",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; INSULATION DAMAGED, T/C WRITTEN, PIGEON FECES
-ACCEPTABLE'01290 SN-VT FWU-48 AUG MECHANICAL SNUBBER 94 -S/N 7475, TEMP.
200+
DEG. F.,
SETTING 2.875",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; NO ID TAG &
PIGEON FECES
-ACCEPTABLE.
601300 SN-VT FWU-51 AUG MECHANICAL SNUBBER 94 -S/N 7483, TEMP. 200 DEG. F.,
SETTING 2.625",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; NO ID TAD &
PIGEON FECES
-ACCEPTABLE.
VT-3 69
R.
E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roche er Gas
& Ele ri r
Eas Ave.
R h
r NY 14 4
- 2. Plant R.E.Ginna Nu 1
r Power Pl n 1
03 Lake R
Ontario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial Service Date
~Jul l 7 6.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
FEEDWATER LOOP B OUTSIDE CV (CONT.)
DRAWINGS: HE-5 Summary Exam Number Categ Item Number Component Component Type aaaaaaa a as aaasaa a
a aaaaaa sass as aaaaas 601310 SN-VT FWU-52 AUG MECHANICAL SNUBBER 94 -S/N 8607, TEMP.
200+
DEG. F.,
SETTING 1.9375am PSA-10.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES - ACCEPTABLE.
NDE Exam VT-3 601320 SN-VT FWU-54 MECHANICAL SNUBBER AUG 94 -S/N 7482, TEMP.
44 DEG. F.,
SETTING 4.25",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
601333 SN-VT FWU-57 MECHANICAL SNUBBER AUG 94 -S/N 10064, TEMP.
44 DEG. F.,
SETTING 2.812",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
G21.
MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Exam Number Categ 601350 SN-VT Item Number Component Component Type sass assssss aaaaaassasasaasass aa asaaaaaassssss MSU-2 AUG MECHANICAL SNUBBER NDE Exam VT-3 94 -VT: REJECT; SNUBBER BODY TO EXTENSION & PROTECTIVE SHIELD IS LOOSE, SNUBBER CAN BE TURNED. NCR94-018 GENERATED.
FUNCTIONAL TESTED-ACCEPTABLE.
NOT SERVICE INDUCED; INSTALLATION PROBLEM. S/N 7087, TEMP.
73 DEG.F.,
SETTING 3 5/8",PSA-35.VT-3;ACCEPT.
601351 SN-FT MSU-2 AUG MECHANICAL SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
WO 19401004 FT 70
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999
- Znterva1, Second Period, Third Outage (1994) 1.
Owner R chester a
'6 Electric Cor 8
E Ave R
h s er NY 1464
- 2. Plant R
E Ginna Nucl r
P wer Pl n 1
Lake R ad n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~1
~1 70 6.National Board Number for Unit
~N A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT.
MAIN STEAM LOOP A INSIDE CV (CONT.)
DRAWINGS: B-8 Summary Exam Item 601360 SN-VT NDE Component Component Type Exam aaaaaaassaaaaaaaaaaaassa aaaaaa=aaaaaaaaa assaa MSU-3 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 7060, TEMP.
90 DEG. F.,
SETTING 3 3/16",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; SNUBBER BODY TO EXTENSION WASHER IS LOOSE
-ACCEPTABLE PER MECHANICAL ENGINEERING.
G22.
MAIN STEAM LOOP B INSIDE CV DRAWINGS: B-8 Summary Number 601369 Exam Categ SN-VT Ztem Number Component ss ssssaaaaaa aa
'aaaaaa MSU-7 (TOP/WEST)
MECHANICAL SNUBBER NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa AUG VT-3 94 -S/N 7051, TEMP.
66 DEG. F.,
SETTING 2 1/2",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601370 SN-VT MSU-7 (BOTTOM/EAST)
AUG MECHANICAL SNUBBER 94 S/N 7047 TEMP 66 DEG F
SETTING 2 3/4 s
PSA 35 VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601380 SN-VT MSU-8 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 620968-1-30, TEMP.
90 DEG. F.,
SETTING 3-3/4",
BERGEN 6n STROKE VT-3 NO RECORDABLE INDICATIONS 6c INSIGNIFICANT; FLUID LEVEL 1-5/8 AND OIL RESIDUE ON SNUBBER
-ACCEPTABLE.
71
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ch s er Gas El ctric r
8 Eas Ave Rochester NY 1464
- 2. Plant R
E irma N l ar P wer Pl n 1
03 Lak Road Ontario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.commercial service Date Julvul 70 S.National Board Number for Unit N~A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT.
G23.
MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10A Summary Exam Number Categ 601390 SN-VT Item NDE Number Component Component Type Exam xaam===
=afmaasssfmssas---aaafaafmafmsm a=aaaaafmafmaas-aaa afmfmfm MSU-12 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 9400, TEMP.
44 DEG. F.,
SETTING 3.56N e
PSA-35. VT-3:
NO RECORDABLE INDICATIONS & ZNSZGNIFICANTJ PIGEON FECES ON SNUBBER -ACCEPTABLE.
601399 SN-VT MSU-13 (EAST)
MECHANICAL SNUBBER AUG 94 -S/N 14676 TEMP.
44 DEG. F.,
SETTING 3.5",
PSA-100.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
601403 SAN-VT MSU-13 (WEST)
AUG MECHANICAL SNUBBER 94 -S/N 1464, TEMP.
44 DEG. F.,
SETTING 3.5NN PSA-100.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
601409 SN-VT MSU-15 (NORTH)
MECHANICAL SNUBBER AUG 94 -S/N 7476, TEMP.
>150 DEG. F.,
SETTING 3-3/4NN PSA-35, VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601410 SN-VT MSU-15 (SOUTH)
AUG MECHANZCAL SNUBBER 94 -S/N 7477, TEMP.
>150 DEG. F.,
SETTING 4-1/8".
PSA-35, VT-3:
NO RECORDABLE INDICATIONS & ZNSIGNIFICANT; PZGEON FECES
& BOOT SHOWS SIGNS OF TWISTING -ACCEPTABLE.
601419 SN-VT MSU-16 (NORTH)
AUG MECHANICAL SNUBBER 94 -S/N 7481, TEMP.
44 DEG. F.,
SETTING 2 3/4",
PSA 35.
VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
VT-3 72
R.
E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ches r
as
& Electric or Ea Av R
hes r NY 1464
- 2. Plant R
E Ginn Nuclear P
w r Plan 150 L k R
n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N 5.Commercial Service Date ~Ji~11~7 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
MAZN STEAM LOOP B OUTSIDE CV (CONT.)
DRAWINGS: B-10A Summary Exam Number Categ 601420 SN-VT Item Number Component aaaaa MSU-16 (SOUTH)
MECHANICAL SNUBBER NDE Component Type Exam aaaaaaaaaaaaaaaa aaaa AUG VT-3 94 -S/N 7480, TEMP.
40 DEG. F.,
SETTING 3 1/2",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS -ACCEPTABLE.
601421 SN-FT MSU-16 (NORTH)
MECHANICAL SNUBBER AUG 94 "FT: OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400471.
601422 SN-FT MSU-16 (SOUTH)
AUG MECHANICAL'SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400472.
601429 SN-VT MSU-18 (NORTH)
AUG MECHANICAL SNUBBER 94 -S/N 7478, TEMP.
44 DEG. F.,
SETTING 2.25",
PSA-35. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
FT 601430 SN-VT MSU-18 (SOUTH)
MECHANICAL SNUBBER AUG VT-3 94 S/N 7479 TEMP 44 DEG F
SETTING 2 375
)
PSA 35 VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
601439 SN-VT MSU-19 (NORTH)
MECHANICAL SNUBBER AUG 94 -S/N 9369, TEMP.
44 DEG. F.,
SETTING 2.437",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
73
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner R chester
& Electric r
East Ave R
h r NY 1464
- 2. Plant R
E Ginna Nu l r P wer Plant 150 Lake Roa ntario NY 1451
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~1
~1 7
6.National Board Number for Unit ~A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT.
MAIN STEAM LOOP B OUTSZDE CV (CONT.)
DRAWINGS: B-10A Summary Exam Number Categ 601440 SN-VT Item Number Component MSU-19 (SOUTH)
MECHANICAL SNUBBER NDE Component Type Exam saaa-------aaaaaa anal AUG VT-3 94 "S/N 9372, TEMP.
44 DEG. F.,
SETTING 2.375",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
601450 SN-VT MSU-22 AUG MECHANICAL SNUBBER
.94 -S/N - MISSING, TEMP.
44 DEG. F.,
SETTING 2.125" PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; NO ID TAG, W/0 002485 GENERATED.
PIGEON FECES ON SNUBBER -ACCEPTABLE.
60146'3 SN-VT MSU-25 AUG MECHANICAL SNUBBER 94 -S/N 1465, TEMP.
44 DEG. F.,
SETTING 1.375" PSA-100.
VT-3:
NO RECORDABLE INDICATIONS & INS1GNZFICANT; PIGEON FECES ON SNUBBER -ACCEPTABLE.
VT-3 VT-3 601469 SN-VT MSU-26 (TOP)
MECHANICAL SNUBBER AUG VT-3 94 -S/N 9355, TEMP.
40 DEG. F.,
SETTING 4.750",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNZFICANT; NO ID TAG, T/C GENERATED -ACCEPTABLE.
601470 SN-VT MSU-26 (BOTTOM)
MECHANICAL SNUBBER AUG 94 -S/N 4686, TEMP.
40 DEG. F.,
SETTING 4.375",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS &. INSIGNIFICANT; NO ID TAG, T/C GENERATED -ACCEPTABLE.
601471 SN-FT MSU-26 (TOP)
MECHANICAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
<<ACCEPTABLE.
74
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches r Ga Ele ric C r 8
East Av R
h ster NY 14649
- 2. Plant R.E irma N l r P wer Pl n 1
03 Lak R ad n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial Service Date
~Jul l 7 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
MAIN STEAM LOOP B OUTSIDE CV (CONT.)
DRAWINGS: B-10A Summary Number 601472 Exam Categ SN-FT Item Number Component
====a@a a=aaaaa:a-aaaaaaaaasaaaaaaaa MSU-26 (BOTTOM)
MECHANICAL SNUBBER NDE Component Type Exam
&&&MMMMSNfNNtta MMBB&
&BN AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400464.
601480 SN-VT MSU-27 MECHANICAL SNUBBER AUG 94 -S/N 9398, TEMP. )150 DEG. F.,
SETTING 4-1/2",
PSA-35, VT-3:
NO RECORDABLE ZNDICATIONS 6( INSIGNZFZCANT; PIGEON FECES
-ACCEPTABLE.
601490 SN-VT MSU-29 MECHANICAL SNUBBER AUG 94 -S/N 1469, TEMP. )350 DEG. F.,
SETTING 4-1/4",
PSA-100.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601500 SN-VT MSU-31 MECHANICAL SNUBBER 94 -S/N 9356, TEMP.
69 DEG. F.,
SETTING 1 1/8", PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601501 SN-FT MSU-31 MECHANICAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400474.
601510 SN-VT MSU-32 MECHANICAL SNUBBER AUG 94 -S/N 1093, TEMP.
325 DEG. F.,
SETTING 2-1/2",
PSA-100.
VT"3: NO RECORDABLE INDICATIONS; "ACCEPTABLE.
75
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h r
El ri 8
Ea Av R
h r NY 1464
- 2. Plant R.E.
inn Nuclear Pow r Pl n 1503 Lake R
d n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date
~Jul l 7 6.National Board Number for Unit ~NB ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G24.
MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9A Summary Exam Number Categ aaa a
assssaa 601520 SN-VT Item NDE Number Component Component Type Exam aaaassaa aaaaaaaaaaaaaaaaaaaaaa aaaaassssaaaaaaaaa aaaa MSU-38 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 1090, TEMP.
210 DEG. F.,
SETTING 1-1/2",
PSA-100.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601530 SN-VT MSU-39 MECHANICAL SNUBBER AUG 94 -S/N 1087, TEMP.
73 DEG. F.,
SETTING 4 3/4",
PSA-100.
VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; MANUFACTURERS ID TAG HAS A BROKEN RIVET Ec RGScE TAG (MSU-39)
IS MZSSING, T/C GENERATED.
-ACCEPTABLE.
601540 SN-VT MSU-40 MECHANICAL SNUBBER AUG VT-3 94 S/N 1 080 6 TEMP 72 DEG F
6 SETTING 3 3/4 6
PSA 100 VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601541 SN-FT MSU-40 MECHANZCAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400475.'01550 SN-VT MSU-44 MECHANICAL SNUBBER AUG 94 -S/N 1468, TEMP. )350 DEG. F.,
SETTING 3-1/8",
PSA-100.
VT-3; INSIGNIFICANT; PAINTED OVER, PAINT SCRAPPED
- OFF, SCALE ACCEPTABLE.
76
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h r
a El ric r
8 E
Av R
h r NY 14649
- 2. Plant R
E irma Nu lear P wer Plant 1503 Lake Road Ontario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date Q~l
~997. 6.National Board Number for Unit
~N A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CO G25.
MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam aaacscs QRRJQ QQCSRSQR RRRSQRR RRRRNRRRRSNSCRCCR RCISSSSC5$ $
RCQzSSSR5C5CC SCSRSC5 601560 SN-VT MSU-55 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 18195, TEMP.
64 DEG. F.,
SETTING 2 7/8",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; "ACCEPTABLE.
601561 SN"FT MSU-55 MECHANICAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
601570
,SN-VT MSU-57 MECHANICAL SNUBBER AUG 94 -S/N 10161, TEMP.
130 DEG. F.,
SETTING 2 1/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G26.
MAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS'-9A Summary Exam Item Number Categ Number CROSS OZRSRER SSNOC5 601580 SN-VT NDE Component Component Type Exam zsossassaaaasssseaaaaaosassa ssaaaaaaaaaaaaaaa asaa MSU-58 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 18187, TEMP.
425 DEG. F.,
SETTING 2",
PSA-3. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601590 SN-VT MSU-60 MECHANICAL SNUBBER AUG 94 -S/N 10107, TEMP. )200 DEG. F.,
SETTING 2 1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
77
R.
E ~
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Ro h r Gas
& El ric r
8 E s Av R
h s r NY 14 4
- 2. Plant R.E Ginna Nuclear Power Plan 1
3 Lake R
d n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.Commercial Bervfce Date
~Jul 1 70 6.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G27.
MAIN STEAM LOOP B TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item Number Categ Number a a mt aaafmlmttaaa 601600 SN-VT Component aa aaaaaaaaaa aaaaaa MSU-72 MECHANICAL SNUBBER NDE Component Type Exam aaaaaaaa AUG VT-3 94 S/N 15767 f TEMP 180 DEG F
SETTING 2 1/2 PSA 3
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601610 SN-VT MSU-74 AUG MECHANICAL SNUBBER 94 -S/N 10066, TEMP.
235 DEG. F.,
SETTING 3-1/4NA PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
VT-3 G28.
MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS c B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam aaaaaa aaaaaaa aaaaaaa aaaaaaaaaaaaaaaaaaamaaa aaaaaaaaaaataaaaaa sass 601620 SN-VT MSU-75 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 8030, TEMP.
135 DEG.
F.
(HOT),
SETTING 2",PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G29.
MAIN STEAM LOOP A TO AUX PW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item Number Categ Number aaaaaa aaaaaaa aaaaaaaamt 601630 SN-VT NDE Component Component Type Exam aaaaaaaaaaaaaaaaaaaaaa aaaaaaaaaaaaaaaa sass MSU-78 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 8576, TEMP.
180 DEG. F.,
SETTING 3-1/16",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601640 SN-VT MSU-80 AUG MECHANICAL SNUBBER 94 -S/N 18181, TEMP.
180 DEG. F.,
SETTING 2-1/16mB PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
78
R. E.
GZNNA NUCLEAR POWER PLANT
~ Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R ch r
s
& El ric Cor East Av R
he r NY 14 4
- 2. Plant R
E inn Nuclear Power Plan 1
Lak Road Ontari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~Jul 1
70 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
MAIN STEAM LOOP A TO AUX PW PUMP TURBINE (CONT.)
DRAWINGS: C-32 Summary Exam Number Categ 601650 SN-VT Item Number NDE Component Component Type Exam falafel---ssasasssssasaaaaafnaa tNSNtaa aaaaaafnass a
ataaa MSU-82 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 15768, TEMP.
180 DEG. F.,
SETTING 2-7/8" PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601659 SN-VT MSU-84 (EAST)
MECHANICAL SNUBBER AUG VT-3 94 -S/N 10108, TEMP.
64 DEG. F.,
SETTING 3 1/8",
PSA-3.
VT-3:
NO RECORDABLE INDZCATIONS; -ACCEPTABLE.
601663
-SN-VT MSU-84 (WEST)
MECHANICAL SNUBBER AUG 94 -S/N 10141, TEMP.
64 DEG. F.,
SETTING 2 3/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601661 SN-FT MSU-84 (EAST)
MECHANICAL SNUBBER AUG 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400465.
601662 SN-FT MSU-84 (WEST)
AUG MECHANICAL SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400466.
FT 601670 SN-VT MSU-85 MECHANICAL SNUBBER AUG 94 S/N 10074 TEMP
)350 DEG F
~
6 SETTING 3 3/8 PSA 10 VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
79
1 C'
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R chester Gas
& Elec ric Cor 8
Ea Ave.
Roches r NY 1464
- 2. Plant R
E irma N l r P
w r Plan 1
Lake Road On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date ~ul l 70 6.National Board Number for Unit jNA ATTACHMENT X SNUBBER PROGRAM COMPONENTS CONT s
G30.
6-XN. RESZD HT REMOVAL TO RPV (LHSZ)
DRAWINGS: B-17 Summary Exam Number Categ K SS SS SS SS SS SS 601680 SN-VT Xtem Number Component SSR&&M&
tS SS SSSSSSSSSSSSSSSSSSSSSSSSSS RHU-8 MECHANICAL SNUBBER NDE Component Type Exam SSSSSSSSSSSSSSSSQSSSSre SSS SS AUG VT-3 94 -S/N 15775, TEMP.
62 'DEG. F.,
SETTING 2 1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601681 SN-FT RHU-8 AUG MECHANICAL SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400477.
FT G31.
RESIDUAL HEAT REMOVAL PROM LOOP A HOT LEG DRAWINGS s A-15 Summary Number 601690 Exam Categ SN-VT Item Number NDE Component Component Type Exam SSSSSSSSSSSSSSSSSSRRRRR 0>>
SS SSSSSSSSSSSSSSSRRCRRRRR SSSSSSSS RHU-30 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 7065, TEMP.
80 DEG. F.,
SETTING 1", PSA-35.
VT-3:- NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601700 SN-VT RHU-33 MECHANICAL SNUBBER AUG 94 -S/N 7064, TEMP.
73 DEG. F.,
SETTING 3-1/8",
PSA-35.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G32.
RESIDUAL HEAT REMOVAL LXNE 8B-AC-601 DRAWINGS: B-23 Summary Number 601710 Exam Categ 0 SS SS SS SS SN-VT Item Number Component SSSSaaaaa aaaaSSSSSSSSSSSSSSaaaaar=aSSSSSS RHU-36 MECHANICAL SNUBBER NDE Component Type Exam SSSSSSSSSSSSMMMMMM 5 &SSSS AUG VT-3 94 -S/N 15756, TEMP.
62 DEG. F.,
SETTING 2-1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
80
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Rochester Ga
& Electric r
8 Eas Av R
h ster NY 1464
- 2. Plant R
E Ginna N l ar Power Pl n 1
0 Lake Road n ri NY 14 1
- 3. plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date
~J 1
~1 7g. 6.National Board Number for Unit
~N A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT G33.
RESZDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-25 Summary Exam Number Categ 601720 SN-VT Item Number Component RHU-51 MECHANICAL SNUBBER NDE Component Type Exam AUG VT-3 94 S/N 15752 TEMP 74 DEG F
SETTING 2 3/8n PSA 3
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601730 SN-VT RHU-53 AUG MECHANICAL SNUBBER 94 -S/N 15754, TEMP.
74 DEG. F.,
SETTING 2 3/4",
PSA-3.
VT-3:
NO RECORDABLE 1NDZCATZONS;'ACCEPTABLE.
601731 SN-FT RHU-53 AUG MECHANICAL SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
FT G34.
RESIDUAL HEAT REMOVAL LINE 6D-AC-601 DRAWINGS) B-26 Summary Number 601740 Exam Categ SN-VT Item Number NDE Component Component Type Exam aaaaaassssssa aaaaaassssssssa aaaaaaaaaaassaaass aaaa RHU-61 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 15753, TEMP.
74 DEG. F.,
SETTING 2-1/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G35.
RESIDUAL HEAT REMOVAL LINE 10E-AC-601 DRAWINGS: B-20 Summary Exam Number Categ aaaaaaa 601749 SN-VT Item Number Component Component Type aaaaaaassaaaaaaaaaaaaaa aaaaaaaaaaassassssa RHU-63 (NORTH)
AUG MECHANICAL SNUBBER NDE Exam VT-3 94 -S/N 16380, TEMP.
65 DEG. F.,
SETTING 2-15/16",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
81
0
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
he ter El ric Cor 8
E Ave.
R h
r NY 1464
- 2. Plant R.E.Ginna N l r Power Plan 1
L ke Road On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date Qi~ll')70 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
RESIDUAL HEAT REMOVAL LINE 10E-AC-601 (CONT. )
DRAWINGS: B-20 Summary Exam Number Categ 601750 SN-VT Item Number NDE Component Component Type Exam MMWMMMRRXSlRCCXRSC&&
MMMM CISSCC$ 8$5$CCSCCM
&St
&ICRRR5 RHU-63 (SOUTH)
AUG VT-3 MECHANICAL SNUBBER 94 S/N 16375
~
TEMP 65 DEG F
~
SETTING 3
PSA 1
VT 3 NO RECORDABLE INDICATIONS; "ACCEPTABLE.
G36.
RESIDUAL HEAT REMOVAL LINE 10G-AC-601 DRAWINGS: B-20A Summary Number 601760 Exam Categ SN-VT Item Number Component RHU-69 MECHANICAL SNUBBER NDE Component Type Exam AUG VT-3 94 -S/N 8629, TEMP.
62 DEG. F.,
SETTING 2-1/2",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601769 SN-VT RHU-71 (NORTH)
AUG MECHANICAL SNUBBER VT-3 94 -S/N 11466, TEMP.
65 DEG. F.,
SETTING 2-1/2", PSA-l.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601770 SN-VT RHU-71 (SOUTH)
AUG MECHANICAL SNUBBER 94 -S/N 11465, TEMP.
65 DEG. F.,
SETTING 2-5/8",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G37.
RHR PUMP A SUCTION LINE DRAWINGS: B-20A Summary Exam 1tem Number Categ Number asm'==
ascsaaaa aaaaasm 601780 SN-VT NDE Component Component Type Exam aaaaaaaarsscsaeaaaaaaaaa maaeseaassa
=mama amass RHU-72 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 8606, TEMP.
62 DEG. F.,
SETTING 3 1/16",
PSA-10, VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
82
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch er
& Electri or 89 Ea t Av R ch s er NY 1464
- 2. Plant R
E Ginna Nuclear Power Plan 1
03 Lake R
On ari NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date $~1~17 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
~
G38.
RESIDUAL HEAT REMOVAL LINE 10D-AC-601 DRAWINGS: B-20 Summary Number 601790 Exam Categ SN-VT Ztem Number Component
--a-a@a aaaaa-aaaaa
=aaaaassaa RHU-75 MECHANICAL SNUBBER NDE Component Type Exam
&&CC&2R MWlSXS AUG VT-3 94 -S/N 8632, TEMP.
62 DEG. F.,
SETTING 3-1/2",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G39.
RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Exam Number Categ arm===
a----aa 601800 SN-VT Item Number Component Component Type
&&St&
MMMM SSSRM&
&RIES MMWRSXR$$ $5 RHU-92 AUG MECHANICAL SNUBBER NDE Exam VT-3 94 -S/N 16376, TEMP.
62 DEG. F.,
SETTING 2 1/4" PSA-l.
VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT; BORON CONTAMINATION & CORROSION, SCALE ON PISTON BARELY LEGIBLE, TC 002484 GENERATED -ACCEPTABLE.
G40. H.P.
SAFETY INJECTION LINE FROM RWST DRAWINGS: B-19 Summary Exam Number Categ 601810 SN-VT Ztem Number Component Component Type
--aaaaa arsaazsaaaaaaa aaaa--aaa aaaaassa aaaaea a
RHU-109 AUG MECHANICAL SNUBBER NDE Exam VT-3 94 -S/N 11463, TEMP.
71 DEG. F.,
SETTING 2-1/8",
PSA-1.
VT-3:
NO RECORDABLE INDZCATIONS; -ACCEPTABLE.
601820 SN-VT RHU-110 AUG MECHANICAL SNUBBER 94 -S/N 16373, TEMP.71 DEG. F.,
SETTING 2-1/8",
PSA-1. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
83
R. E.
G1NNA NUCLEAR POWER PLANT Zn service Znspec tion Repor t 1990-1999 Znterval, Second Period, Third Outage (1994) 1.
Owner Roche r
Ele ri Cor East Ave R
h er NY 14 4
- 2. Plant R
E Ginna Nuclear Pow r Plan 1
L k Ro d ntario NY 14519
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date ~Jul 1 vo S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G41. H.P.
SAFETY INJECTION PUMP A SUCTION LINE DRAWINGS: B-16B Summary Exam Number Categ aaa aaaaaaa 601830 SN-VT Item Number Component aaaaaaa eaaaaaaaa aaaaaaaaaaaa RHU-119 MECHANICAL SNUBBER NDE Component Type Exam sass assess sass sees AUG VT-3 94 -S/N 15766, TEMP.
78 DEG. F.,
SETTING 1 5/8NA PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
601831 SN-FT RHU-119 MECHANICAL SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400479.
G42. H.P.
SAFETY INJECTION LINE 8J-SI-151 DRAWINGS: B-19 Summary Exam Item Number Categ Number a
assam aaaaaRRR aaasaaa 601840 SN-VT NDE Component Component Type Exam aaaasssaaaasssassaaaasa asaasassaaasaaas sass RHU-123 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 15765, TEMP.
83 DEG. F.,
SETTING 2-1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G43. H.P.
SAFETY ZNiTECTZON LINE TO LOOP A COLD LEG DRAWINGS! A-17 Summary Exam Item Number Categ Number
==-scca aaaaaaa aaaaaaa 601850 SN-VT NDE Component Component Type Exam aaaaaaaaaaasasaasa aaaaa aaaaaaaaaaaaaaaaasSN sass SIU-3 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 8614, TEMP.
78 DEG. F.,
SETTING 3"1/4",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
84
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R chester as
& Ele ric r
East Av Ro h s er NY 14 4
- 2. Plant R.E irma Nuclear Pow r Pl n 1
L k R ad On ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A S.Commercial Service Date tulvu175 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G44. H.P.
SAFETY IN1TECTION LZNE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Exam Number Categ 601860 SN-VT Item Number Component aaaaaaaaa aaaaaaaaaa SIU-47 MECHANICAL SNUBBER NDE Component Type Exam aaaassaa aaa aaa aaa AUG VT-3 94 S/N 15346 6
TEMP 72 DEG F
6 SETTING 3 6
PSA 3
VT 3 NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G45.
RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Exam Item Number Categ Number a a a ss ss ss a 601870 SN-VT NDE Component Component Type Exam aaaaaassaaaaaaaaaaassaaa aaaaaaassassaaaaaa ssaaa SZU-52 AUG VT-3 MECHANICAL SNUBBER 94 - S/N 15348, TEMP.
70 DEG. F.,
SETTING 2-1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G46.
SVC.WTR.-TO A & B DIESEL GEN.WTR.COOLERS DRAWINGS: C-13 Summary Exam Item Number Categ Number 601890 SN-VT NDE Component Component Type Exam aaaaaaaaaassassaaaaaaaaa ssaa aaaaaaaaaaaa aaaa SWU-254 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 12508, TEMP.
61 DEG. F.,
SETTING 1 1/8", PSA-1/2.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G47.
SERVICE WATER LINE 8L-SW-125 DRAWINGS: B-SOA Summary Exam Number Categ 601900 SN-VT Ztem Number Component aaaaaaaaaaaaaassaaaaaass SWU-308 MECHANZCAL SNUBBER NDE Component Type Exam assassa aass aa a
ass AUG VT-3 94 -S/N 8031, TEMP.
44 DEG. F.,
SETTING 2 7/8",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
85
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch r
6 El c ri r
8 Eas Ave R
h r NY 1464
- 2. Plant R
E Ginna Nucle r Pow r Plan 1
Lake Road On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 6 C.ommercial Service Date ~ul l 70 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
SERVICE WATER LINE 8L-SW-125 (CONT.)
DRAWINGS: B-50A Summary Exam Number Categ sea aats amaa 601910 SN-VT Ztem NDE Number Component Component Type Exam aaaaaaa aesaaaa aaaaaaaaaaaaaaa aaaaaatmaaaaaaaaa aaaa SWU-309 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 10073, TEMP.
44 DEG. F.,
SETTING 3 1/4",
PSA-10.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G48.
SVC.WTR.-1NTMD.BLDG.16"HD.TO PEN 312-320 DRAWINGS: C-16B Summary Number 601920 Exam Categ SN-VT Item Number NDE Component Component Type Exam aaaaaaaaaaaaaaamsaeaaaaa aaaaaaaaaaaaaaaa aaaa SWU-370 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 11464, TEMP.
55 DEG. F.,
SETTING 2 3/16",
PSA-1.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G49.
STANDBY AUX FW THRU PEN 123 TO B S/G FWHD INCV DRAWINGS) C-24 Summary Exam Number Categ 601930 SN-VT Item Number Component Component Type aaaaaaa aaaaaaaaaaa aaaaaaaaaa aaaaaaaaaaaaaaaa AFU-205 (AFW-10)
AUG HYDRAULIC SNUBBER NDE Exam VT-3 94 -S/N 15403, TEMP.
63 DEG. F.,
SETTING 3",
GRZNELL SIZE 1
1/2.
FLUZD LEVEL 3/4 FULL. VT-3: NO RECORDABLE INDICATIONS; "ACCEPTABLE.
601931 SN-FT AFU-205 (AFW-10)
AUG HYDRAULZC SNUBBER SUCCESSIVE 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400463.
601940 SN-VT AFU-208 (AFW-13)
HYDRAULIC SNUBBER AUG VT-3 94 -S/N 21010, TEMP.
70 DEG. F.,
SETTING 2-1/16",
GRINELL 1 1/2.
FLUID LEVEL 3/4 FULL. VT-3: NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
86
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester
& Electri Cor East Av R
h s r NY 1464
- 2. Plant R E.Ginna Nucl ar Pow r Plan 1503 Lake Road On ario NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date /~1~170 6.National Board Number for Unit ~NA ATTACHMENT Z SNUBBER PROGRAM COMPONENTS CONT.
G50.
STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV DRAWINGS: C-20 Summary Number 601970 Exam Categ SN-VT Ztem Number Component Component Type AFU-224 (AFW-28)
AUG HYDRAULIC SNUBBER NDE Exam 94 -S/N 12905, TEMP.
74 DEG. F.,
SETTING 2-3/8",
GRINELL 1-1/2.
FLUID 7/8 FULL. VT-3: NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
601980 SN-VT AFU-226 (AFW-27)
HYDRAULIC SNUBBER AUG 94 -S/N 12901, TEMP.
74 DEG. F.,
SETTING 3",
GRINELL 1-1/2.
FLUID 3/4 FULL. VT-3:
NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
601990 SN-VT AFU-225 (AFW-29)
HYDRAULIC SNUBBER AUG VT-3 94 -S/N 12906, TEMP.
70 DEG. F.,
SETTING 1 9/16",
GRINNEL 1 1/2.
FLUID LEVEL 3/4 FULL. VT-3:
NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
601991 SN-FT AFU-225 (AFW-29)
HYDRAULIC SNUBBER AUG FT 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
602000 SN-'VT AFU-227 (AFW-31)
MECHANICAL SNUBBER AUG 94 -S/N 22594, TEMP.
75 DEG. F.,
SETTING 4-1/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
87
R ~
E ~
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches er
& Elec ri Cor 8
E Ave.
R he er NY 1464
- 2. Plant R.E irma Nuclear Power Plant 1503 L k R a Ontario NY 14 1
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (Zf Req.)
~N A S.commercial service Date Julvulvo S.National Board Number for Unit N~A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G51.
PRESS.RELIEF FM PRESS.TO RELIEF MANIFOLD DRAWINGS:
S -2 Summary Exam Number Categ aaa assaa 602010 SN-VT Ztem Number Component m
maaam aammaamaaamaaaammmssassss N601 HYDRAULIC SNUBBER NDE Component Type Exam aaaaaaaassssssssa AUG VT-3 94 -S/N 6565, TEMP.
63 DEG. F.,
SETTING 3 3/4",
GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; NO ID TAG, FLUID LEVEL 7/8 FULL. -ACCEPTABLE.
602011 SN-FT N601 HYDRAULIC SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19400480.
FT 602020 SN-VT N602 HYDRAULIC SNUBBER AUG 94 -S/N 44707, TEMP.
70 DEG. F.,
SETTING 2 1/4NB GRINNELII SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & ZNSZGNIFICANT; RESIDUAL ON RESERVOIR ELBOW & FLUID 3/4 FULL -ACCEPTABLE.
602030 SN-VT N604 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 6566, TEMP.
70 DEG. F.,
SETTING 1 3/8Na GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; FLUID LEVEL 3/4 FULL -ACCEPTABLE.
602040 SN-VT N605 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 6561, TEMP.
70 DEG. F.,
SETTING 2 1/2",
GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; RESIDUAL ON SNUBBER BODY & FLUID LEVEL 3/4 FULL -ACCEPTABLE.
602050 SN-VT N607 HYDRAULIC SNUBBER 94 -S/N 6562, TEMP.
70 DEG. F.,
SETTING 3
SIZE 2. VT-3:
NO RECORDABLE INDICATIONS &
FLUID LEVEL 3/4 FULL -ACCEPTABLE.
AUG 1/2",
GRINNELL INSIGNIFICANT; 88
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Gas
& Electric r
8 E
Ave. Rochester NY 1464
- 2. Plant R
E inn Nucle r P
w r Pl nt 15 Lak R
ntari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~1~17 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
G51.
PRESS.RELZEF FM PRESS.TO RELIEF MANIFOLD DRAWINGS: S-2 Summary Exam Item Number Categ Number Component aaraaa aaa$ $ $$ $$ $$
$$ $$ $$ a$ $ $$ $$
$$ aa$ $ $.s$ $ $$ $$ $$ $$ $$ $$ aass$
$ $$sa 602060 SN-VT N608 HYDRAULIC SNUBBER NDE Component Type Exam RCSSO AUG VT-3 94 -S/N, 6563, TEMP.
70 DEG. F.,
SETTING 3 3/4",
GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; MINOR RESIDUAL ON RESERVOIR, FLUID LEVEL 5/8 FULL
-ACCEPTABLE.
602070 SN-VT N615 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 6364, TEMP.
70 DEG. F.,
SETTING 2 1/4",
GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & INSIGNIFICANT; FLUID LEVEL 5/8 FULL -ACCEPTABLE.
602080 SN-VT N616 HYDRAULIC SNUBBER AUG VT-3 94 -S/N 6567, TEMP.
70 DEG. F.,
SETTING 2 3/8",
GRINNELL SIZE 2. VT-3:
NO RECORDABLE INDICATIONS & ZNSZGNIFICANT; RESIDUAL OIL ON SNUBBER BODY & EXTENSION ROD, NO MEASURABLE LEAKAGE. FLUID LEVEL 3/4 FULL -ACCEPTABLE.
G52.
POWER PRESS.RELIEF LINE DRAWZNGS: S-1 Summary Number 602090 Exam Item Categ Number SN-VT NDE Component Component Type Exam
$$ $$ $$ %%$$ $$ $$ $$ CCRR RC$$ $$ $$ $$ $$
CCSRRRR RQ$ $ $$ $$ $$ $$ $$
PS-2 AUG VT-3 HYDRAULIC SNUBBER 94 -S/N PD87239-1244, TEMP.
70 DEG. F.,
SETTING 4",
PMH-2103. VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT; LIGHT OIL ON LOWER SNUBBER BODY, 1/4" GREEN
& 1/16" RED SHOWING -ACCEPTABLE.
602100 SN-VT PS-4 HYDRAULIC SNUBBER AUG 94 - S/N 86144-1152$
TEMP.
70 DEG. F.,
SETTING 1", 1/16" GREEN, 1/4"
- RED, PMH-2103. VT-3:
NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
89
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochest r Gas
& Elec ric Cor 8
E Ave R ch r NY 14 4
- 2. Plant R,E,Ginna Nucl ar P
w r Pl n 1
Lake Road Ontari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A B.commercial service Date
~cul 1 70 S.National Board Number for Unit ~NB SNUBBER PROGRAM COMPONENTS CONT s
G53.
3-ZN.
PRESSURIZER RELZEF LINE DRAWINGS: A-12 Summary Exam Number Categ 602110 SN-VT Item Number NDE Component Component Type Exam aaaasaasaaaaaaaaaaaaaa aaaaaa aaaaasaa sass PS-5 AUG VT-3 HYDRAULIC SNUBBER 94 S/N PD87239 1246 6
TEMP 70 DEG ~
F ~ f SETTING 2 3/4 1/4 GREEN, 1/8" RED, PMH-2103. VT-3:
NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
602120 SN-VT PS-6 HYDRAULIC SNUBBER AUG 94 S/N PD87767 1239 6
TEMP ~
70 DEG F
SETTING 11/16 1/8" GREEN, 1/4"
- RED, PMH-2103. VT-3:
NO RECORDABLE INDICATIONS; ACCEPTABLE.
60213t)
SN-VT PS-8 HYDRAULIC SNUBBER AUG 94 -S/N 86144-1159, TEMP.
70 DEG. F.,
SETTING 3NN PMH-2103, 1/16" GREEN
& 3/8" RED. VT-3: NO RECORDABLE INDICATIONS;
-ACCEPTABLE.
G54.
POWER PRESS.RELIEF LINE DRAWINGS:
S -lA Summary Exam Item Number Categ Number 602140 SN-VT NDE Component Component Type Exam aaaaaaaaaaaaeaaaaaaaaaa aaaaaaaa aaaaaaa sass PS-9 AUG VT-3 HYDRAULIC SNUBBER 94 -S/N PD86144-1154, TEMP.
70 DEG. F.,
SETTZNG 3-1/4' PMH 2 1 03 f 1/1 6 GREEN
& 3/8 RED ~ VT 3 NO RECORDABLE INDICATIONS; -ACCEPTABLE.
602150 SN-VT PS-10 HYDRAULIC SNUBBER AUG VT-3 94 -VT-3: REJECT; INSUFFICIENT FLUID. NCR94-027 GENERATED.
FUNCTIONAL TESTED SNUBBER -ACCEPTABLE. RE-EXAMINED AFTER REINSTALLATION &,FLUID FILLING. S/NPD86144-1157, TEMP.
62 DEG. F.,
SETTING 3 7/8",
PMH-2103. VT-3:NO RECORDABLE INDICATIONS-ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roch er Gas Electric Cor 8
Ea Ave R
hes r NY 14649
- 2. Plant R.E.
irma Nu l ar Pow r Pl nt 1503 Lake R a n ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A 5.Commercial Service Date Ji~11~I 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.
~
POWER PRESS. RELIEF LINE (CONT.)
DRAWiNGS:
S - 1A Summary Number a
602151 Exam Categ SN-FT Item NDE Number Component Component Type Exam aaaassssss aaaaaaaaaaaassassssssaaaaa aaaaaaaaaaaaaaaa aaaa PS-10 AUG FT HYDRAULIC SNUBBER 94 -FT:
OTHER:
FUNCTIONALLY TESTED SNUBBER;
-ACCEPTABLE.
¹ 19401110.
602160 SN-VT PS-11 HYDRAULIC SNUBBER AUG VT-3 94 -S/N PD86144-1156, TEMP.
70 DEG. F.,
SETTING 2 1/4",
PMH-2103, 5/16" RED & 1/16" GREEN. VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
G55.
SEAL WATER RETURN FROM RCP-B DRAWINGS: S-3 Summary Number 602200 Exam Ztem NDE Categ Number Component Component Type Exam aaaaaaa aassaaass a
aaaaaaaaaaaaaaaaaaa aaaaaaaaaaaaaaaa aaaa SN-VT CVU-131 AUG VT-3 MECHANICAL SNUBBER 94 -S/N 25432, TEMP.
74 DEG. F.,
SETTING 2-1/2",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
602300 SN-VT CVU-550 AUG MECHANICAL SNUBBER 94 -S/N 18190, TEMP.
74 DEG. F.,
SETTING 2-1/4",
PSA-3.
VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
'Number aaaaaa aaaaaaa aaaaaaa 602400 SN-VT NDE Component Component Type Exam aaaaaaaaaaassaaaaaaassaa aaaaaaaaaaaaaaaa aaaa AFU-209 AUG VT-3 HYDRAULIC SNUBBER 94 -S/N 12904, TEMP.
70 DEG. F.,
SETTING 2-1/4",
GRINELL 1-1/2, FLUID LEVEL 5/8 FULL. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches er
& El ri Cor 8
Ea Av R
h r NY 1464
- 2. Plant R.E irma Nu 1 ar P
w r Plan 1
Lak Rpad On ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.) ~A s,commeroial service Date
~Jul l vo S.National Board Number for Unit ~NA ATTACHMENT SNUBBER PROGRAM COMPONENTS CONT.
G57.
STANDBY AUX FW THRU PEN 119 TO A S/G FWHD INCV DRAWINGS: C-20 Summary Exam Number Categ BBBB a
sass 602500 SN-VT Ztem NDE Number Component Component Type Exam aaaaaaa aaaaaaaaaaaaaaaaaaaaaa aaraaaaaaaaaaaaaaaa sass AFU-229 AUG VT-3 HYDRAULIC SNUBBER 94 -S/N 12903, TEMP.
75 DEG. F.,
SETTING 2-1/4",
GRINELL 1-1/2, FLUID LEVEL 3/4 FULL. VT-3:
NO RECORDABLE INDICATIONS; -ACCEPTABLE.
H.
SEISMIC SUPPORT COMPONENTS:
Hl. 'UX FW PUMP DISCHARGE DRAWZNGS: C-1H Summary Exam Numb e ":Categ 700000 SS-CS Item Number Component Component Type a aaaaa aaaaBBNf a aataaaaaaaaaaa aaaaaaatmaaaaaaaa
H2.
2" LETDOWN LZNE DRAWINGS: A-23A Summary Exam Number Ca teg Bta a a a a Balm at as 700170 SS-CS Item Number Component aaaaataa aaaaaaaaaaaaaaaaaaaaaaa
- F1.20V CVU-39 VARIABLE SPRING NDE Component Type Exam aaaaamaaaaaaaaaaatta aaaa AUG VT-3 94 -VT-3: REJECT; INSUFFICIENT THREAD ENGAGEMENT, 5/8" NUT IS 1/8" BELOW FULL ENGAGEMENT.
SUPPORT AS PAINTED, 1 1/2 THREADS DISENGAGED.
NOT SERVICE INDUCED, ORIGINAL CONSTRUCTION.
NCR94-025 GENERATED-ITEMS REPLACED. VT-3:
NO RECORDABLE INDICATIONS, ACCEPTABLE.
R. E.
G1NNA NUCLEAR POWER PLANT Znservice 1nspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
hester Gas
& Elec ric C r 89 East Ave. Roches r NY 1464
- 2. Plant R.E.Ginna Nuclear Power Plant 1503 Lak Ro d n ario NY 1451
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date $~1~17 6.National Board Number for Unit ~NA ATTACHMENT I SEISMIC SUPPORT COMPONENTS CONT.
H3.
FEEDWATER LOOP B OUTSIDE CV DRAWINGS: B-,14 Summary Number 700200 Exam Categ SS-CS Item Number Component
- F1
. 20S FWU-39 MECHANICAL SNUBBER IA NDE.
Component Type Exam AUG 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE. TEMP.
72 DEG. F.,
SETTING 3 1/2".
700300 SS-CS "F1.20R FWU-29 RIGID SUPPORT
& IA AUG 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
84.
FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-5 Summary Exam Ztem Number Categ Number Component Component Type 700370 SS-CS
NO RECORDABLE INDICATIONS; -ACCEPTABLE. SETTING 3 3/4",
TEMP.
260 DEG.
F.
HS.
MAINSTEAM HIGH ENERGY SYSTEM DRAWINGS: HE-7 Summary Number 700440 Exam Categ SS-CS Item Number Component
- F1.20A MSU-35 ANCHOR & IA OE VT-3 NDE Component Type Exam 94 -VT-3: NO RECORDABLE INDICATIONS; -ACCEPTABLE.
93
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Roches r
& Electric C r 8
Eas Av Ro he r NY 1464
- 2. Plant R.E.
irma N
lear P
w r Plant 1503 Lak Road ntari NY 14 1
- 3. Plant Unit 1
- 4. Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date
~ul
~1 70 6.National Board Number for Unit
~N ATTACHMENT I SE1SMXC SUPPORT COMPONENTS CONT.
H6.
MAZNSTEAM'RAW1NGS: B-9A Summary Number 700470 Exam Categ aaa SS-CS Item NDE Number Component Component Type Exam aaaaaaa aaaaaaaaaaaaaaaaaaascaa aaaaaaccaaaaaaaaa aaaa
- F1.20R MSU-51 OE VT-3 RIGID SUPPORT
& IA 94 -VT-3: LOOSE HOLD DOWN BOLTS ON ALL 4 CORNERS OF BASE PLATE. SHIM PLATES SHIFTED SOUTH.
EAST & WEST ENDS OF BASE PLATE BENT UP BY JACK BOLTS.
NCR 94-057 GENERATED.
INTERZUM USE-AS-IS UNTIL 5"30-94.
FXNAL DISPOSITION, SERVICE
- INDUCED, USE-AS-ZS.)
700480 SS-CS
- F1.20R MSU-52 RIGID SUPPORT
2 BOLTS ON SOUTH SXDE LOOSE.
1 BOLT IN SW CORNER MISSING JAM NUT.
EAST
&. WEST ENDS OF BASE PLATE BENT UP BY JACK BOLTS.
NCR 94-058 GENERATED.
INTERZUM USE-AS-IS UNTIL 5-30-94.
FINAL DXSPOSITION, SERVICE INDUCED, USE-AS-IS
-ACCEPTABLE.
700490 SS-CS "F1.20R MSU-53 OE RIGZD SUPPORT
& IA EXPANDED 94 -VT-3: SE, SW HOLD DOWN BOLTS ARE LOOSE.
SHIM PLATE BETWEEN I-BEAM & BASE PLATE ARE WORKING OUT OF THE SOUTH SIDE.
BASE PLATE DEFORMED AT E.
&. W.
- ENDS, NCR 94-059 GENERATED.
INTERIUM USE-AS-IS UNTIL 5-30-94.
FINAL DISPOSITION, SERVICE INDUCED, OK.
700500 SS-CS
- F1.20R MSU-54 OE RIGID SUPPORT
& IA EXPANDED 94 -VT-3: NE, SE, SW HOLD DOWN BOLTS IN BASE PLATE ARE LOOSE.
2 SHIM PLATES SHIFTED NORTH.
E
& W ENDS OF BASE PLATE ARE BENT UP.
NCR 94-060 GENERATED.
INTERZUM USE-AS-IS UNTIL 5-30-94.
FINAL DISPOSITION, SERVICE INDUCED, USE-AS-XS,-ACCEPTABLE.
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h er
& El tri r
Ea Av R
h r NY 1464
- 2. Plant R.E inn N
lear P wer Plan 1
Lak R
n ari N
14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A S.Commercial Service Date Q~l
~ 1970 6.National Board Number for Unit
~N A ATTACHMENT I SEISMIC SUPPORT COMPONENTS CONT.
s MAZNSTEAM (CONT.)
Summary Exam Item Number Categ Number Component saaaas a----aa aaaaaa-
=rasa'--saaaassaass3-aiba 700510 SS-CS
- F1.20R MSU-47 RIGID SUPPORT
& IA DRAWINGS: B-9A NDE Component Type Exam IS<<&CSCIC5&SC&&&&& &
CRSR&
OE VT-3 EXPANDED 94 -VT-3: 1)
BASEPLATE BOLTS SOUTH
& WEST LOOSE.
2)
SHIM PLATES ARE LOOSE.
3)
BASE PLATE BENT UP AT EAST & WEST ENDS.
NCR 94-062 GENERATED.
INTERIUM USE-AS-IS GRANTED.
700520 SS-CS
- F1.20R MSU-48 RIGID SUPPORT
& IA OE, EXPANDED VT-3 94 -VT-3: SHIM PLATE (BOTTOM) MOVING NORTH'HIM PLATE (TOP)
MOVINS SOUTH.
BASE PLATE BENT UP AT EAST & WEST ENDS.
REJECT; NCR 94-063 GENERATED.
INTERIUM USE-AS-IS GRANTED UNTIL 5-30-94.
FINAL NCR DISPOSITION - USE-AS-IS, SERVICE INDUCED-ACCEPTABLE.
700530 SS-CS
- F1.20R MSU-49 RIGID SUPPORT
& IA OE EXPANDED 94 -VT-3: BASE PLATE BOLTS (SW., SE.,
NW., NE.)
LOOSE.
BASE PLATE BENT UP AT EAST & WEST ENDS.
NCR 94-064 GENERATED.
INTERZUM USE-AS-ZS GRANTED UNTIL 5-30-94.
FINAL NCR DISPOSITION, USE-AS-IS, SERVICE
- ZNDUCED,
-ACCEPTABLE.
700540 SS-CS
- F1.20R MSU-50 RIGID SUPPORT
& IA OE EXPANDED VT-3 94 -VT-3: ANCHOR BOLTS LOOSE, SHIM PLATES SLIDING SOUTH.
BASE PLATE BENT UP AT EAST & WEST ENDS.
NCR 94-065 GENERATED.
INTERIUM USE-AS-ZS GRANTED UNTIL 5-30-94.
FINAL NCR DISPOSITION, USE-AS-ZS, SERVICE
- INDUCED,
-ACCEPTABLE.
700910 SS-CS
- F1.20R SWU-639 U-BOLT AUG VT-3 94 -VT-3: NO RECORDABLE INDICATIONS - BASELINE PER EWR 5405 ACCEPTABLE.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Rochester Elec ri r
E Av R ch s
r NY 14 4
- 2. Plant R
E irma Nucl ar Power Pl n 1
0 L k R a n ri NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (Zf Req.)
~N A 5.Commercial Service Date g~l 1997, 6.National Board Number for Unit
~N A ATTACHMENT Z Z.
STEAM GENERATOR EDDY CURRENT EXAMINATIONS:
Z1.
STEAM GENERATOR A DRAWINGS:
Summary Exam Number Categ 800000 B-Q Ztem Number Component
$$ RRRC RRRRCRR$ $ $$
C$$ $$ $$ $$ $$ $$ $$ $$ $$ $$
B16.20 OPEN GENERATOR TUBES PREV.
IDENT. DEGRAD.
20 l NDE Component Type Exam M&MM$$ &$$ $$ $$ &&
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
800150 B-Q B16.20 OPEN GENERATOR TUBES ASME 20%'OTATZNG RANDOM SAMPLE 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED ZNDZCATZONS LISTINGS
& 1994 EDDY CURRENT REPORT FOR DETAILS.
800200 SG-ET OPEN GENERATOR TUBES OE 100%'F ALL UNSLEEVED TUBES 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
800350 B-Q B16.20 SLEEVED GENERATOR ASME TUBES 20%'OT.
RAN. SAM.
EACH TYPE SLEEVE 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner R
h r
El tric Cor 8
Ea Av R chester NY 1464
- 2. Plant R.E Ginna Nuclear P
w r Plant 1503 Lake R
On ari NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date g~1~17 6.National Board Number for Unit ~NA ATTACHMENT I STEAM GENERATOR EDDY CURRENT EXAMINATIONS CONT.
STEAM GENERATOR A (CONT.)
DRAWINGS:
Summary Exam Number Categ Ztem Number Component NDE Component Type Exam 800360 WEAR IND.
COLD OE LEG-2ND/3RD SP R1C10-R1C12, R2C10
- R2C12, R3C10-R3C12 94
-EXAMINATIONSCOPE COMPLETED, NO DETECTABLE DEFECTS LOCATED IN INSPECTED TUBES.
ATTACHED ZS A LISTING OF RESULTS.
SEE 1994 EDDY CURRENT REPORT FOR DETAILS.
ET Z2.
STEAM GENERATOR B DRAWINGS:
- Summary Exam Item Number Categ Number sac m
m m
801000 B-Q B16.20 Component
&&W&MMM&CI&&RS&CSMW&
OPEN GENERATOR TUBES PREV.
IDENT. DEGRAD.
20%
NDE Component Type Exam
&55 % SR CS C5 CS &XS CR D ZXK%
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
801150 B-Q B16.20 OPEN GENERATOR TUBES ASME 20%'OTATING RANDOM SAMPLE 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
80)200 SG-ET OPEN GENERATOR TUBES OE 100%'F ALL UNSLEEVED TUBES 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED ZNDZCATIONS LISTINGS & 1994 EDDY CURRENT REPORT FOR DETAILS.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1994) 1.
Owner Ro h r
& El ri r
8 East Ave.
R h
r NY 14 4
- 2. Plant R
E inn N l r P wer Pl n 1
L k R
n i
NY 14 1
- 3. Plant Unit 1
4.
Owner Certificate of Authorization (If Req.)
~N A 5.Commercial Service Date ~Tel~17 6.National Board Number for Unit ~NA ATTACHMENT I STEAM GENERATOR EDDY CURRENT EXAMINATIONS CONT.
STEAM GENERATOR B (CONT.)
DRAWINGS:
- Summary Exam Number Categ Item Number Component NDE Component Type Exam mmmmmm
==
mscmsssamca sssssscsmm=
m=mm mmssmacssa mmmmmzsmm mm=mmmm mzsssm 801350 B-Q B16.20 SLEEVED GENERATOR TUBES ASME ET ET ET ET 20%'OT.
RAN. SAM.
EACH TYPE SLEEVE 94
-EXAMINATIONSCOPE COMPLETED, SEE ATTACHED INDICATIONS LISTINGS 6
1994 EDDY CURRENT REPORT FOR DETAILS.
FORM NISc2 OWNERPS REPORT FOR REPAIRS OR REPLACEMENTS As Required by thc Provisions of the ASMECode Section XI 1.Owner Roche er Gas
& El ri r
8 Ea Ave.
R hester NY 1464 2.
Plant R
E inn Nuclear P
w r Plan Date Sheet 1
Unit une 1994 of 1503 Lake Road n ario NY 14 1
Address Repair Organization P.O. No., Job No., ctc.
- 3. Work Performed by Name Type Code Symbol Stamp Authorization No.
N A N A Address Expiration Date N A 4.
Identification of System
- 5. iai Applicable cenallnclinn cede ~ip~ pdidnn,~
Addenda,~ cade canc (b) Applicable Edition of Section XI Utilized for Repairs or Replaccmcnts 1986
- 6. Identification of Components Repaired or Rcplaccd and Replacement Components
(')
Name of Component Name of Manufacturer Manufacturer Seria No.
National Board No.
Other Identification Year Build Repaired Replaced of Replacement ASME Code Stamped (Yes or No)
- 7. Description of Work
- 8. Tests Conducted:(~)
Hydrostatic 0 Pneumatic 0
Nominal Operating Prcssure 0
Other 0 Prcssure psi Test Temp.
'F NOTE: Supplemental sheets in form of lists, skctchcs, or drawings may be used, provided (1) size is 8-1/2 in. x ll in.,(2) information in items 1 through 6on this rcport is included on each
- sheet, and (3) each sheet is numbcrcd and the number of shccts is rccordcd at thc top of this form.
(i)Sec ATTACHMENT II'12/82)
This Form (E00030) may bc obtained from thc Order Dept., ASME,345 E. 47th St., Ncw York, N. Y. 10017 1
FORM NIS-2 (Back) 9.Remarks Applicable Manufacturer's Data Reports to bc attached CERTIFICATE OF COMPLIANCE ASMECodc, Section XL repair or replacement N/A Type Code Symbol Stainp Certilicate of utho 'ion No.
N/A Expiration Date Si ncd P.A.Kle acki ISI En ineer Date 30 June Owner or Owner's Designee, Title N/A 1994 CERTIFICATE OF INSERVICE INSPECTION I,thc undcrsigncd, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and thc State or Province of New York and cmploycd by IISBIdtICo.
of llaitford CT.
have inspected the components described in this Owner's Rcport during the period bclicl', thc Owner has perforined examinations and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as rciiuired by thc ASMECodc, Section XL By signing this certificate ncithcr the Inspector nor his employer makes any warranty,'xpressed or implied, concerning the examinations and corrective measures described in this Owner's Report.
Furthermore, neither the Inspector nor his employer shall bc liable in any manner for any personal injury or property damage ora loss of any kind arising from or connected with this inspection.
dsc44r A 8 l/~
Inspector's Signature Date
~ +~
19 5 Commissions n/
cP W9 cP'ational Board, State,
- Province, and Endorscments
(~)
See "ATPACHMENT II'")
Repair, Replacement or Modification as identified within ATPACIIMENTII
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPAIR REPLACEMENT and MODIFICATION PROGRAM The Repair, Replacement and Modification (RR&M) Program, as identified within the "Appendix B" Program of the Ginna Station Quality Assurance
- Manual, identifies component jurisdiction and associated requirements.
Applicable
- Repair, Replacement or Modification activities have been performed in accordance with ASME Section XI Code, 1986 edition, no addenda..
When an item under the rules and requirements of the "Appendix B"
Program is found deficient, an Engineering "use-as-is" evaluation may result.
This determination is indicated within the ISI Program
- Summary, "Attachment I", for the applicable component within this report.
If the deficiency results in a Code Repair, Replacement or Modification; the deficiency will be classified as one of three category types.
These category types shall consist of a "Code Service Induced Rejectable Indication",
a "Code Rejectable Indication" and a "Corrective Action Activity".
A "Code Service Induced Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be "Service Induced".
"Service Induced" indications, stemming from Inservice Inspection Examinations (ISI),
shall require additional expanded examinations.
The associated expanded examinations shall be performed in accordance to the requirements of the ASME Section XI Code.
A "Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not "Service Induced".
This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Znspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- l. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 1451
- 3. Applicable Edith.on of Section XZ Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT IZ A "Corrective Action Activity" may occur when a
component under the RR&l Program requires corrective action.
This corrective action may be a result from a maintenance operation that identifies a need to perform a Code Repair, Replacement or Modification.
This category includes but is not limited to items such as machining a
component to correct an identified problem or the removal and 'later reapplication of hardface material on pressure boundary surfaces.
The following groups have performed applicable
- Repair, Replacement and Modification activities during the 1993 Outage.
Each group has been identified by a number and will correspond to the groups'ame and address.
Rochester Gas and Electric, Ginna Station departments will not be identified as like contractors but by generic name.
In the below listing of Repairs, Replacements or Modifications; the work group will be identified by a number within the component discussion.
Rochester Gas E Electric, Ginna Station 2.
Ginna Station Projects Department Nuclear Power Services Philadelphia, Pa.
3.
ITI Movats 2825 Cobb International Blvd.
Kennensaw, Ga.
30144-5512 ABB Combustion Engineering, Inc.,
1000 Prospect Hill Road P.O.
Box 500 Windsor, Connecticut 06095-0500 5.
Babcock
& Wilcox Lynchburg, Virginia
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II The following information will report applicable
- Repairs, Replacements or Modifications performed at R.
E.
Ginna Nuclear Power Plant during this reporting period as required by ASME Section XI Code.
A.
CODE REPAIRS:
ASME Class:
3
~S stem:
Service Water GORR No.:
94-M-001 Construction Code:
ASME Section III, 1986 Edition.
Work Performed B
3 Name of Com onent.
Valve 4605; Valve Stem Repair.
Work Descri tion Remarks A Repair by machining was performed on the valve stem associated with Valve 4605.
This activity was controlled by WO 5
19221490.
Upon completion and reassembly, an ASME Section XI VT-2 leakage examination was performed and acceptable.
2.
ASME Class:
3 ~Sstem:
Service Water GORR No.:
94-M-002 Construction Codex'SME Section III, 1986 Edition.
Work P rform d B
~
3 Name of Com onent
~ MOV-4670; Pipe End Prep Weld Repair.
Work Descri tion Remark
~ A Weld Repair was performed on the pipe end prep downstream of Valve 4670.
This activity was controlled by WO 5 19221497.
Construction Code examinations were performed and acceptable.
The valve was replaced and reinstalled by welding.
See Replacement GORR 5 94-T-056 for details.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990 - 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT 1Z CODE REPAIRS Cont.
3.
ASME Class:
1 ~Sstem:
RCS GORR No.: 94-E-015
/
Construction Code:
ASME Section III, 1986 Edition.
Work Perform d B 5
Name of Com onent:
Steam Generator "A & B" (EMSO1A, EMSO1B)
- Tubes, Explosive Sleeves/Plugs.
Work Des ri tion R mark
- During the Eddy Current Examination of Steam Generator "A & B",
a total of 247 tubes containing defects were identified and determined to be candidates for B&W bimetallic explosive sleeves or plugs.
A total of 143 B&W explosive sleeves and one (1)
B&W explosive plug was installed in the "A" Steam Generator.
A total of 103 B&W explosive sleeves were installed in the "B"
The location of these defective 'tubes are identified within the Eddy Current "1994 Final Examination Report for Steam Generators".
This activity was controlled by Ginna Station Maintenance Procedures M43.16
& M43.43.3, and B&W document 51-1212535-01.
Upon completion of the installation activity, Eddy Current examinations were performed and acceptable on the sleeves No Eddy Current examination was performed on the Plug.
Eddy Current Sleeve Examinations are also utilized to verify proper weld location and provides comparison to ensure weld soundness.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario
.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II CODE REPAIRS Cont.
4, GORR No.: 94-E-016 Line:
N/A Construction Codex'SME Section III, 1986 Edition.
Work Perform d B 4
Name of Com onent:
S B"
(EMS01A, EMS01B)
- Tubes, Welded Plugs.
Work Descri tion Remarks: During the Eddy Current Examination of Steam Generator "A
8 B",
a total of 7 tubes containing defects were identified and determined to be candidates for CE welded plugs.
A total of five (5) welded CE Plugs were installed in the "A" Steam Generator.
A total of two (2) welded CE Plugs were installed in the "B" Steam Generator.
The location of these defective tubes are identified within the Eddy Current "1994 Final Examination Report for Steam Generators".
This activity was controlled by Ginna Station Maintenance Procedure M43.55 and CE Report CEN-320-P.
Upon completion of the installation activity, VT Examinations were performed and acceptable.
5.
M" GORR No.
~ 94-E-005 Construction Code:
ASME Section
- 111, 1986 Edition Work Performed B:
1 Name f Com on nt:
CCU-228 Work Descri tion R mark
- A Repair activity was initiated to replace applicable sections of a poor workmanship Original Construction Code Integral Attachment Weld associated with CCU-228. This activity was controlled by WO 5 19401238 8
NCR 94-029. Construction Code visual examination was acceptable.
ASME Section XI preservice (VT-3) baseline examination was performed and acceptable.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II B.
REPLACEMENTS AND MODIFICATIONS:
AEME Class:
3 ~stem:
Aux. Feedwatet GORR No.l 94-E-001 Construction Co ASME Section II1, 1986 Edition Work Performed B:
1, Name of Com onent:
FE-2009, Orifice Flange Work Descri tion Remarks'n "Approved Equivalent" Replacement activity was initiated on FE-2009 Orifice Flange.
The original 1" diameter, A193 B7 Studs (8) were replaced with 1 1/4" diameter Studs of the same material.
This activity was controlled by WO 5 19300257 6 NCR 93-228.
Studs were obtained under POg N2210902BGD.
Upon reinstallation, a VT-2 Leakage Examination was performed
& acceptable.
- 2. al":
. ~
/
Construction Code:
ASME Section III, 1986 Edition Work Performed B
~
1 Name of Com onent:
- V5706, Tee S Elbow Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 5706, Tee and Elbow due to a
leak found during operation.
This activity was controlled by WO 5 19369423
& NCR 93-250.
Upon completion of this activity, Construction Code examinations were performed and acceptable.
The Code Case Surface Examination for Partial Penetration Welds were also completed and acceptable.
A VT-2 Leakage Examination was performed and acceptable.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd Ontario N.Y 14519
- 3. Applicable Edition of Section XZ Utilized for Repah.rs, Replacements or ModificationsE'1986 No Addenda REPLACEMENTS AND MODIFICATIONS:
Cont.
ASME Class:
1
~S stem:
RCS-Pr-essurizer GORR No.
94-E-006 Construction Code B16.34 6
ASME Section III, 1986 Work P rform d B 3
Name of Com onent:
V-515 Work Descri tion Remarks:
Valve 515 was
- removed, items replaced and valve body end prep repaired before reinstalled by welding.
Items replaced included the
- seats, discs and wedges.
This activity was controlled by WO 5 19369443 and NCR 94-044.
Construction Code examinations were performed and accepted.
ASME Section XI preservice baseline examinations were performed and accepted.
A Hydrostatic Test and accompanying VT-2 examination was performed and acceptable.
ASME Class:
3
~S stem:
Service Water GORR No.: 94-E-007 Construction Code:
ASME Section III, 1986 W rk P rf rme B
~
2 Name of Com onent:
VS-1 Valve Support to MOV-4616 Work D cri ion Remarks:
A Modification activity was initiated to add a valve support (VS-1) to MOV-4616 Yoke. This activity was controlled by EWR 5098 and SM 5098.6.
Construction Code examination (VT) was performed and acceptable.
In accordance with Engineerings'lassification of this item being a
"valve support",
no ASME Section XI preservice baseline examination was applicable.
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
5.
RSt4E Class:
3
~S stem:
Service Water GORR No 94-E-008 Construction Cod
- B31.1 1973
& ASME Section III, 1986 Work Performed B
2 Nam of'om on nt:
Slip on Flange/Blind Flange, "A" Header Reli f R u st g 25 Work Descri tion Remarks:
A Modification activity was initiated to replace the welded elliptical end cap on the "A" Service Water Header with a slip-on/blind flange assembly.
This activity was controlled by EWR 5405 and SM 5405.1.
Construction Code NDE was performed and acceptable.
Relief Request 5 25 was invoked which required a Construction Code PT examination of the root
& final weld. These examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
Construction C d
. B31.1 1973
& ASME,Section,III, 1986 Work Performed B
~
2 Name of Com on nt:
Replaced existing 3/4" connection
& valve with 2" connection
& valve 4612A.
Reli f Re s
I 25 Work D seri tion Remarks:
A Modification activity was initiated to replace the existing 3/4" connection
& valve with a 2" connection
& valve 4612A. This activity was controlled by EWR 5405 and SM 5405.1 per MDCN 5405-01. Construction Code NDE was performed and acceptable.
Relief Request I 25 was invoked which required a Construction Code PT examination of the root final weld.
These examinations were acceptable.
An ASME
,.Section XI VT-2 Leakage Examination was performed and acceptable.
10
R.
E ~
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994) 1 ~ Owner: Rochester Gas 6 Electric Co 8 E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
7.
Construction Code:
ASME Section III, 1986 Work Performed B:
2 Name of Com onent:
Removal of FE-2927
& replacement with bolted blind flange.
Work De cri tion Remarks A
Modification activity was initiated to mechanically remove the annubar
- assembly, associated tubing and support.
These items were then replaced with a 3" bolted blind flange. This activity was controlled by EWR 5405 and SM 5405.1.
Upon conclusion of this activity, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
8.
ASME Class 3 ~Sstem:
Service Water GORR No.: 94-E-012 Corrective Action Activity Constructi n
od
- B31.1 1955 S
ASME Section III, 1986 Work Perform d B
2 Nam f
m nent
~
Studs
& Nuts Replacement associated with 20" Elbow located in the Control Building.
Work Descri tion Remarks A Replacement activity was initiated to replace Studs
& Nuts associated with a 20" Service Water Elbow. This activity was controlled by EWR 5405 and SM 5405.1.
Upon conclusion of this mechanical replacement
- activity, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
11
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co 8 E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
9.
e" -: ",
KN" Lines:
Construction Code:
B31.1 1973
& ASME Section III, 1986 Work Performed B
2'am of Com onent:
Replaced existing 3/4"
& 1" drain lines with new 2" connections
& valves (4342,
- 4343, 4358A, 9716A
& 9716B)
Relief Re est: I 25 Work Descri tion Remarks:
A Modification activity was initiated to replace the existing 3/4"
& 1" connections valves with 2"
connections
& valves.
This activity was controlled by EWR 4658C and SM's 4658C.1/.2/.3/.4
.5.
Construction Code NDE was performed and acceptable.
Relief Request I 25 was invoked which required a Construction Code PT examinations of the root
& final weld. These examinations were acceptable.
ASME Section XI VT-2 Leakage Examinations were performed and acceptable.
10.
ASMS Class:
3 ~Sstem SAFW GORR No.: 94-E-014 Construction C de:
ASME Section III, 1974
& 1986 Work Performed B:
2 Name of Com onent:
Temporarily removed and rewelded SWU-594 Support for activity described within GORR I 94-E-013.
W rk D
ri i n R m rk Support SWU-594 was temporarily removed and rewelded back to the original configuration to permit installation of new drain connections associated with modification activities described in GORR I 94-E-013.
Upon reinstallation, Construction Code NDE was performed and acceptable.
- Also, a
Section XI preservice (baseline) examination was performed and accepted.
12
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
- 1. Owners Rochester Gas 6 Electric Co 8 E. Ave.
Rochester N.Y. 1464
- 2. Plants R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT II REPLACEMENTS AND MODIPICATIONSs Cont.
2)6H-SWO-125-1 3)18A-SWO-125-1 4)14H-SWO-125-1 Construction Code:
ASME Section III, 1986 Work Performed B
2 Name of Com onent:
- 1) Valve 4614 Replacement
(**)
- 2) Valve 4733 Replacement
(**)-
- 3) Valve 4735 Replacement
(**)
- 4) Support SWU-195 Modification Relief Re est:
g25 (**)
W rk De ri tion R marks' Modification activity was initiated to replace Valves 4614,
- 4733, 4735 and modify piping support SWU-195. This activity was controlled by EWR 5098 and SM's 5098.3/.4/
E.6. Construction Code NDE was performed and acceptable.
Relief Request 5 25 was invoked on the valve work which required that all piping 10" and larger be 100%
Radiographed.
All piping c
10" would require surface examinations of the root E final weld. These examinations were acceptable.
ASME Section XI VT-2 Leakage Examinations were performed and acceptable for the valves.
ASME Section XI VT-3 preservice (baseline) examination was performed and acceptable for SWU-195 support.
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
12.
~S stem:
CCW GORR No.: 94-E-018 10A-ACS-152 8B-AC5-152 10B-ACS-152 Construction ode B31.1 1955, B16.34, ASME Section III, 1986 Work Performed B
2 Name of Com on n Replaced Valves 723A
& 723B, components and modified Component Supports CCU-86 5
CCU-89.
Relief R
est. I 26 Work Descri tion Remarks:
A Modification activity was initiated to replace Valves 723A
- 723B, associated components, and modifications to Supports CCU-86 6 CCU-89.
This activity was controlled by EWR 5284 and SM 5284.1.
Construction Code NDE was performed and acceptable.
Relief Request g 26 was invoked which required a Construction Code PT examinations of the root 6 final weld for piping <10" NPS.
RT examinations would be required for NPS 10" and larger.
These examinations were performed and acceptable.
ASME Section XI VT-2 Leakage Examinations were performed and acceptable.
- Also, preservice (baseline) examinations were performed and acceptable for CCU-86 6 -89.
R.
E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owners Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant:
R.E Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
14B-SWO-125-1 Construction Code: B31.1 1955, B156.34, ASME Section III, 1986 Work Performed B
2 Name of Com onent:
Replaced Valves 4601
& 4602 and applicable components.
Relief Re est:
g 25 Work Descri tion Remarks:
A Modification activity was initiated to replace Valves 4601 4602 and applicable components.
This activity was controlled by EWR 5284B and SM 5284B.1. Construction Code NDE was performed and acceptable.
Relief Request I 25 was invoked which required a Construction Code RT for NPS 10" and larger.
These examinations were performed and acceptable.
ASME Section XI VT-2 Leakage Examinations were performed and acceptable.
14.
ASME Cla s:
2 ~Sstem RHR GORR No.. 94-T-001 Constru ion Code:
ASME Section III, 1974
& 1986 Work Performed B:
1 Name of Com on nt:
RHU-92 Snubber Support, Pin Replacement.
W rk D seri tion R marks
~
A "Like-for-Like" Replacement activity was initiated to replace a pin in RHU-92 Snubber Support.
This activity was controlled by WO I 19320641.
Upon installation of the new pin, a
VT-3 preservice (baseline) examination was performed and acceptable.
15
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas k Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
8" Line: N/A Construction Code: Gilbert Spec; R0-2167, B31.1 1955
& ASME Section III 1986.
Work Performe B
1 Name of Com onent:
Expansion Joint SSW04
& Bolting
'eplacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace an expansion Joint (SSW04) and bolting.
This activity was controlled by WO 5 19340701.
Upon reinstallation, an ASME Section XI VT-2 examination was performed and acceptable.
Line: N/A Construction Code: Gilbert Spec; R0-2204, SP 5291,
& ASME Section III, 1986.
Work Performe B
1 Name of Com on nt:
SW Pump "C" (PSW01C) Rebuilt Replacement.
Work Descri tion Remarks:
This Rebuilt activity consisted of a Pump Assembly, bolts
& nuts. This activity was controlled by WO g's 19340658 19320752.,
Upon reinstallation, a
VT examination of the underwater support was performed as well as a flow test as documented within PT-2.7.1 Line N/A onetruction Code:
ASME Section
- 111, 1974 Work P rf rmed B:
1 Name of Com n nt:
EAC14; Nuts
& Studs Replacement on SFP Hx MAII Work De ri i n Remark A "Like-for-Like" Nuts Studs Replacement was performed on the SFP Hx "A" (EAC14)
. This activity was controlled by WO 5
19320678 Maintenance Procedure M-110. Upon installation of the new studs
& nuts, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
16
R. E.
GZNNA NUCLEAR POWER PLANT Xnservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co 8
E Ave Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
18.
~S st m: Spent Fuel Pool GORR No.: 94-T-006 Line: N/A Construction Code.
ASME Section III, 77/W78
& 83/W85 Work Performed B
1 Name of Com onent:
EAC13; Nuts
& Studs Replacement on SFP Hx IfB II Work Des ri tion R marks:
A "Like-for-Like" Nuts Studs Replacement was performed on the SFP Hx "B" (EAC13). This activity was controlled by WO 5 19320677 and 19321405.
Upon installation of the new studs
& nuts, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
Line: N/A Con tructi n Code ASME Section III, 77/W78 Work Performed B
1 Name of Com onent:
PAC07B; Nuts
& Studs Replacement on "B" SFP Pump Suction Flange.
Work D ri tion R
m rks:
A "Like-for-Like" Nuts
& Studs Replacement was performed on the "B" SFP Pump (PAC07B) Suction Flange.
This activity was controlled by WO 5
19300469 Maintenance Procedure M-37.134.
Upon installation of the new studs
& nuts, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
20.
ASME Class 2 ~Sst m
CS GORR No.: 94-T-008 C nstruc ion Code:
B31.1 1986
& SP-5291 Work Performed B
1 N m f
m onent.
FT-930:
Studs
& Nuts Replacement.
Work Descri tion Remarksl A Replacement activity was initiated on Studs
& Nuts associated with FT 930.
This activity was controlled by WO 5
19301464.
Upon installation of the new studs
& nuts, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
17
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant:
R.E Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 1451
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
GORR No.: 94-T-009 Corrective Action Activity 21.
ASME Class 2 ~Ssteml RHR Construction Code:
B31.1, 1986 Work Performed B
1 Name f Com on nt:
Valve 626; Shaft
& Flange Studs/Nuts Replacement.
Work D ri tion Remarks:
The Flange Studs
& Nuts,
& the Shaft associated with Valve 626 were replaced.
This activity was controlled by WO 5
19221430.
Upon installation of the new
- items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
22, ASME Class:
3 ~Ssteml Service Water GORR No.: 94-T-010 Construction Cod
- B31 F 1 ('55),
B16.34, ASME Section III
('86).
Work Performed B:
3 Name of Com nent:
Valve 4622; Stem
& Disc Assembly Replacement.
Work Descri tion Remark
- Corrective action was initiated to replace the stem
& disc assembly associated with Valve 4622.
This activity was controlled by WO 5
19320990.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
23.
~S st m: Service Water GORR No.: 94-T-011 Con tru i n B31.1 ('55), B16.5 ('61),
('86).
W rk P rf rm d B 3
Name f
m n n
~
Valve 4666; Flange Valve Replacement.
Work De cri ti n Remark
- Corrective action was initiated to replace the flange Valve 4666. This activity was controlled by WO g 19221524.
Upon installation of the new valve, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
18
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co 8 E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd Ontario N.Y 14519
- 3. Applicable Edition of Section XX Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT Ii REPLACEME TS AND MODIFICATIONS:
Cont.
25.
Construction Code B31.1 ('55), B16.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent:
Valve 4621; Replacement.
Relief Re e t g 25 Work Descri tion Remarks Corrective action was initiated to replace Valve 4621.
This activity was controlled by WO 19221482.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
- Also, as required by Relief Request
The results of the examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
ASME Class:
3 ~Sstem:I Service Water GORR No.: 94-T-013 Construction Code: B31.1 ('55), B16.34, ASME Section III1986.
Work Performed B
3 Name of Com onent Valve 4605; Wedge Replacement.
Work D cri tion Remarks Corrective action was initiated to replace the wedge in Valve 4605. This activity was controlled by WO 5 19221490.
Upon installation of the new item, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
26.
Con truction Code: B31.1 ('55), B16.34, ASME Section III 1986.
Work P rformed B
3 Name of Com onent:
Valve 4606; Wedge'eplacement.
Work Descri tion R marks'orrective action was initiated to replace the wedge in Valve 4606. This activity was controlled by WO g 19221488.
Upon installation of the new item, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
19
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas 6 Electric Co 89E. Ave.
Rochester N.Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 1451
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
27.
ASME Class:
3
~S teml Service Water GORR No.: 94-T-015 samaK='onstruction Code: B31.1 ('55), B16.34, ASME Section III 1986.
Work Perfo ed B
3 Name of Com on nt Valve 4623; Wedge Replacement.
Work Descri tion R marks: Corrective action was initiated to replace the'wedge in Valve 4623. This activity was controlled by WO g 19221484.
Upon installation of. the new item, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
28.
ASME Class:
3 ~Stem:
Service Water GORR No.: 94-T-016 Construction Code:
B31,1 ('55),
ASME Section III ('86).
Work Performed B:
3 N me of Com on nt Valve 4666; Flange Bolting Replacement.
Work Descri tion Remarks'orrective action was initiated to replace the flange bolting associated with Valve 4666.
This activity was controlled by WO 5 19221524.
Upon installation of the new item, an ASME Section XI VT-2 Leakage Examination was performed and acceptable'9.
ASME Class:
3 ~Ssteml Service Water GORR No.: 94-T-017 samlz='onstruction od
. B31.1 ('55), B16.34, ASME Section III 1986.
Work Perform B
~
3 N m of m on n Valve 4605; Body to Bonnet Bolting Replacement.
Work Descri ti n R
m rk
~ Corrective action was initiated to replace the body to bonnet bolting associated with Valve 4605.
This activity was controlled by WO 5
19221490.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
20
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
30.
ASME Class:
3
~S stem:
Service Water GORR No.: 94-T-018 Construction Code: B31.1 ('55), B16.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent:
Valve 4606; Body to Bonnet Bolting Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace the Body to Bonnet bolting associated with Valve 4606.
This activity was controlled by WO 5
19221488.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
31.
ASME Class:
3 ~Sstem:
Service Water GORR No.: 94-T-019 Construction Code: B31.1 ('55), B16.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent:
Valve 4623; Body to Bonnet Bolting Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace the Body to Bonnet bolting associated with Valve 4623.
This activity was controlled by WO 5
19221484.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
32.
ASME Class:
3
~S stem:
Service Water GORR No.: 94-T-020 svamL:
Construction Code: B31.1 ('55), B16.34, ASME Section III1986.
W rk Performed B:
3 Name of Com onent:
Valve 4639; Body to Bonnet Bolting 6 Stem Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace the Body to Bonnet bolting and Stem associated with Valve 4639.
This activity was controlled by WO 5 19221720.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
21
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co 8 E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N Y 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
33.
Construction Code: B31.1 ('55), B16.34, ASME Section III1986.
Work Performed B
3 Name of Com onent:
Valve 4665; Body to Bonnet Bolting Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace the Body to Bonnet bolting associated with Valve 4665.
This activity was controlled by WO 5
19221495.
Upon installation of the new items, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
34.
~Lin N/A Construction Code Gilbert Spec; RO-2167, B31.1 1955
& ASME Section III 1986.
Work Performed B
1 Name of Com onent:
Expansion Joint SSW02, Bolting &
Control Rods Replacement.
Work D cri tion R m rks
~ A Replacement activity was initiated to replace an Expansion Joint (SSW02), Bolting & Control Rods on the Service Water "A"'Pump. This activity was controlled by WO I 19340699.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
35.
Nam of m
n n Line N/A Constrn tion C d Gilbert Spec; R0-2167, B31.1 1955 e ASMR Section III 1986.
1 Expansion Joint SSW03, Bolting Control Rods Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace anExpansion Joint (SSW03), Bolting & Control Rods on the Service Water "B" Pump. This activity was controlled by WO I 19340700.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
22
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas Ec Electric Co 8 E. Ave Rochester N.Y 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y 14519
- 3. Applicable Edition of Section XZ Utilised for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
/
/
(
/
C nstruction ode:
B31.1 1955.
Work Performed B
1 Name of om on nt Valve 5989; Bolted Replacement.
Work Descri tion Remarks:
A "Like-for-Like" Replacement activity was initiated to replace the bolted Valve 5989. This activity was controlled by WO 5 19340484.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
3/.
ASME Cia 3 ~stem Service Water GORR No.: 94-T-025 Construction Code B16.34, ASME Section III ('86).
Work Performed B
~
3 Name of Com onent:
Valve 4671; Replacement.
Relief R
est.
g 25 Work D seri tion R marks: Corrective action was initiated to replace Valve 4671.
This activity was controlled by WO I 19320989
& TE 93-548.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
- Also, as required by Relief Request
- N25, a
surface (PT) examination was performed on the root and final weld.
The results of the examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
23
R.
E.
G1NNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co 89E. Ave.
Rochester N.Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
38.
ASME Class:
2 ~Sst m
CCW GORR No.: 94-T-026 Construction Code:
B16.34, ASME Section III ('86).
Work Perform d B 3
Name of Com onent:
Valve 750A; Replacement.
Code Case:
N-416 Work D ri ti n R
m rks: Corrective action was initiated to replace Valve 750A.
This activity was controlled by WO 19321015
& TE 93-577.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
Also; as required by Code Case N-416, volumetric examination results were evaluated to ASME Section XI criteria.
The results were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
ASME Class:
3
~S st m:
CCW onstruction d
. B16.34, ASME Section III 1986.
Work Performed B
~
3 Name of om onent:
Valve 738A; Stem, Disc S Body/Bonnet Bolting Replacement.
Work Descri ti n R marks' Replacement activity was initiated to replace the Stem, Disc
& Body to Bonnet bolting associated with valve 738A.
This activity was controlled by WO 19221444.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
40 ASME Class:
3 ~Sstem:
CCW El" Construction Code.
B16.34, ASME Section III 1986.
W rk P rf rm d B
~
3 N me of om n nt:
Valve 738B;
- Stem, Disc
& Body/Bonnet Bolting Replacement.
Work Des ri tion Remarks A Replacement activity was initiated to replace the Stem, Disc S Body to Bonnet bolting associated with valve 738B.
This activity was controlled by WO 19221442.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
24
W
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Pexiod, Second Outage (1994) 1.
Owners Rochestez'as
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nucleaz Power Plant 1503 Lake Rd.
Ontario N Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repaixs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
43.
ASME Class:
3 SvVs em CCW GORR No.: 94-T-029 Construction Code:
B16.34, ASME Section III ('86)
Work Performed B
3 Name of Com onent:
Valve 817; Replacement.
Relief Re est:
g 26 Work Descri tion Remarks:
Corrective action was initiated to replace Valve 817.
This activity was controlled by WO I 19321390
& TE 93-527.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
- Also, as required by Relief Request
- N26, a
surface (PT) examination was performed on the root and final weld.
The results of the examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
42.
ASME Class:
2 ~Stem RHR 0 "" "
10E-AC-601 Construction Code:
B31.1, 1955/1986.
Work P rform d B
3 Name of Com onent:
Valve 850A; Stem S Disc Replacement.
Valve 850B; Disc Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace the Stem 8 Disc of Valve 850A and the Dies for Valve 850B. These activities were controlled by WO 5 19201737 and 19300369.
Upon reinstallation, ASME Section XI VT-2 Leakage Examinations was performed and acceptable.
25
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
43.
44.
ASME Class:
3
~S stem:
CCW GORR No.
94-T-031 Construction Code:
B31.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent:
Valve 816; Body to Bonnet Bolting 8
~
Clapper Hinge Studs Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace Body to Bonnet bolting 6
Clapper Hinge Studs associated with valve 816. These activities were controlled by WO g 19221440.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
ASME Class:
3
~S stem:
Service Water GORR Nc.: 94-T-032 Construction Code:
B16.34, ASME Section III ('86).
W rk Performed B
1 Name of m on nt:
Valve 4612; Replacement.
Relief Re est g 25 Work De ri tion Remarks:
Corrective action was initiated to replace Valve 4612.
This activity was controlled by WO 19321102 6
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
- Also, as required by Relief Request
- 525, a
surface (PT) examination was performed on the root and final weld.
The results of the examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
- 45. s GORR No 94-T-033 Con ruc ion C de:
B16.34, ASME Section III 1986.
Work Perf rmed B
3 Nam of Com onent Valve 392A; Cage/Plug Assembly Replacement Work De ri tion R marks: A Replacement activity was initiated to replace the Cage/Plug Assembly associated with Valve 392A.
This activity was controlled by WO 5
19221464.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
26
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. APPlicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1 86 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
46 ASME Classy 3
~S c~m: Service Water GORR No
- 94-T-034 Construction Code:
B16. 34, ASME Section 111 ('6)
Work Performed B
3 Name of Com onent:
Valve 4672; Replacement.
Relief Re est: ¹ 25 Work Descri tion R mark: Corrective action was initiated to replace Valve 4672.
This activity was controlled by WO ¹ 19320988
- 5. TE 93-548.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
- Also, as required by Relief Request
¹25, a
surface (PT) examination was performed on the root and final weld.
The results of the examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
47
/
Line: N/A Construction Codex'16.5, B31.1 1955.
Work Performed B
1 Name of Com onent:
Valve 5990; Replacement.
Work D seri tion Remarks:
Corrective action was initiated to replace Valve 5990.
This activity was controlled by WO ¹ 19340485.
Upon installation of the new valve, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
48 Con ruction Code:
B31.1 1986, ASME Section III 1986.
Work P rformed B
3 Nam of Com onent:
Valve 625; Flange Bolting Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace the flange bolting associated with Valve 625.
This activity was controlled by WO ¹ 19122266 and TSR 91-140.
Upon installation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
27
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas 6 Electric Co 89E. Ave.
Rochester N.Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZI REPLACEMENTS AND MODIFICATIONS:
Cont.
49.
m" Construction Code:
B16.34, ASME Section III ('86).
Work Performed B
3 Name of Com nent:
Valve 4616; Replacement.
Relief Re st:
g 25 Work Descri tion Remark
~ Corrective action was initiated to replace Valve 4616.
This activity was controlled by WO
- 19221505, TSR 94-528 and Short Form EWR 10238.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable. Also,'s required by Relief Request
- g25, a volumetric (RT) examination was performed and acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
50
~
msaltK
~
Corrective Action Activity Construction Code:
B16.34, ASME Section III 1986.
Work Performe B
3 Name of Com onent
~
Valve 4617; Body to Bonnet Bolting Replacement.
Work Des ri i n Remarks A Replacement activity was initiated to replace the Body to Bonnet Bolting associated with Valve 4617.
This activity was controlled by WO 5
19221479.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
51.
~S stem:
Service Water GORR Nc.: 94-T-039 Constructi n Code:
B16.34, ASME Section III 1986.
W rk Perform B
3 Nam of om nent
~
Valve 4610; Body to Bonnet Bolting Replacement.
Work Descri tion Remark
~ A Replacement activity was initiated to replace the Body to Bonnet Bolting associated with Valve 4610.
This activity was controlled by WO 5
19221480.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
28
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1 86 o Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
52.
ASME Class:
3
~S stem:
CCW GORR No.: 94-T-040 Construction Code:
B16.34, ASME Section III 1986.
Work Performed B:
3 Name of Com onent:
Valve 816; Body to Bonnet Bolting Replacement Work Descri tion Remarks:
A Replacement activity was initiated to replace the Body to Bonnet Bolting associated with Valve 816.
This activity was controlled by WO 5
19221440.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed'nd acceptable.
53.
I Construction Code B16.34, ASME Section III 1986.
Work Performed B:
3 Name of om onent:
Valve 4561; Flange Bolting Replacement.
W rk D cri i n R
m rk
~ A Replacement activity was initiated to replace the Flange Bolting associated with valve 4561. This activity was controlled by WO I 19321095.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
54.
ASME Class:
2 ~Ssteml CCW n
i n B16.34, ASME Section III 1986.
W rk P rforme B
~
3 Name of C
m on nt Valve 759B; Stem Replacement.
W rk D seri tion Remarks' Replacement activity was initiated to replace the Stem of Valve 759B.
This activity was controlled by WO I 19321388.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
29
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas E Electric Co
. 89E. Ave Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
55.
ASME Class:
2
~S stem:
CVCS-Letdown GORR No.: 94-T-043 Construction Code:
B16.34, B31.1 1955.
Work Performed B
1 Name of om onent:
Valve 203; Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace Valve 203.
This activity was controlled by WO ¹ 19440312.
Upon installation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
56.
ASME Class:
2
~S stem:
CVCS-Letdown GORR No.
94-T-044 Line: 2" Construction Code:
B16.34, B31.1 1955
'ork Performed B
1 Name of Com onent:
Valve 209; Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace Valve 209.
This activity was controlled by WO ¹ 19440313.
Upon installation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
57.
ASME Class:
2
~S stem:
CCW GORR No.: 94-T-045 Construction Code:
B16.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent:
Valve 749A; Stem
& Body to Bonnet Bolting Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace the Stem and Body to Bonnet Bolting associated with Valve 749A. This activity was controlled by WO ¹ 19321379.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
30
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- l. Ownez". Rochester Gas 6 Electric Co
. 89E. Ave.
Rochester N.Y. 14649 2.. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
58 ASME Class:
1
~S stem:
RCS-Pressurizer GORR No 94-T-046 Construction Code:
B16.34, B31.1 1955.
Work Performed B
1 Name of Com onent:
Valve 434; Replacement.
Work Descri tion Remarks:
A "Like for Like" Replacement activity was initiated to replace Valve 434. This activity was controlled by WO I 19440319 and NCR 94-011.
Upon installation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
59 Construction Cod
. B16.34, B31.1 1955.
Work Performed B
1 Name of Com onent:
Valve 435; Replacement.
Work Descri tion Remarks:
A "Like for Like" Replacement activity was initiated to replace Valve 435. This activity was controlled by WO I 19440320 and NCR 94-011.
Upon installation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
60 ASME Class:
3
~S stem:
TDAFW-P Lube Oil GORR No.
94-T-049 Line.
3" Constru tion Code:
B31.1 1986.
W rk Performed B
1 Name of Com onent:
2" 5: 3" Piping Component Replacements.
Work Descri tion Remarks Corrective action was initiated to replace piping associated with the TDAFW Pump Lube Oil System.
This activity was controlled by WO I 19401304
& TE 94-036.
Upon installation of the new items by welding, Construction Code NDE was performed and acceptable.
A Shop Hydro of the assembly was performed and acceptable.
Also; upon reinstallation of the flange ends, a VT-2 Leakage Examination was performed and acceptable.
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas a Electric Co 89E Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS:
Cont.
61.
ASME Class:
2
~S stem:
S/G Blowdown GORR No.: 94-T-050 Construction Code:
B16.34, B31.1 ('86),
ASME Section IZI
('86)
Work Performed B
1 Name of Com onent:
Valve 5706; Replacement.
Work Descri tion Remarks:
Corrective action was initiated to replace Valve 5706.
This activity was controlled by WO 19401317.
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
Also; as required by Code Case N-416, the surface examination results were evaluated to ASME Section XI criteria.
The results were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
62.
ASME Class:
3 ~Sstem:
MS/Aux.
FW GORR No.: 94-T-051 Construction Code:
ASME Section III,.1977.
Work P rform d B
~
3 Name of Com nent
~
Valve 3505B; Disc, Hinge Arm 8 Pin Replacement.
Work Descri tion Remarks:
A "Like for Like" Replacement activity was initiated to replace the Disc, Hinge Arm 6 Pin associated with Valve 3505B. This activity was controlled by WO g
19301047.
Upon installation, a Construction Code PT examination was performed on the disc after hardfacing and the results were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
32
R. E.
GZNNA NUCLEAR POWER PLANT Znsezvice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 14649
- 2. Plant: R.E. Ginna Nucleax Powex Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modificath.ons:
1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
63, ASME Class:
2
~S stem:
S/G Blowdown GORR No.: 94-T-062 Construction Code.
ASME Section III 1986.
Work Performed B
1
& 3 Name of Com onent:
Valve 5738; Stem
& Inner Plug Replacement.
Work Descri ti n Remarks:
A Replacement activity was initiated to replace the Stem and Inner Plug associated with Valve 5738.
This activity was controlled by WO I 19401389.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
/
Cons ruction Code:
ASME Section III 1986.
W rk Performed B
1
& 3 Nam f Com onen Valve 5737;
- Stem, Inner Plug
& Seal Ring Replacement.
Work Descri tion Remarks:
A Replacement activity was initiated to replace the
- Stem, Inner Plug
& Seal Ring associated with Valve 5737.
This activity was controlled by WO 5 19401389.
Upon reinstallation, an ASME Section
. XI VT-2 leakage Examination was performed and acceptable.
65.
ASME Class:
2 ~Sc~tm:
CCW GORR No
. 94-T-055 on truction Codex'16.34, ASME Section III 1986.
Work Performed B
3 Name of Com onent
~
Valve 814; Stem Replacement.
Work Descri tion R marks' Replacement activity was initiated to replace the Stem associated with Valve 814. This activity was controlled by WO I 19221204.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
33
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co 89E. Ave.
Rochester N Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N Y. 14519
- 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS:
Cont.
66.
ASME Class:
3 ~Ss em Service Water GORR No.: 94-T-056 Con truction Code:
B31.1 ('55),
B16.34, ASME Section III
('86).
Work Performed B
3 Name of Com onent:
Valve 4670; Replacement.
Relief Re est:
g 25 Work Descri tion R m rks Corrective action was init-'ated to replace Valve 4670.
This activity was controlled by WO
Upon installation of the new valve by welding, Construction Code NDE was performed and acceptable.
Also, as required by Relief Request
- 525, a surface (PT) examination was performed on the root and final weld. The examinations were acceptable.
An ASME Section XI VT-2 Leakage Examination was performed and acceptable.
67.
ASME Class:
2 ~Stem.
Main Steam GORR No.
94-T-057 on ruction Code.
ASME Section III 1974 6 1986.
Work Performed B
1 Name of om on nt MSU-2: Snubber Support Replacement.
Work Descri tion Rem rk
~
A "Like for Like" Replacement activity was initiated to replace Snubber Support MSU-2. This activity was controlled by WO 5 19401004 and NCR 94-018.
Upon reinstallation, a VT-3 Baseline examination was performed and acceptable.
34
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Znterval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N.Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT 1Z REPLACEMENTS AND MODIFICATIONS:
Cont.
68.
ASME Class:
2
~S stem:
Steam Generator GORR No.: 94-T-068 Line: N/A Construction Code:
ASME Section III 1965.
Work Performed B
1 Name of Com on nt:
"B" S/G, ¹4 R ¹6 Wedge Port Cover Studs 5
Nuts Replacement.
Work Descri tion Remarks:
A "Like for Like" Replacement activity was initiated to replace Studs and Nuts associated with S/G "B", ¹4 and ¹6 Wedge Port Covers.
This activity was controlled by Procedures GMS-43-20 and GMS-43-21. Construction Code and augmented NDE were performed on the nuts and studs and acceptable.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
69.
ASME Class:
1
~S stem:
RCS GORR No.: 94-T-059 Line: N/A Construction Code:
ASME Section III 1965.
Work Performed B
1 Name of Com on nt.
Pressurizer Manway ¹10 6 ¹16, Bolting Replacement Work D seri tion Remark
~
A "Like for Like" Replacement activity was initiated to replace Bolting associated with the Pressurizer Manway ¹10
& ¹16. This activity was controlled by M-47.1 Procedure.
Construction Code and augmented NDE were performed on the bolting and acceptable.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
35
R. E.
GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990
- 1999 Interval, Second Period, Second Outage (1994)
- 1. Owner: Rochester Gas
& Electric Co
. 89E. Ave.
Rochester N Y. 1464
- 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.
Ontario N.Y. 14519
- 3. Applicable Edi.tion of Section XZ Utilized for RePairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT IX REPLACEMENTS AND MODIRICATIONS:
Cont.
70.
ASME Class:
1 ~Sstem CVCS-Letdown GORR No.: 94-T-060 Line: 2" Construction Code:
Westingtouse Spec.;
- 676270, ASME Section III 1986.
Work Performed B
1 Name of Com onent:
Valve 427; Body to Bonnet Studs 6 Nuts Replacement.
Work Descri tion R marks: A Replacement activity was initiated to replace Body to Bonnet Studs
&, Nuts associated with Valve 427.
This activity was controlled by WO I 19401577.
Upon reinstallation, an ASME Section XI VT-2 Leakage Examination was performed and acceptable.
71.
ASME Class:
1
~S stem 6/G "A" GORR No.: 94-T-061 Line: N/A Constructi n Cod
~ Spec; SP-5378, ASME Section III 1986.
Work Perf rm d B 1
Name of C
m nent:
SGA-7: Snubber Support Replacement.
Work Des ri tion R m rks-A Replacement activity was initiated to replace Snubber Support SGA-7. This activity was controlled by WO 5 19400481 and NCR 94-061.
Upon reinstallation, a VT-3 Baseline (Preservice)
Examination was performed and acceptable.
36
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Second Outage (1994)
ATTACHMENT ZZZ EROSION/CORROSION (MINWALL) PROGRAM SU?QGLRY This section provides Erosion/Corrosion examination details and information corresponding to items inspected during the 1994 Outage.
A total of 115 items were examined.
The breakdown of this total is as follows:
Com onent e
Total Number Pipes Elbows Reducers Tees Heater Shells Total 55 24 12 18 6
115 The following lists identifies systems of examined components, system component result summaries, and component result details.
stems of Examined Com onents:
Component thickness measurements were performed on the following systems.
DWG.
NO.
M-2 M-5 M-6 M-7B M-21 M-22 M-45 M-46B M-75 M-81 SYSTEMS 5 A/B F.W.
HEATERS TO F.WE HEADER HEATERS 4A/B TO FEEDWATER SUCTION FEEDWATER SUCTION TO PUMPS A/B CONDENSATE PUMP
& HEATER DRAIN TANK DISCHARGE TO FEEDWATER SUCTION STEAM EXTRACTION TO PRESEP.
TANK B
& 4B LP.
HEATER STEAM EXTRACTION TO PRESEP.
TANK A & 4A LP.
HEATER PRESEPARATOR A/B TO HEATER DRAIN TANK AND CONDENSER PRESEPARATOR A/B TO HEATER DRAIN TANK STEAM EXTRACTION TO 5A & SB HEATERS FEEDWATER DISCHARGE (TURBINE BLDG)
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Second Outage (1994)
ATTACHMENT ZZZ S stems of Examined Com onents:
Cont.
DWG.
NO.
M-82 M-83 M-84 M-89A M-89B M-92 M-105 4'S-57 SYSTEMS FEEDWATER DISCHARGE (INTERMEDIATE BLDG)
FEEDWATER DISCHARGE (INTERMEDIATE BLDG AND FACADE)
FEEDWATER TO S/G 1A S.G.
1A BLOWDOWN LINE (INSIDE CONT.)
S.G.
1B BLOWDOWN LINE (INSIDE CONT.)
MAIN FEEDWATER PUMP RECIRC HEATING STEAM
&. 625 4A and 4B LOW PRESSURE HEATER SHELL (Note: * = Not a Controlled Drawing.)
S stem Com onent Result Summaries:
The following break down by system provides general results on the component types that were examined.
DWG.
NO.
M-2 M-5 SYSTEM 5 A/B P.W.
HEATERS TO P.W.
HEADER Components Examined:
Results:
0 of Nominal 1
Tee 1
)88o HEATERS 4A/B TO PEEDWATER SUCTION Components Examined:
Results:
% of Nominal 1
Elbow 5
)88o 3
Pipes 2
88 82o 3
Tees
R.
E ~
GINNA NUCLEAR POWER PLANT Inservfce Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHME III S stem Com onent Result Summaries:
Cont.
DWG.
NO.
SYSTEM M-6 M-7B REEDWATER SUCTION TO PUMPS A/B Components Examined:
Results:
0 of Nominal 1
Tee 2
>88%
1 Pipe Results:
0 of Nominal 5
>88%'
88 820 CONDENSATE PUMP
& HEATER DRAIN TANK DISCHARGE TO PEEDWATER SUCTION Components Examined:
4 Pipes 2
Tees M-21 M-22 STEAM EXTRACTION TO PRESEP.
TANK B
& 4B LP.
HEATER Components Examined:
Results:; of Nominal 1
Elbow 5
>88o 3
Pipes 1
Tee STEAM EXTRACTION TO PRESEP.
TANK A & 4A LP.
HEATER Components Examined:
Results:
-. of Nominal 2
Elbows 6
>88%'
Pipes 1
Tee M-45 PRESEPARATOR A/B TO HEATER DRAIN TANK AND CONDENSER Components Examined:
Results:
% of Nominal 1
Pipe 1
>88%
1 Reducer 1
76-70%
M-46B PRESEPARATOR A/B TO HEATER DRAIN TANK Components Examined:
Results:
0 of Nominal 1
Pipe 1
70-65o 1
Tee 1
<65~o M-75 STEAM EXTRACTION TO 5A & 5B HEATERS Components Examined:
Results:
0 of Nominal 1
Elbow 6
>88%'
Pipes 2
88 820 1
Reducer 1
82 76o 2
Tees 2
<65%'
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT III S stem Com onent Result Summaries:
Cont.
DWG.
NO.
M-81 SYSTEM PEEDWATER DISCHARGE (TURBINE BLDG)
Components Examined:
Results:
% of Nominal 2
Reducers 1
88-82%
1 (65%'-82 PEEDWATER DISCHARGE (INTERMEDIATE Components Examined:
Results:
2 Elbows 3
> 8 8+o 1
Pipe BLDG) of Nominal M-83 PEEDWATER DISCHARGE (INTERMEDIATE BLDG AND FACADE)
Components Examined:
Results:
0 of Nominal 1
Pipe 1
>88%'-84 FEEDWATER TO S/G 1A Components Examined:
2 Elbows 1
Pipe 1
Reducer Results:
0 of Nominal 3
> 8 8~o 1
76-70~o M-89A S.G.
1A BLOWDOWH LINE (INSIDE COHT.)
Components Examined:
Results:
0 of Nominal 2
Elbows 7
>88~o 4
Pipes 1
Tee M-89B S.G.
1B BLOWDOWN LIHE (IHSIDE COHT.)
Components Examined:
Results:
-: of Nominal 2
Elbows 9
>88%'
Pipes 1
Tee M-92 MAIN FEEDWATER PVMP RECIRC Components Examined:
Results:
0 of Nominal 4
Elbows 11
>88o 4
Pipes 1
88-82%
3 Reducers 1
Tee
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT III S stem Com onent Result Summaries:
Cont.
DWG.
NO.
SYSTEM M-105 HEATING STEAM Components Examined:
1 Elbow 3
Pipes 2
Reducers Results:
0 of Nominal 3
) 88+o 1
88 82O 1
76-70%'
(65~o S-57 GLAND STEAM RROM HP TURBINE THROUGH LGS 05
& LGS 08 Components Examined:
Results:
-. of Nominal 4
Elbows 13
>88o 8
Pipes 1
Tee RHR SYSTEM NEAT VALVES 624
& 625 Components Examined:
Results:
0 of Nominal 2
Elbows 10 )88 o 4
Pipes 2
Reducers 2
Tees 4A and 4B LOW PRESSURE HEATERS Components Examined:
Results:
% of Nominal 2 L.P. Heaters 5
>88-:
(6 areas) 1 82-76+o Com onent Result Details:
The following list provides examination result details on components by drawing number and system description.
The
<<Component Type" classification specified in the list below corresponds to the following:
P
= Pipe E
= Elbow T = Tee R = Reducer/Expander S
= Heater Shell
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Second Outage (1994)
ATTACHMENT ZZZ Com onent Result Details:
Cont.
Drawing No. M-2 System:
5 A/B FEEDWATER HEATERS TO FEEDWATER HEADER Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Meth 201340 34 T
1.281 0.500 1.003,0.438 1.298
)88 UT Drawing No. M-5 System:
HEATERS 4A & 4B TO FEEDWATER SUCTION Summary Comp.
Comp. Nominal Number ID e
Wall 1 Nominal Minimum Wall 2 Allowabl Minimum Percent NDE Readin Nominal M th 205110 11 T
0.375 0.375 0.253,0.218 O.S25
)88 UT 205120 12 P
0.375 205230 23 T
0.375 0.375 0.248 0.316 88-82 UT 0.253,0.218 0.535
)88 UT 205280 28 P
- 0. 375 205330 33 E
0.375 205340 34 P
0.375 205270 27 T
0.375 0.252 0.249 0.252 0.248 0.449
)88 UT 0.355
)88 UT Drawing No. M-6 System:
FEEDWATER SUCTION TO PUMPS A & B Summary Comp.
Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID e
Wall 1 Wall 2 Allowable Readin Nominal Meth 206240 24 206250 25 T
- 0. 375 P
- 0. 375 0.252 0.249 0.498
)88 UT 0.346
)88 UT
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT III Com onent Result Details:
Cont.
Drawing No. M-7B System:
CONDENSATE PUMP DISCHARGE TO FW SUCTION Summary Comp.
Comp. Nominal Number ID W ll 1 Nominal Minimum Wall 2 Allow bl Minimum Percent NDE Readin Nominal Meth 208650 65 T
0.322 0.196 0.400
>88 UT 208660 66 P
0.322 0.182 0.322 88-82 UT 208680 68 P
0.322 0.177 0.296
>88 UT 208710 71 208730 73 P
0.322 P
0.322 208700 70 T
0.322 0.196 0.182 0.177 0.367
>88 UT 0.306
>88 UT 0.298
>88 UT
~
~
~
Drawing No. M-21 System:
STEAM EXTRACTION TO PRESEP.
B R 4B LP.HEATER Summary Comp.
Comp.
Nominal Nominal Minimum Minimum Percent NDE Number ID e
Wall 1 Wall 2 Allow ble Readin Nominal Meth 301340 32 P
0.375 0.328 0.357
>88 UT 301350 33 301360 34 301370 35 301380 36 T
0.375 P
0.375 E
0.375 P
0.375 0.328 0.328 0.328 0.328 0.523
>88 UT 0.333
>88 UT 0.405
>88 UT 0.373
>88 UT Drawing No. M-22 System:
STEAM EXTRACTION TO PRESEP.
A & 4A LP.HEATER Summary Comp.
Comp. Nominal Nominal Minimum Number ID Wall 1 Wall 2 All wabl Minimum Percent NDE Readin Nominal Meth 302050 32 E
0.375 302060 32A P
0.375 t
302070 33 T
0.375 302080 34 P
0.375 0.328 0.328 0.328 0.328 0.444
>88 UT 0.338
>88 UT 0.565
>88 UT 0.329
>88 UT
R. E.
GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT ZZI Com onent Result Details:
Drawing No. M-22 (Cont.)
Summary Comp.
Comp. Nominal Number ID e
Wall 1 Cont.
Nominal Minimum Minimum Percent NDE Wall 2 Allowable Re din Nominal Meth 302090 35 302100 36 E
0.375 P
0.375 0.328 0.436
)88 UT 0.328 0.358
)88 UT Drawing No. M-45 System:
PRESEP DRN TNKS AM3 TO HTR DRN TNK & COND.
Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Meth 298520 52 P
0.432 0.185 0.307 76-70 UT e
298525 52A R
0.432 0.232,0.179 0.337
)88 UT Drawing Ho. M-46B System:
PRESEPARATOR ASB DRAIN TO HEATER DRAIN TANK Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowabl Minimum Percent NDE R
din Nominal Meth 328080 08 P
0.432 0.168 0.232 (65 UT 328090 09 T
0.562 0.231 0.283 70-65 UT Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowable Minimum Percent NDE Readin N min l Meth 0.377
)88 UT 0.218 303010 01 P
0.375 303015 1A R
0.365 303020 02 T
0.375 303030 03 P
0.375 0.375
- 0. 210,'0. 228
- 0. 376
)88 UT 0.231 0.225 0.309 88-82 UT 0.358
)88 UT Drawing No. M-75 System:
STEAM EXTRACTION TO SA 8
5B H.P.H.
R. E.
GINNA NUCLEAR POWER PLANT Znservh.ce Znspecth.on Report 1990-1999 Interval, Second Perh.od, Second Outage (1994)
ATTACHMENT ZZZ Com onent Result Details:
Drawing No. M-75 (Cont.)
Summary Comp.
Comp. Nominal Number ID e
Wall 1 Cont.
Nominal Minimum Wall 2 Allowable Minimum Percent NDE Rea in Nominal Meth 303240 24 303250 25 E
0.375 P
- 0. 375 303040 04 T
0.375 303055 05A P
0 '75 303065 06A P
0.375 303195 19A P
0.375 303205 20A P
0.375
)88 UT 0.343
)88 UT 0.194 0.349
)88 UT Drawing No. M-81 System:
FEEDWATER DISCHARGE Summary Comp.
Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID e
Wall 1 Wall 2 Allowable Readin Nominal Meth 390060 06 390210 21 R
0.844 R
0.844 0.938 0.938 0 739I 0 821 0 530 (65 UT 0.633,0.821 0.716 88-82 UT Drawing No. M-82 System:
FEEDWATER DISCHARGE Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
W ll 1 Wall 2 All wabl Minimum Percent NDE Re din Nominal Meth 392100 10 E
0.938 392120 12 E
0.938 392130 13 P
0.938 0.710 0.963
)88 UT 0.710 0.953
)88 UT 0.605 0.912
)88 UT
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT IZZ Com onent Result Details:
Cont.
Drawing No. M-83 System:
FEEDWATER DISCHARGE Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Meth 392540 04 P
0.938 0.628 0.948
>88 UT Drawing No. M-84 System:
FEEDWATER Summary Comp.
Comp. Nominal Nominal Minimum Number ID Wall 1 Wall 2 Allowable Minimum Percent NDE Readin Nominal Meth 393130 13 E
0.938 0.705 0.914
>88 UT 393140 14 393150 15 393160 16 P
0.938 R
0.938 E
1.156 1.156 0.606 0.900
>88 UT 0.932,1.146 0.963
>88 UT 0.745 0.849 76-70 UT Drawing Ho. M-89A System:
S/G 1A BLOWDOWN (INSIDE CONT.)
Summary Comp.
Comp. Nominal Nominal Minimum Number ID Wall 1 Wall 2 Allowabl Minimum Percent NDE R adin Nominal Meth 387210 21 387220 22 387230 23 387250 25 387260 26 387270 27 387290 29 P
0.179 E
0.179 P
0.179 P
0.179
, T 0.179 P
0.179 E
0.179 0.125 0.175
>88 RT 0.125 0.239
>88 RT 0.125 0.168
>88 RT 0.125 0.168
>88 RT 0.125 0.173
>88 RT 0.125 0.179
>88 RT 0.125 0.158
>88 RT 10
R. E.
GINNA NUCLEAR POWER PLANT Inserv9.ce Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT IIZ Com onent Result Details:
Cont.
Drawing No. M-89B System:
S/G 1B BLOWDOWN (INSIDE CONT.)
Summary Comp.
Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID e
Wall 1 Wall 2 Allowable R
in Nominal Meth 388140 14 388150 15 388160 '6 388170 17 388180 18 388200 20 388210 21 388220 22 388240 24 P
0.179 E
0.179 P
0.179 E
0.179 P
0.179 P
0.179 T
0.179 P
0.179 P
0.179 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.165
>88 RT 0.174 0.170
>88 RT a
>88 RT 0.174
>88 RT 0.177
>88 RT 0.172
>88 RT 0.182
>88 RT 0.173
>88 RT 0.172
>88 RT Drawing No. M-92 System:
MAIN FEEDWATER PUMP BYPASS Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowable Minimum Percent NDE Re in Nominal Meth 281060 06 281140 14 281150 15 281160 16 281180 18 281190 19 281200 20B 281270 27 E
0.594 P
0.322 E
0.322 P
0.322 E
0.594 P
0.594 E
0.594 R
0.237 0.337 0.337 0.322 0.466,0.267 0.542
>88 UT 0.166 0.166 0.166 0.443 0.376 0.309
>88 UT 0.321
>88 UT 0.303
>88 UT 0.586
>88 UT 0.553
>88 UT 0.444,0.267 '.443
>88 UT 0.113,0.169 0.336
>88 UT 11
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT III Com onent Result Details:
Drawing No. M-92 (Cont.)
Summary Comp.
Comp. Nominal Number ID e
Wall 1 Cont.
Nominal Minimum Minimum Percent NDE Wall 2 Allowable Readin Nominal Meth 281280 28 281290 29 281300 30 281730 73 P
0.322 R
0.322 T
0.375 R
0.594 0.375 0.322 0.337 0.166 0.314
>88 UT 0.167,0.212 0.309
>88 UT 0.213,0.168 0.299
>88 UT 0.430,0.231 0.488 88-82 UT Drawing No. M-105 System:
House Heating System P
0.237 01 331010 0.166 Summary Comp.
Comp. Nominal Nominal Minimum t
Number ID e
Wall 1 Wall 2 All w ble Minimum Dercent NDE Readin Nominal Meth 0.176 76-70 UT 331020 02 331030 03 331110 11 331130 13 331140 14 E
0.237 P
0.237 R
0.237 P
0.216 R
0.216 0.216 0.237 0.166 0.225 '88 UT 0.151,0.151 0.202
>88 UT 0.151 0.188 88-82 UT 0.151,0.166 0.244
>88 UT 0.166 0.150 (65 UT Drawing No.
NA System:
4A L.P.
HEATER SHELL Summary Comp.
Comp. Nominal Nominal Minimum Number ID e
Wall 1 Wall 2 Allowabl Minimum Percent NDE Readin Nominal Meth 400100 4A S
400101 4A S
400102 4A S
400103 4B S
0.500 0.500 0.500 0.500 0.438 0.438 0.438 0.438 0.500
>88 UT 0.525
>88 UT 0.505
>88 UT 0.489
>88 UT 12
R. E.
GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT III Com onent Result Details:
Cont.
Drawing No.
NA System:
4A L.P.
HEATER SHELL (Cont.)
Summary Comp.
Comp. Nominal Number ID e
Wall 1 Nominal Minimum Wall 2 Allowabl Minimum Percent NDE Readin Nominal Meth 400105 4B S
0.500 0.438 400104 4B S
0.500 0.300 0.408 82-76 UT 0.502
>88 UT Drawing No. S-57 System:
GLAND STEAM FROM HP TURBINE THROUGH LGS-05,08 Summary Comp.
Comp. Nominal Number ID e
Wall 1 Nominal Minimum Wall 2 Allowable Minimum Percent NDE Readin Nominal Meth 400106 1
t 400108 3
400109 4
400110 5
400111 6
400112 7
400113 8
400114 9
400115 10 400116 11 400117 12 400118 17 400121 20 P
0.179 P
0.179 E
0.179 P
0.179 E
0.179 P
0.179 E
0.179 P
0.179 E
0.179 P
0.179 T
0.179 P
0.179 P
0.191 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.125 0.134 0.247
>88 RT 0.180
>88 RT 0.238
>88 RT 0.178
>88 RT 0.229
>88 RT 0.181
>88 RT 0.250
>88 RT 0.180
>88 RT 0.257
>88 RT 0.173
>88 RT 0.162
>88 RT 0.175
>88 RT 0.175
>88 RT 13
R. E.
GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Second Outage (1994)
ATTACHMENT ZIZ Com onent Result Details:
Cont.
Drawing No.
NA System:
RHR NEAR VALVES 624 and 625 Summary Comp.
Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID e
Wall 1 Wall 2 Allowable Readin Nominal Meth 400122 1
400123 2
400124 3
400125 4
400126 5
400127 6
400128 7
400129 8
400130 9
400131 10 T
0.322 P
0.322 R
0.322 0.365 0.282 0.282 0.337
>88 UT 0.356
>88 UT 0.282,0.319 0.317
>88 UT P
0.322 0.322 0.322 0.322 0.322 0.365
- 0. 365 0.282
, 0.282 0.282 0.282 0.372
>88 UT 0.284
>88 UT 0.299
~88 UT 0.360
>88 UT
- 0. 282, 0. 319
- 0. 340
>88 UT 0.319 0.335
>88 UT E
0.280 0.322 0.245,0.282 0.299
>88 UT 14
i