ML17264A123

ISI Rept for Third Interval (1990 - 1999) Second Period, Third Outage (1995) at Re Ginna Nuclear Power Plant, Rev 0

ML17264A123
Person / Time
Site:	Ginna
Issue date:	07/24/1995
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
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ML17264A122	List: ML17264A121 ML17264A123
References
NUDOCS 9508080402
Download: ML17264A123 (177)

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ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUES ROCHESTER'Y 14649 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE THIRD INTERVAL (1990 - 1999)

SECOND PERIODi THIRD OUTAGE (1995)

AT R E GINNA NUCLEAR POWER PLANT REVISION 0 JULY 24 i 1995 9'508080402 950802 PDR ADOCK 05000244 9 PDR

R E GINNA NUCLEAR POWER PLANT NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT THIRD INTERVAL (1990 - 1999)

SECOND PERIODS THIRD OUTAGE (1995)

OWNERS DATA SHEET Date: 24 July, 1995 Owner: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 I

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

0 R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

TABLE OF CONTENTS Introduction and Synopsis Summary of Work Accomplished Class 1 Components Class 2 Components Class 3 Components High Energy Components Design Break Weld Examinations Consequential Break Weld Examinations Component Support Examinations Steam Generators System Pressure Testing Hydrostatic Testing Leakage Testing Section XI, Service Induced Rejectable Components Expanded Examinations Snubbers Visual Examinations Functional Testing Seismic Support Program Erosion/Corrosion (Minwall) Program Attachment I ISI Program Examination Summary Attachment II Repair, Replacement & Modification Program Summary Attachment III Erosion/Corrosion (Minwall) Program Summary 1 ~

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

ZNTRODUCTION AND SYNOPSIS Inservice Inspection (ISI) activities for 1995 were performed on components within Class 1, 2, 3, High Energy Piping, Steam Generator Tubes, Seismic Supports and Snubbers.

ISI examinations were concluded on May 4, 1995. 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 this time.

Personnel involved included RG&E Laboratory and Inspection Services, 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, RG&E General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering .Services Department.

ASME SECTION XI

SUMMARY

OF WORK ACCOMPLISHED:

Upon conclusion of the 1995 Outage, 56.14 of ASME Section XI Code required examinations for the, Third Interval ISI Program has 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 38 ASME, Augmented or Owner Elected components were examined. The examinations for these components consisted of 2 VT-3's, 33 PT's, and 12 UT's. A total of 47 examinations were performed on Class 1 Components.

R. E GINNA NUCLEAR PORER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

CLASS 1 COMPONENTS: Cont.

Class 1 examinations were performed on the following items/systems and/or plant lines/component:

Item S stem Descri tion Plant Line Com onent CVCS-Charging System: 2-CH5-2501 2B-CH5-2501 2C-CH5-2502 2A-CH5-2501 2I-CH5-2502 Regenerative Heat Exchanger: ECH02C CVCS-Letdown System: 2A-CH4-2501 High Pressure Safety Injection System: 10A-SI2-2501-B 2A-SI2-2501 2B-SI2-2501 Pressurizer: TRC01 Pressurizer System: 3A-RC8-2501-A 3A-RC8-2501-B 3A-RC8-2501 3B-RC8-2501 3C-RC8-2501 4A-RC8-2501-A Reactor Coolant Pump B Items: PRC01B Reactor Coolant System: 31 -RC -2501-A 31 -RC -2501-B 27.5-RC -2501-A, 2D -RCO-2501-B 2B -RCO-2501-B Residual Heat Removal System: 10A -AC7-2501-B

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

CLASS 2 COMPONENTS:

A total of 63 ASME or Owner Elected Components were examined. The examinations for these components consisted of 3 VT-1's, 30 VT-3's, 21 PT's, 10 MT's, 2 RT's, 8 UT's, and 2 VT-2's for a total of 76 examinations.

Class 2 examinations were performed on the following items/

systems and/or plant lines/components:

Item S stem Descri tion Com onent Pulsation Dampener: SCH11 CVCS-Charging System: 8A-CH -2502 2D-CH5-2501 2F-CH5-2501 Feedwater System: 14A-FW-900-1A 14B-FW-900-1B High Pressure Safety Injection System: 10 -SI-151 8K-SI-151 4 -SI-301 4D-SI-1501 4E-SI-1501 3C-SI-1501 3E-SI-1501 Mainsteam System: 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1B 6B-MS-600-1A 6B-MS-600-1B Residual Heat Removal Heat Exchanger: EAC02A Residual Heat Removal System: 10 -AC-601 10A-AC-601 6 -'AC-60 1 6B -AC-601 6D -AC-601 Standby Aux. Feedwater System: 3C-FW-902S-1A

R ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

CLASS 2 COMPONENTS: Cont.

Item S stem Descri tion Plant Line Com onent Service Water System: 8I-SW-125 8L-SW-125 8M-SW-125 6-SW-125 6A-SW-125 6B-SW-125 6F-SW-125 6G-SW-125 CLASS 3 COMPONENTS:.

A total of 119 ASME or Owner Elected Components were examined utilizing the VT-3 visual technique.

Examinations were performed on the following items /

systems and/or'lant lines/components:

Item S stem Descri tion Plant Line Com onent Auxiliary Cooling System: 14B -AC5-152 14C -AC5-152 10G -AC5-152 10H -AC5-152 10I -AC5-152 8B -AC6-152 6C -AC6-152 6E -AC6-152 6G -AC6-152 Auxiliary Feedwater System: 5A -FW7-900-1 4A -SW -125-1B 4A -SW -125-1C 3A -FW7-900-1A 3A -FW7-900-1B 3E -FW7-900-1 3G -FW7-900-1 3H -FW7-900-1 3J -FW7-900-1 2A -FW7-900-1B 2C'-FW7-900-1A 1-5A-FW7-900-1

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

CLASS 3 COMPONENTS: Cont.

Item S stem Descri tion Plant Line Com onent Seal Water Heat Exchanger: ECH04 Diesel Generator System: 5C-DG-A Mainsteam System: 6A-MS-600-1 6C-MS-600-1 Standby Aux. Feedwater System: 4A-FW8-152S-B 4G-SWO-152S 4F-SWO-152S 3A-FW8-902S-A 3A-FW8-902S-B 3C-FW8-902S Service Water System: 14D-SWO-125-1 14E-SWO-125-1 14G-SWO-125-1 14H-SWO-125-1 10B-SWO-125-1 6H-SWO-125-1 HIGH ENERGY COMPONENTS:

Nineteen (19) Augmen'ted or Owner Elected items associated with the High Energy Program were examined during the 1995 Outage. The examinations for these items consisted of 15 VT-1's, 3 VT-3's, 16 MT's, 8 RT's, and 7 UT's for a total of 49 examinations.

High Energy component examinations were performed on the following items / systems and/or plant lines:

Item S stem Descri tion Plant Line Feedwater System: 20 -FW-900-1 14A-FW-900-1A 14B-FW-900-1 14B-FW-900-1B Mainsteam System: 36 -MS-600-1 30A-MS-600-1 30B-MS-600-1 24B-MS-600-1A

R ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

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 1995 Outage:

Open Generator Tubes, Previous indications greater than or equal to 204 were examined to the extent of degradation as a minimum.

2. Open Generator Tubes, 204 Random Sample of all open unsleeved tubes were examined Full Length (F/L).

3. 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. Applicable Wear Indications Cold Leg, Tubes R1C10-R1C12.

Steam Generator Eddy Current Examination details are documented in the Rochester Gas & Electric 1995 Steam Generator Eddy Current Final Report.

SYSTEM PRESSURE TESTS:

H drostatic Testin No 10-Year ISI (ASME) Hydrostatic tests were performed during the 1995 Outage.

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

SYSTEM PRESSURE TESTS: Cont.

Leaka e Testin A total of sixteen (16) ASME or Augmented Leakage Examinations were performed. The Leakage tests included; one (1)

Class 1, Reactor Coolant System (PT-7) examination, fourteen (14) Class 2 or 3 examinations, and one (1) High Energy Mainsteam examination. It should be noted that one (1) Class 3 examination was partially completed during this refueling outage.

ASME Section XI Re uired Com onents Service Induced Re'ectable

- E anded Examinations:

There were no ASME Section XI required components that were classified as "Service Induced Rejectable" that needed Code expanded examinations.

SNUBBER PROGRAM:

Visual Examinations:

A total of 23 Snubber component support baseline examinations were performed during the 1995 outage.

Snubber visual examinations were performed on'he following items /systems and/or plant lines:

Item S stem Descri tion Plant Line Aux. Feedwater System: 3B-FW -900-lA 3Z-FW7-900-1 3K-FW7-900-1 Blowdown System: 2C-MS -600-1B CVCS-Letdown System: 2A-CH4-151 2E-CH -601 Feedwater System: 14A-FW-900-1A 14B-FW-900-1B

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item S stem Descri tion Plant Line Mainsteam System: 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1 6B-MS-600-1A 6B-MS-600-1B Pressurizer System: 6AP-RC -602 3B -RC8-2501 Standby Aux. Feedwater System: 3C-FW-902S-1A 3C-FW-902S-1B Steam Generator B: EMS01B Functional Testin A total of twenty-three (23) snubbers were Functionally Tested (FT) during the 1995 outage. From the sixteen (16) snubbers that were originally scheduled, twelve (12) were mechanical snubbers and four (4) were hydraulic snubbers. Due to snubber failures, an expansion was performed that consisted of seven (7) additional snubbers that were Functionally Tested.

Scheduled Snubber Functional Tests (FT) were performed on Plant Lines listed above under Snubber Visual examinations.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

SEISMIC SUPPORT PROGRAM:

A total of nine '(9) 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 tion Plant Line CVCS-Charging System: 2T-CH-151 Mainsteam System: 6D-MS-600-1A 6E-MS-600-1B 6F-MS-600-1B Pressurizer System: 8 -RC-601 Residual Heat Removal System: 3C-WD-151 Standby Aux. Feedwater System: .5F-CD-152S Service Water System: 10C-SWO-125-1 EROSION CORROSION MINWALL PROGRAM:

A total of 96 items were examined during the 1995 Outage.

The breakdown of this total is as follows:

Com onent T e Total Number Pipes 51 Elbows 34 Reducers 6 Tees 4 Expansion Joints 1

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

EROSION CORROSION MINWALL PROGRAM Cont.

Component thickness measurements were performed on the following systems:

DWG NO SYSTEM M-1 A/B F.W. PUMP DISCHARGE TO 5 A/B HEATERS M-2 5 A/B F.W. HEATERS TO F.W. HEADER M-4A FEEDWATER CLEANUP TO CONDENSER FROM 5A/B HP HEATERS M-4B FEEDWATER CLEANUP TO CONDENSER & CONDENSATE DEM.

RINSE M-7A HEATER DRAIN TANK DISCHARGE M-10 LOW PRESSURE DOWNCOMERS (WEST CONDENSER)

M-10A LOW PRESSURE DOWNCOMERS TO L.P.H. (WEST CONDENSER)

M-10B LOW PRESSURE DOWNCOMERS (EAST CONDENSER)

M-10C LOW PRESSURE DOWNCOMERS TO L.P.H. (EAST CONDENSER)

M-11A MSR 1A & 1B 2ND PASS DRAIN M-15A MSR 1A 4TH PASS TO 5A HEATER M-15B MSR 1B 4TH PASS TO 5A HEATER M-16 MSR 1A & 1B 4TH PASS TO CONDENSER M-3 1 MSR 1A & 1B TO HEATER DRAIN TANK & CONDENSER M-4 1A 5A HP HEATER DRAIN TO 4A LP HEATER M-4 1B 5B HEATER DRAIN TO 4B HEATER M-75 STEAM EXTRACTION TO 5A & 5B HEATERS M-81 FEEDWATER DISCHARGE (TURBINE BLDG)

M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

M-90 FEEDWATER CLEAN UP (CV-18)

M-91 FEEDWATER CLEAN UP (CV-19)

M-105 HEATING STEAM 10

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

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. Kl packi Date ISI Engineer Michael J. Saporito Date Manager, Laboratory and Inspection Services, Technical Performance and Field Inspections 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 New 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 Code,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: Pica c'f CP 7u 5~

ANII's Signature Date 11

S FORM NIS-1 OWNERsS REPORT FOR INSERVICE INSPECTIONS As required by thc Provisions of thc ASME Code Rules I. Owner Rochester Gas g Electric Cor . 89 East Ave. Rochester N.Y. 14649 (Name and Address of Owner)

2. Plant R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519 (Name and Address of Plant)

Plant Unit 1 4. Owner Certificate of Authorization (ifrequired) N A

5. Commercial Service Date Jul 1970 6. National Board Nurnbcr for Unit N A

7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

(*) SEE "ATTACHMENT I" FOR APPLICABLE INFORMATION Note: Supplemental sheets in form of lists, sketches, or drawings may bc used, provided (1) size is 8-1/2 in. x 11 in., (2) information in items 1 through e 6 on this rcport is included on each shcct, and (3) each shcct is numbered and the number of sheets is recorded at thc top of this lorm.

(12/86) This form (E0029) may be obtained from thc Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ07007-2300

FORM NIS-1. (Back)

9. Inspection Interval I'rom 1990 to 1999

10. Applicable Editions of Section XI 1986 Addenda No I I. Abstract of Examinations, Include a list of examinations and a statcmcnt concerning status of work required for current interval. (*)

12. Abstract of Conditions Noted. (*)

13. Abstract of Corrective Measures Rccommcnded and Taken. (*)

We certify that statements made in this rcport are correct and the examinations and corrective mcasurcs taken conform to the rules of thc ASME Code,Section XI.

Ccrtificatc of Authorization No. (ifapplicable) N A Expiration Date N A Date 24 Jul 19 95 Signed Rochester Gas dc Electric Co oration By Owner CERTIFICATE OF INSERVICE INSPECTION I, the undcrsigncd, holding a valid commission issued by thc National Board of Boiler and Pressure Vessel Inspectors and thc State or Province of New York and employed by Hartford Steam Boiler Ins ection 8c Insurance Com an . of Hartford CF have inspected the components described in this Owner's Report during thc period AP to W M 5~ and state that to the best of my knowledge and belief, the Owner has pcrforrncd examinations and taken corrective mcasurcs described in this Owner's Report in accordance with the inspection plan and as required by thc ASME Code,Section XI.

By signing this certilicate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrcctivc measures dcscribcd in this Owner's Rcport. Furthermore, neither the Inspector nor his employer shall bc liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

~~i+'5'. .u~~ Commissions Inspector's Signature National Board, State, Province, and Endorscmcnts Date 19 9S SEE <<ATTACHMENT I<< FOR APPLICABLE INFORMATION

0 S

iO

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.oommerci al Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I A. CLASS 1 COMPONENTS t Ale PRESSURIZER DRAWINGS'-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 004700 B-D B3.120 SPLN ASME UT SPRAY LINE NOZ-INS RAD SECT 95 -UT: NO RECORDABLE INDICATIONS, 360 DEGREES ACCEPTABLE.

004800 B-F B5.40 RC-1000-MSW-1 ASME PT SAFE END-TO-NOZZLE UT (SPRAY LINE) 95 -PT! INSIGNIFICANTS L=O, W= 1/8, UP, 1/16" ROUND. UT! NO RECORDABLE 6 GEOMETRYS ID GEOMETRY. > 90% CODE COVERAGE OBTAINED ACCEPTABLE.

A2e REGENERATIVE HEAT EXCHANGER C DRAWINGS: A-8 Item NDE Number Component Component Type Exam B3.150 RHE-Nl ASME UT VESSEL-TO-NOZZLE WELD 95 -UT: NO RECORDABLE INDICATIONS, UT LAM PERFORMED IN 1986.

APPROX. 94% COVERAGE OBTAINED ACCEPTABLE.

NOTE: "COMPONENT TYPE" IS DEFINED AS FOLLOWSt "ASME"= ITEM REQUIRED BY ASME SECTION XI CODE "AUG" = AUGMENTED PROGRAM ITEM REQUIRED BY NRC COMMITMENT "OE" = OWNER ELECTED NON MANDATORY EXAMINATIONS

e 1990-1999 Re Ee "GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT CLASS 1 COMPONENTS CONT ~

A3e REACTOR COOLANT SYSTEM-LOOP A DRAWINGS: A-3B n

Summary Exam Item NDE Number Categ Number Component Component Type Exam 011820 B-J B9.12 PL-FW-XII-LR (XIII) ASME UT LONGITUDINAL SEAM WELD 95 -UT NO RECORDABLE INDICATIONS ACCEPTABLE. GREATER THAN 90t COVERAGE OBTAINED. RELIEF REQUEST TO BE GENERATED FOR CAST MATERIAL.

012100 B-J B9.11 PL-FW-VI ASME UT PUMP(RCP-A)-TO-PIPE PT 95 -PT: NO RECORDABLE Ec INSIGNIFICANT INDICATIONS- L=33.5 CWS W= 2.10" UP-0.15" LONG. L=39.4 CW, WNN 0.45am DOWN ROUND 0 15" -ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE. ) 90%.

A4 ~ REACTOR COOLANT SYSTEM-LOOP B DRAWINGS: A-3F Summary Exam Item NDE Number Categ Number Component Component Type Exam

'013320 B-J B9.12 . PL-FW-XI-LR (XV) ASME UT LONGITUDINAL SEAM WELD PT 95 -PTt INSIGNIFICANTS FABRICATION INDICATIONS ACCEPTABLE.

UT: NO RECORDABLE INDICATIONS ACCEPTABLE. RELIEF REQUEST TO BE GENERATED DUE TO CAST MATERIAL.

013500 = B-J B9.11 PL-FW-XV ASME UT ELBOW-TO-PUMP(RCP-B) PT 95 -PT NO RECORDABLE INDZCATIONS, SURFACE CONDITIONING PERFORMED ACCEPTABLE. UT: NO RECORDABLE INDICATIONS < 90't CODE COVERAGE OBTAINED. RELIEF REQUEST TO BE GENERATED TO ADDRESS CODE COVERAGE AND CAST MATERIAL ACCEPTABLE.

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 S.National Board Number ror Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

A5. 3-IN. PRESSURIZER SPRAY LINE DRAWINGS: A-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 015400 B-J B9.21 BSW-1 ASME PT PIPE-TO-ELBOW 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

019600 B-J B9.21 M-1 ASME PT PIPE-TO-REDUCER 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

019800 B-J B9.21 A ASME PT NOZZLE-TO-PIPE 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

A6. 2-IN. PRESSURIZER SPRAY LINE DRAWINGS: A-ll Summary Exam Item NDE Number Categ Number Component Component Type Exam 024000 B-J B9.40 14 ASME PT PIPE-TO-COUPLING 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

025300 B-J B9.40 21 ASME PT ELBOW-TO-PIPE 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

025400 B-J B9.40 22 ASME PT PIPE-TO-VALVE(297) 95 -PT$ NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit, 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT ~

A7a 3-IN. PRESSURIZER RELIEF LINE DRAWINGS: A-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 026600 B-J B9.21 C ASME OE PT REDUCER-TO-VALVE(515) 95 -PTs BASELINE EXAMINATION, NO RECORDABLE INDICATIONS ACCEPTABLE- NOTE: CONSTRUCTION NDE ON MAINTENANCE

SUMMARY

M95127.

026700 B-J B9.21 D OE PT VALVE(515)-TO-PIPE 95 -PT: BASELINE EXAMINATION, NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE1 CONSTRUCTION NDE ON MAINTENANCE

SUMMARY

M95127.

027000 B-J B9.21 B ASME PT REDUCER-TO-VALVE(516) 95 -PT: BASELINE EXAM, NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: CONSTRUCTION NDE ON

SUMMARY

M95132 Ec.

MOVATS REPORT 95-36.

027100 B-J B9.21 C ASME PT VALVE(516)-TO-PIPE 95 -PT: BASELINE EXAM, NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: CONSTRUCTION NDE ON

SUMMARY

M95132 &

MOVATS REPORT g 95-36.

R. E. GINNA NUCLEAR POWER PLANT

/

Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 C.ommercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

AS. 4-IN. PRESSURIZER RELIEF LINE DRAWINGS: A-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 028200 B-J B9.11 Q ASME UT REDUCER-TO-ELBOW PT 95 -PT 6 UT: NO RECORDABLE INDICATIONS ACCEPTABLE. 100't COVERAGE.

A9 ~ RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 029100 B-J B9.11 ASW-1 ASME UT PIPE-TO-ELBOW PT 95 -PT 6 UT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

A10 ~ H.P ~ SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 033800 B-J B9.11 FSW-1 ASME UT PIPE-TO-ELBOW PT 95 -PT 6 UT: NO RECORDABLE INDICATIONS ACCEPTABLE. GREATER THAN 90% COVERAGE OBTAINED.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

All. H.P, SAFETY INJECTION LINE DRAWINGSa A-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam

,038700 B-J B9.40 FSW-19 ASME PT TEE-TO-REDUCER 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

041700 B-J B9.40 GSW-15 ASME PT ELBOW-TO-PIPE 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE A12 ~ 2" H.P SAFETY INJECTION TO LOOP B HOT LEG DRAWINGS: A-21 Summary Exam Item Number Categ Number Component Component Type Exam 042200 B-J B9.40 GSW-20 ASME PT 2" PIPE-TO-BRANCH CONNECTION 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

A13. 2" LETDOWN TO REGEN HTX DRAWINGS: A-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 044900 B-J B9.40 20 ASME PT PIPE-TO-ELBOW 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

045425 F-A F1.10R CVU-33 ASME GUIDE 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT ~

Ale SEAL WATER TO RCP-A, DRAWINGS: A-3 1 Summary Exam Item Number Categ Number Component Component Type Exam 049750 B-J B9.40 20 ASME PT ELBOW-TO-PIPE 95 PT RE JECT f 1 /8 ROUND PORE f BLEEDOUT 1 /4 AT F ITTING SIDE-TOE OF WELD ORIGINAL CONSTRUCTION, NCR95-030 GENERATEDS USE AS IS ~ SURFACE CONDITIONING PERFORMEDS PORE REMOVED. PERFORMED VT & PT ON CONDITIONED AREA, NO RECORDABLE - ACCEPTABLE.

049765 B-J B9.40 19 ASME PT PIPE-TO-ELBOW 95 -PT: NO RECORDABLE INDICATIONS, GREATER THAN 90't COVERAGE OBTAINED, ACCEPTABLE.

A15e 2" CHARGING TO LOOP B COLD LEG DRAWINGS: A-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 050740 F-A F1.10V CVU-6 ASME VT-3 VARIABLE SPRING 95 -VT-3: NO RECORDABLE INDICATIONS, TEMP. 73 DEG F SETTING 5/8" = 80 1'Sf ACCEPTABLE.

050745 B-J B9.40 21C ASME PT TEE-TO-REDUCER 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

050750 B-J B9.40 22 ASME PT PIPE-TO-VALVE(295) 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

0 i

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT. t A16 ~ 2" ALTERNATE CHARGING TO LOOP A COLD LEG DRAWINGS: A-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 051400 B-J B9.40 20 ASME PT VALVE(392B) -TO-PIPE UT 95 -PT: WELD NO RECORDABLE INDICATIONS ACCEPTABLE VALVE (V392B) CASTING SIDE CONTAINS LARGE AMOUNTS OF POROSITY (1/8 TO 3/8"), NOT SERVICE INDUCED. NCR 95-033 GENERATED. UT THICKNESS PERFORMED, AVERAGE ~ 600" ~ USE-AS-IS PER ENGINEERING -ACCEPTABLE.

052500 B-J B9.40 30 ASME PT ELBOW-TO-PIPE 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

052700 B-J B9.40 32 ASME PT PIPE-TO-COUPLING 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

A16. 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 054930 B-J B9.40 9B ASME PT r

VALVE(9315)-TO-TEE 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

054960 B-J B9.40 9D ASME PT TEE-TO-REDUCING INSERT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

10

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

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 ~

Ale 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Item Number Categ Number Component Component Type Exam 055300 B-J B9.40 12 ASME PT PIPE-TO-NOZZLE 95 -PT NO RECORDABLE INDICATIONS ACCEPTABLE.

A18 ~ REACTOR COOLANT PUMP B DRAWINGS NA Summary Exam Item NDE Number Categ Number Component Component Type Exam 058105 FLYWHEL RG-1.14 RCP-B FLYWHEEL, EXPOSE AUG PT AREAS UT 212-3D19156-Gol-02 95 -PT & UT: EYWMINED ALL ACCESSIBLE AREAS, NO RECORDABLE INDICATIONS ACCEPTABLE.

058120 ---- BOLT RCP-B ANCHOR BOLTS OE UT BOLTS 95 UT NO RECORDABLE INDICATIONS FOR STUDS Ll L4 f Ml M4 f Nl f N3 s N4 ~ OTHER STUD L4 IS 1 1 7 LONG ~ REJECT STUD N 2 f INDICATION AT 19.2", SEE NCR94-056 FOR RESOLUTION, NO APPARENT CHANGE SINCE 1994 EXAM. ACCEPTABLE 11

R. E ~ GINNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Intervals Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 1970 S.National Board Number for Unit jNA ATTACHMENT I B~ CLASS 2 COMPONENTS t Bl. 2" CHARGING FROM REGEN HTX DRAWINGS: A-25A Summary Exam Item NDE Number Categ Number Component Component Type Exam 050420 C3.20 CVU-60 ( IA) OE PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

050425 -- Fl. 20A CVU-60 OE VT-3 ANCHOR (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

B2e 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 054625 C3.20 CVU-48 (IA) OE PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

054630 ---- F1. 20A CVU-48 OE VT-3 ANCHOR (ZA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

12

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT ~

B3 PULSE DAMPENER DRAWINGS: B-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 075430 F-A F1.20A CF-Sl OE VT-3 SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

075460 F-A F1.20A CF-S2 OE VT-3 SUPPORT (IA) 95 -VT-3: NO RECORDABLE 6 REJECTS LACK OF THREAD ENGAGEMENT BY 1 THREAD ON NE HILTI NUT, NOT SERVICE INDUCED. USE-AS-IS PER ENGINEERING LETTER DATED 5/25/95 ACCEPTABLE.

075500 C-C C3.20 CF-Sl (IA) OE PT

. INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

075600 C-C C3.20 CF-S2 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

13

R. E ~ GINNA NUCLEAR POWER PLANT inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1970.6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT. t B4e CHARGING PUMP A TO PULSE DAMPENER DRAWINGS: B-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 077500 F-A F1.20R CVU-411 OE VT-3 RIGID RESTRAINT (IA) 95 -VT-3s NO RECORDABLE & INSIGNIFICANTS POOR WORKMANSHIP ON WELD REPORTED ON 942074 PT EXAM RECORD ACCEPTABLE.

077501 C-C C3.20 CVU-411 (IA) ASME PT INTEGRAL ATTACHMENT LENGTHEN VT-1 95 -PT: REJS POOR WELD WORKMANSHIP ON ORIGINAL WELD.

NCR94-133 GENERATED. SURF CONDITIONED. VT-1: NO RECORDABLE &

INSIG: 6" OF 3/16" WELD ROUGH ON BACKSIDE PT: INSIGS IN 6" OF WELDS 1 1/4 HAS SLAGS &f INDICATIONS ON 3 ACCEPT PER NCR REV 2.

B5 ~ MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 080900 F-A F1.20V MSU-45 OE VT-3 VARIABLE SPRING 95 -VT-3: NO RECORDABLE INDICATIONS. TEMP. 106 DEG. F.,

NORTH = 1935 if'S (0.4"), SOUTH = 2115 f'S (0.6)

ACCEPTABLE.

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Intervalf Second Per'iod, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS 'ONT ~

B6a MAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 083850 C-F-2 C5.51 G2-BC-2-B ASME VT-1 FLANGE(3507)-TO-PIPE MT RT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS ACCEPTABLE. RT:

NO RECORDABLE & INSIGNIFICANTS 5-10 POROSITY AT 7 1/2' 0.031" ACCEPTABLE.

084320 F-A F1.208 MSU-58 OE VT-3 MECHANICAL SNUBBER 95 VT 3 BASELINE EXAM TEMP ~ 75 DEG ~ F f SETTING 3 1/8 f PSA-3 5" STROKES S/N 18187. NO RECORDABLE INDICATIONS ACCEPTABLE.

B7 ~ MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 088830 F-A F1.20R MSU-33 OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

088835 C-C C3.20 MSU-33 (IA) OE MT INTEGRAL ATTACHMENT 95 -MT! NO RECORDABLE INDICATIONS & LIMITATIONSS ONLY 50 't OF INTEGRAL ATTACHMENT WELD IS ACCESSIBLE DUE TO AS BUILT CONFIGURATION LIMITS ACCEPTABLE.

15

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periods Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commeccial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT ~  !

BS ~ MAIN STEAM LOOP B TO AUX FW PUMP TURBINE DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 090300 C-F-2 C5.51 L2-BC-1-A ASME RT PIPE-TO-VALVE(3504) VT-1 MT 95 -MT: NO RECORDABLE. VT-1: NO RECORDABLE & INSIGNIFICANTS SLIGHT RUST & WELD PREP. RT: INSIGNIFICANTs SLAG, POROSITYS INTERNAL CONCAVITY NO CHANGE SINCE LAST EXAMINATION ACCEPTABLE.

B9 ~ MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 090820 F-A F1.20S MSU-55 OE VT-3 MECHANICAL SNUBBER 95 VT 3 BASELINE EXAM TEMP ~ 74 DEG ~ F ~ 5 SETTING 2 1 3/ 1 6 PSA-3 5" STROKE, S/N 18195'. NO RECORDABLE INDICATIONS ACCEPTABLE v

B10. FEEDWATER LOOP A INSIDE CV DRAWINGS! B-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 093100 F-A F1.20V FWU-2 OE VT-3 VARIABLE SPRING 95 -VT-3: TEMP. 65 DEG. F., SETTING 2126 ig'S. NO RECORDABLE

& INSIGNIFICANTs LACK OF THREAD ENGAGEMENT ON UPPER HANGER ANCHOR & UPPER HANGER ROD BENT. ACCEPTABLE PER NCRS83-132 &

92-147.

093700 C-F-2 C5.51 DD5 ASME RT PIPE-TO-ELBOW MT VT-1 95 -VT-1 & MT: NO RECORDABLE INDICATIONS ACCEPTABLE RT:

NO RECORDABLE & INSIGNIFICANTs TUNGSTEN Q 30 5/8 (1/32 )5 NO CHANGE SINCE LAST EXAMINATION ACCEPTABLE.

16

Re E GINNA NUCLEAR POWER PLANT Znse&ice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 Commercial Service Date ~Jul

~ 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT. t Bll ~ FEEDWATER LOOP B OUTSIDE CV DRAWINGS'-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 095200 F-A Fl.20R FWU-45 OE VT-3 RIGID RESTRAINT 95 -VT-3: NO RECORDABLE 6 INSIGNZFICANTS RESTRAINT BODY REVERSED ACCEPTABLE.

B12. FEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Exam Item NDE 0 Number Categ 098100 F-A Number F1.20V Component FWU-11 VARIABLE SPRING 95 -VT-3: NO RECORDABLE INDICATIONS, TEMP. 69 DEG Component Type OE F.f Exam VT-3 SETTING 1/2" = 2315= g'Sf - ACCEPTABLE.

B13. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-17 Summary Exam Item Number Categ Number Component Component Type Exam 108450 F-A F1.20A PEN 111 ANCHOR OE VT-3 ANCHOR (IA) 95 -VT NO RECORDABLE INDICATIONS ACCEPTABLE.

108451 C-C C3.20 PEN 111 ANCHOR (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

17

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commeucial Service Date ~Jul 1970 B.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT B14e 6-IN, RESID HT REMOVAL TO RPV (LHSI) DRAWINGSt B-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 110650 F-A F1 20R RHU-9 OE RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 110655 C-C C3.20 RHU-9 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE B15a H P. SAFETY INJECTION FROM RHR DRAWINGS! B-19 Summary Exam Item NDE Number Categ

~ Number Component Component Type Exam 120700 C-F-1 5 OE PT REDUCER-TO-CROSS UT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS fc GEOMETRY - ACCEPTABLE. GREATER THAN 90't COVERAGE ACHIEVED.

B16. H.P. SAFETY INJECTION LINE 8K-SI-151 DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 124200 F-A F1.20R RHU-102 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

124202 C-C C3.20 RHU-102 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

18

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 Co.mmercial Service Date ~Jul 1975 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT. t B17e RESIDUAL HEAT REMOVAL FROM LOOP A HOT LEG DRAWINGS: B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 135350 F-A F1.20A PEN 140 ANCHOR OE VT-3 (IN/OUT)

ANCHOR ( IA) 95 -VT NO RECORDABLE INDICATIONS ACCEPTABLE 135351 C-C C3.20 PEN 140 ANCHOR OE PT (IA)(IN/OUT)

INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS OTHER: APPROX. 1/8im OF WELD 6 THE 1/2" INSPECTION AREA OUTSIDE OF THE TOE ARE NOT INSPECTABLE DUE TO THE INSTALLATION OF STRONG BACK. APPROX.

82% COVERAGE ACHIEVED.

B18. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 145885 F-A Fl.20R RHU-55 RIGID SUPPORT (IA)'E VT-3 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 145890 C-C C3.20 RHU-55 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

19

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periods Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant, R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.Commercial Service Date ~cul 197C S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.  !

B19e RESIDUAL HEAT REMOVAL LINE 6D-AC-601 DRAWINGS: B-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 147900 F-A F1.20A RHU-95 OE VT-3 ANCHOR (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

147910 C-C C3.20 RHU-95 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE SUCCESSIVE EXAM.

B20 ~ RESIDUAL HEAT REMOVAL LINE 6B-AC-601 DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 151100 F-A F1.20R RHU-49 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 151120 C-C C3.20 RHU-49 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE B21, RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 151700 C-F-1 1 OE PT TEE-TO-PIPE UT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY ACCEPTABLE. GREATER THAN 90't ACHIEVED.

20

S R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.Commercial Service Date ~Jul 197C S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B22. H.P. SAFETY INJECTION PUMP A SUCTION LINE DRAWINGS: B-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 160750 F-A F1.20V RHU-118 OE VT-3 VARIABLE SPRING 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. 110 DEG. F ~ , SETTING 9/16" = 183 g'S. RE-EXAM REQUIRED PER NCR94-024.

B23. H.P. SAFETY INJECTION LINE 4D-SI-1501 DRAWINGS: B-38 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161520 F-A F1.20R SIU-41 OE VT-3 RIGID RESTRAINT 95 -VT-3: SUCCESSIVE OWNER ELECTED EXAM, NO RECORDABLE INDICATIONS ACCEPTABLE.

B24. H.P. SAFETY INJECTION LINE 3C-SI-1501 DRAWINGS: B-41 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163020 F-A F1.20R SIU-85 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. SUCCESSIVE EXAM.

163021 C-C C3.20 SIU-85 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE. SUCCESSIVE EXAM 21

e 1990-1999 R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 Co.mmercial service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT t B25. H.P. SAFETY INJECTION LINE 3E-SI-1501 DRAWINGS: B-42 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163720 F-A F1.20R SIU-62 OE VT-3 GUIDE (IA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE.

163721 C-C C3.20 SIU-62 (IA) ASME PT INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B26. H.P. SAFETY INJECTION LINE 4E-SI-1501 DRAWINGS: B-42 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163890 C-F-1 C5.21 28 ASME PT PIPE-TO-ELBOW UT 95 -PT: INSIG- ROUND INDICATION 1/32" DIA. L=8 7/8, CENTER OF WELD UT: NO RECORDABLE INDICATIONS ACCEPTABLE. GREATER THAN 90% COVERAGE OBTAINED.

164180 C-F-1 C5.21 47 ASME PT ELBOW-TO-PIPE UT 95 -PT 6 UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

22

0 R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT ~

B27 e RESIDUAL HEAT EXCHANGER A DRAWINGS: B-109 Summary Exam Item NDE Number Categ Number Component Component Type Exam 169041 C-B C2.33 INSRHE-1A ASME VT-2 INLET NOZZLE-TO-SHELL WELD 95 -VT-2: TAKING CREDIT FOR EXAM PERFORMED UNDER

SUMMARY

NUMBER 413400 IN 1993, TEST WAS ACCEPTABLE.

169051 C-B C2.33 ONSRHE-1A ASME VT-2 OUTLET NOZZLE-TO-SHELL WELD 95 -VT-2: TAKING CREDIT FOR EXAM PERFORMED UNDER

SUMMARY

NUMBER 413400 IN 1993, TEST WAS ACCEPTABLE.

B289 SERVICE WATER LINE 6G-SW-125 DRAWINGS: B-50 Summary Exam Item NDE Number Categ Number Component Component Type Exam 173020 C-F-2* 3 OE MT REDUCING ELBOW-TO-PIPE UT VT-1 95 -VT-1: INSIGS SURFACE RUST 6 CORROSION OVER FULL PIPE AREA. RANDOM PITTING. MT: NO RECORDABLE INDICATIONS. UT: NO RECORDABLE INDICATIONS & GEOMETRY. UT: WALL THICKNESS .246" ACCEPTABLE PER MECH. ENG. DESIGN ANALYSIS DA-ME-95-003. WELD ACCEPTABLE.

23

Re E. GZNNA NUCLEAR POWER PLANT r

Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 Commercial Service Date ~Jul

~ 1970 B.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT. t B29e SERVICE WATER LINE BM-SW-125 DRAWINGS! B-50A Summary Exam Item NDE Number Categ Number Component Component Type Exam 173350 -- F1.20R SWU-78 OE VT-3 GUIDE 95 -VT-3: NO RECORDABLE INDICATIONS & OTHERN'HIM (3" X 1/2" X 4") WELDED IN PLACE WITH 3/16" FILLET WELD ON EAST AND WEST SIDES. ACCEPTABLE PER ME-121. NO INTEGRAL ATTACHMENT B30. SERVICE WATER LINE 6F-SW-125 DRAWINGS: B-50A Summary Exam Item NDE Number Categ Number Component Component Type Exam 173505 -- F1.20A PEN 308 ANCHOR (TYPE OE VT-3 III)

ANCHOR (ZA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

173506 ---- C3.20 PEN 308 ANCHOR OE MT (IA)(TYPE ZII)

INTEGRAL ATTACHMENT 95 -MT NO RECORDABLE INDICATIONS ACCEPTABLE.

B31, SERVICE WATER LINE 8L-SW-125 DRAWINGS: B-50A Summary Exam Item NDE Number Categ Number Component Component Type Exam 173530 C-F-2* 43 OE MT TEE-TO-PIPE UT VT-1 95 -VT-1: NO RECORDABLE INDICATIONS & INSZG: MINOR PITTING ON BASE METAL. MISALIGNMENT BETWEEN PIPE & TEE. TEE OD IS LARGER THAN PIPE 1/16" TO 1/8" ACCEPTABLE. MT:

NRZ -ACCEPT UT: NRI & GEOMETRY ACCEPTABLE. GREATER THAN 90't ACHIEVED.

24

R. E ~ GINNA NUCLEAR POWER PLANT

/ Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authoriration (If Req.) ~N A S.Commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT t B32 ~ SERVICE WATER LINE SI-SW-125 DRAWINGS s B-5 1C Summary Exam Item Number Categ Number Component Component Type Exam 174140 C3.20 SWU-64 (IA) OE MT INTEGRAL ATTACHMENT 95 -MT$ NO RECORDABLE INDICATIONS ACCEPTABLE.

174150 -- F1.20R SWU-64 OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE B33. SERVICE WATER LINE 6B-SW-125 DRAWINGS'-52B Summary Exam Item NDE Number Categ Number Component Component Type Exam 175205 F1.20A PEN 315 ANCHOR (TYPE OE VT-3 III)

ANCHOR ( IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 175206 ---- C3.20 PEN 315 ANCHOR OE MT (IA)(TYPE III)

INTEGRAL ATTACHMENT 95 -MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

25

Ra E. GINNA NUCLEAR POWER PLANT

/

Inservice Inspection Report 1990-1999 Interval, Second Periods Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D 6.'National Board Number for Unit jNA

~ ATTACHMENT I CLASS 2 COMPONENTS CONT B34. SERVICE WATER LINE 6A-SW-125 DRAWINGS: B-53 Summary Exam Item NDE Number Categ Number Component, Component Type Exam 175310 C-F-2* 3 OE MT REDUCING ELBOW-TO-PIPE UT VT-1 95 VT 1 NRI 5 ZNSIG 6 OTHERN RANDOM PITTING (SEE EXAM SHEET), MEDIUM RUST ACCEPTABLE MT! NRI 6 OTHER; RANDOM PITTING, NO WELD DEFECTS FOUND ACCEPTABLE. UT. NO RECORDABLE INDICATIONS 6 GEOMETRY ACCEPTABLE. GREATER THAN 90't ACHIEVED.

175325 F1.20A PEN 312 ANCHOR (TYPE OE VT-3 III)

ANCHOR (IA) 95 -VT-3t NO RECORDABLE & INSIGNIFICANTS VENT LINE IS EMBEDDED IN CONCRETE ACCEPTABLE 175326 ---- C3.20 PEN 312 ANCHOR OE PT (IA)(TYPE III)

INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B35. SERVICE WATER LINE 6-SW-125 DRAWINGS: B-53A Summary Exam Item NDE Number Categ Number Component'omponent Type Exam 175885 Fl.20A PEN 323 ANCHOR (TYPE OE VT-3 III)

ANCHOR (IA) 95 -VT-3s NO RECORDABLE 6 INSIGNZFICANTB VENT LINE EMBEDDED ZN CONCRETE ACCEPTABLE.

175886 ---- C3.20 PEN 323 ANCHOR OE PT (IA)(TYPE III)

INTEGRAL ATTACHMENT 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

26

0 R. Ee GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas f Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) ~N A B.Commercial Bervice Date ~Jul 1970 6.National Board Number for Unit N~A ATTACHMENT I CLASS 2 COMPONENTS CONT ~ t B36. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD INCV DRAWINGS: C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 176120 F1.20R AFU-217 (AFW-19) OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

176121 C3.20 AFU-217 (AFW-19) (IA) OE MT INTEGRAL ATTACHMENT 95 -MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

27

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periodf Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I C. CLASS 3 COMPONENTS:

Cl. SEAL WATER HEAT EXCHANGER DRAWINGS: B-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 073150 F1.40 Sl OE VT-3 SUPPORT LEG Si 95 -VT-3: NO RECORDABLE INDICATIONS - ACCEPTABLE 073160 ---- F1.40 S2 OE VT-3 SUPPORT LEG P2 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

e 073200 ---- D2.20 Sl SUPPORT LEG $ 1 IA 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

OE PT 073300 ---- D2.20 S2 OE PT SUPPORT LEG g2 IA 95 -PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

C2 ~ DIESEL GENERATOR A JSW. COOLING RETURN DRAWINGS t C-35 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500120 D-B D2.20 DG-1A (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS - ACCEPTABLE. NOTE: NO DRAWING AVAILABLE 3/16" FILLET WELDS.

500125 F-A F1.30R DG-1A OE VT-3 RIGID SUPPORT (IA) 95 -VT-3 NO RECORDABLE INDZCATIONS - ACCEPTABLE. NOTE: NO DRAWING AVAILABLE.

28

0 R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) ~N A B.Commercial Service Date ~Jul 1970 B.National Board Number for Unit jNA ATTACHMENT I CLASS 3 COMPONENTS CONT t C2. DIESEL GENERATOR A J'.W. COOLING RETURN (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 500130 D-B D2.20 DG-2A (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE NOTE: NO DRAWING AVAILABLE, 3/16" FILLET WELDS.

500135 F-A F1.30R DG-2A OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: NO DRAWING AVAILABLE.

C3. AUX'OOLING WTRe FROM NON-REG. HT. EXCH. DRAWINGS'-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500320 F-A F1.30R CCU-106 OE VT-3 RIGID RESTRAINT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. INSIG:

CHIPPED PAINT ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-129 &f NCR94-130.

500360 F-A F1.30R CCU-110 OE VT-3 RIGID HANGER 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR94-130 500370 F-A F1.30R CCU-111 OE VT-3 RIGID HANGER 95 -VT-3: NO RECORDABLE INDICATIONS-ACCEPTABLE. NOTE: 2 LUGS ON EITHER END OF U-BOLT LUGS APPEAR TO BE OLD SADDLES CUT-OUT, APPROX. 3/4 TO 1" LONG W/ 3/16" FILLET WELDS AS AN INTEGRAL ATTACHMENT-ACCEPTABLE. OE EXPANDED EXAM FOR NCR94-129 &6 NCR94-130.

29

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT ~

C4 ~ COMPeCOOL.HT.EXCHS.TO RESIDUAL HT.EXCHS ~ DRAWINGS t C-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500530 D-B D2.20 CCU-138 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE 66 INSIGS LUGI3 UNDERSIZE WELD 4"(1/8" FILLET) FROM TOP TO BOTTOM. LUG/4 UNDERSIZE WELD 7 1/2 TO 8 FROM TOPS < 1/16 f 1/2 IN LENGTH UNDERCUT 8 4" FROM TOP 1" IN LENGTH <1/32me OK PER ENG. ORIGINAL CONSTRUCTION -ACCEPTABLE.

F1.30R CCU-138 OE VT-3 GUIDE ( IA) 95 -VT-3: NO RECORDABLE 66 INSIGNIFICANTS PAINTED SURFACE, SLIGHT RUST ACCEPTABLE.

500610 D-B D2.20 CCU-146 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

500615 F-A F1.30R CCU-146 OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

CS ~ COMP ~ COOL.PMPS.SSUC.FM RES.HT ~ EX'6 SG.TK DRAWINGS: C-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500760 D-B D2.20 CCU-156 (IA) OE VT-3 INTEGRAL ATTACHMENT MT 95 -VT-3$ NO RECORDABLE INDICATIONS ACCEPTABLE'T NO RECORDABLE INDICATIONS, AUGMENTED EXAM. ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-124.

30

R. E ~ GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) ~N A B.oommeccial Bervice Date ~Jul 197D 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS . CONT.

C5 ~ COMP. COOL.PMPS.,SUC.FM RES.HT.EX. & SG. TK (Cont. )

Summary Exam Ztem NDE Number Categ Number Component Component Type Exam.

500765 F-A F1.30R CCU-156 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. INSIG:

1/8" SHIM ON WEST SIDE 6 NORTH WEST CORNER OF SUPPORT ACCEPTABLE OWNER ELECTED EXPANDED EXAM FOR NCR94-124 500770 D-B D2.40 CCU-158 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE INSIG:

LIGHT RUST, SOME CHIPPED PAINT ACCEPTABLE.

500775 F-A F1.30V CCU-158 OE VT-3 VARIABLE SPRING (IA) VT-3 95 -VT-3: REJ: OWNER ELECTED EXAM, W. SPRING CAN UPPER ATTACH LOOSE NUT, SPACER MISSING ON LOWER E. SIDE OF CLAMP.

SPRING CANS OFF SCALE. NCR94-124 GENERATED-SERVICE INDUCED VT 3 RE EXAMf NRI 6 INSIG TEMP ~ 73 DEG F 6 SETTING 1333 g S E.E< W.-ACCEPT.

500780 F-A F1.30R CCU-159 OE VT-3 RIGID RESTRAINT UT 95 -OE EXPANDED'OR NCR94-124. VT-3: OE SERVICE INDUCED REJ DEFORMATION N. ATTACH UPPER BOLT, LOWER BOLT PULLED OUT.

NCR94-125 GENERATED. VT-3: RE-EXAM REJ: S. PLATE LIFTED 5/32". UT: AUG. EXAM., 4 BOLTS 6" LONG. USE-AS-IS PER REV.

NCR94-125.

500790 D-B D2.40 CCU-160 (IA) OE VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-124.

31

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT. t C5. COMP. COOL.PMPS., SUC.FM RES.HT.EX. & SG. TK (Cont. )

Summary Exam Item NDE Number Categ Number Component Component Type Exam 500795 F-A F1.30V CCU-160 OE VT-3 VARIABLE SPRING (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. = 69 DEG. F., SETTING = 5/8" = 1832 f'S OWNER ELECTED EXPANDED EXAM FOR NCR94-124.

500800 F-A F1.30V CCU-165 OE VT-3 VARIABLE SPRING VT-3 95 -EXPANDED FOR NCR94-125. VT-3: OWNER ELECTED SERVICE ZNDUCED REJECT, LOOSE NUT TURNS < 1/8 TURN. NCR94-129 GENERATED. VT-3: RE-EXAM, NO RECORDABLE INDICATIONS ACCEPTABLE.

500810 F-A F1.30R CCU-166 OE VT-3 RIGID RESTRAINT VT-3 95 -EXPANDED FOR NCR94-125. VT-3: OWNER ELECTED SERVICE INDUCED REJECT: LOOSE BOLT, 4 NUTS LOOSE ON HZLTI BOLTS.

PLATE AWAY FROM WALL 1/8", THRD ROD NOT IN INSPECTION PORT BY 1/2"f THRDS DAMAGE. NCR94-130 GEN. VT-3: RE-EXAM, -NO RECORDABLE INDICATIONS.

500820 D-B D2.40 CCU-167 (IA) OE VT-3 INTEGRAL ATTACHMENT VT-3 95 -OWNER ELECTED EXPANDED FOR'CR94-124 VT-3: ORIGINAL CONSTRUCTION REJ: ITEM g8 WELD MISSING OVER PIPE TO ELBOW WELD. E SIDE 1/2", W SIDE 5/8". NCR94-131 GENERATED. VT-3:

RE-EXAM, INSIG: LIGHT TO MODERATE RUST. USE-AS-ZS PER NCR94-131.

32

R E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 Co.mmercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT.

CS. COMP. COOL.PMPS.,SUC.FM RES.HT.EX.& SG.TK (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 500825 F-A F1.30V CCU-167 OE VT-3 VARZABLE SPRING (IA) VT-3 95 -EXPANDED FOR NCR94-124. VT-3! OWNER ELECTED EXPANSION SERVICE INDUCED REJ: SETTING OUT OF WORKING RANGE T/C 002594 GENERATED. VT-3: RE-EXAM AFTER RESETTING, NO RECORDABLE INDICATIONS, TEMP. 73 DEG. F., SETTING 1 3/32" 29481'S - ACCEPTABLE.

F1.30R CCU-168 OE VT-3 GUIDE 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR94-130-500840 D-B D2.40 CCU-169 (IA) OE VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. INSIG:

MODERATE RUST ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-124.

500845 F-A F1. 30V CCU-169 OE VT-3 VARIABLE SPRING (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. 69 DEG F.f SETTING 7/8" = 2013 g'S. OWNER ELECTED EXPANDED EXAM FOR NCR94-124 500850 D-B D2.20 CCU-170 (IA) OE VT-3 INTEGRAL ATTACHMENT I

95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR-130.

VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

33

Re E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commercial Service Data ~Jul 197D 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT.

C5. COMP. COOL.PMPS.,SUC.FM RES.HT.EX.& SG.TK (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 500855 F-A F1.30R CCU-170 OE VT-3 GUIDE (IA) 95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR94-130.

VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE C6. AUX.COOL. IN & OUT FOR BORIC ACID EVAPORe DRAWINGS! C-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500910 D-B D2 20 CCU-128 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE INSIG LIGHT TO MODERATE RUST. NO SPECIFICATIONS FOR WELD REINFORCEMENT, INTEGRAL ATTACHMENT ABANDONED IN PLACE ACCEPTABLE 500915 F-A F1.30R CCU-128 OE VT-3 GUIDE (IA) 95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE.

501000 F-A F1.30R CCU-161 OE VT-3 GUIDE 95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR94-130.

501010 F-A F1.30R CCU-162 OE VT-3 RIGID RESTRAINT 95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE. OWNER ELECTED EXPANDED EXAM FOR NCR94-129 & NCR94-130.

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Becvice Date ~cul 197D B.National Board Number for Unit Nja ATTACHMENT I CLASS 3 COMPONENTS CONT ~

C6. AUX.COOL. IN & OUT FOR BORIC ACID EVAPOR. (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 501030 D-B D2.20 CCU-164 (IA) ASME INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

501035 F-A F1.30A CCU-164 OE VT-3 ANCHOR (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

C7 ~ AUX ~ COOL WTR FROM PEN 124f 125 f 126 Et 130 DRAWINGS: C-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 501140 F-A F1.30R CCU-231 OE VT-3 RIGID HANGER 95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-129 6 NCR94-130.

VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

501150 F-A F1.30R CCU-232 OE VT-3 RIGID RESTRAINT 95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-129 6 NCR94-130.

VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

501160 F-A F1.30R CCU-233 OE VT-3 RIGID RESTRAINT 95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-129 6 NCR94-130.

VT-3: NO RECORDABLE INDICATIONS - ACCEPTABLE.

35

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT .

C8. SW COMP. COOLeR SP.FUEL PIT HT EXSesDZSCH DRAWINGS:" C-11 Summary Exam Item NDE Number Categ Number Component Component Type Exam 501660 D-C D3.20 SWU-164 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 501665 F-A F1.30R SWU-164 OE VT-3 RIGID HANGER (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

C9 ~ SVC.WTR ~ -TO COMP ~ COOL ~ & SP.FL.PIT HT.EX'RAWINGSi C-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 501870 D-C D3.20 SWU-191 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3t NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; MODERATE RUST ON PIPE ACCEPTABLE.

501875 F-'A F1.30R SWU-191 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT MODERATE RUST. DRAWING DOES NOT MATCH SUPPORT ITEMS OLD Ec CUT-OFF LUGS REMAIN, DCR GENERATED - fl 6 ACCEPTABLE f5.

501890 D-C D3.20 SWU-193 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

36

R. E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 C.ommercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT C9. SVC.WTR.-TO COMP. COOL.& SP.FL.PIT HT.EXS. (Cont.)

Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 501895 F-A Fl.30R SWU-193 OE VT-3 RIGID HANGER (ZA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE C10. SVC.WTR.-TO A & B DIESEL GENeWTReCOOLERS DRAWINGS: C-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 502270 D-B D2.20 SWU-251 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3! NO RECORDABLE INDICATIONS & INSIGNIFICANTS LIGHT RUST ON THE INTEGRAL ATTACHMENT ACCEPTABLE.

502275 F-A F1.30R SWU-251 OE VT-3 RIGID SUPPORT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS & INSIGNIFICANT ITEM g2 BASE PLATE IS COVERED WITH A HEAVY COAT OF PAINT AND CANNOT BE SEEN ACCEPTABLE.

Clio SVC.WTR.-INTMD.BLDG.16"HD.TO PEN 312-320 DRAWINGS: C-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 502960 D-B D2.20 SWU-340 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

502965 F-A F1.30R SWU-340 OE VT-3 RIGID HANGER (IA) f 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: ITEM f3 FILLET WELD TO BEAM = 3/16". ITEM ill, 4 SEPARATE FILLET WELDS ARE ACCORDING TO DRAWING.

37

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 .Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 197C 6.National Noavd Number for Unit jNA ATTACHMENT I CLASS 3 COMPONENTS CONT.

C12 ~ SVC.WTR.-INTMD.BLDG.14"HD.TO CHILL. ASB DRAWINGS: C-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 503000 D-B D2.20 SWU-344 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

503005 F-A Fl.30R SWU-344 ASME VT-3 RIGID RESTRAINT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE COL S/N C13 ~ SVCeWTR ~ PUMPS AfBf C 6 D DISCH ~ SCR ~ HOUSE DRAWINGS'-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 503445 F-A F1.30R SWU-630 (N741) OE VT-3 GUIDE 95 -VT-3: BASELINE EXAM FOR EWR 5284B V4604 REPLACEMENT. NO RECORDABLE Ec INSIGNIFICANTf IMPROPER CLEARANCEf NO GAPf ACCEPTABLE PER ME-121 ACCEPTABLE.

503480 D-B D2.20 SWU-634 (N745) (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: BASELINE EXAM FOR EWR 5284B V4604 REPLACEMENT. NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: ADDITIONAL EXAMINATIONS PERFORMED INCLUDED VT-1 6 MT ACCEPTABLE 503485 F-A F1.30R SWU-634 (N745) ASME VT-3 RIGID SUPPORT (IA) 95 -VT-3: BASELINE EXAM FOR EWR 5284B V4604 REPLACEMENT. NO RECORDABLE 6 INSIGNIFICANTf ANCHOR BOLTS ACCEPTABLE PER NOTE ON DRAWING ACCEPTABLE.

38

R. E. GINNA NUCLEAR POWER PLANT

/

Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Bervice Date ~cul 1970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT C14 ~ AUX ~ FW PUMPS DZSCH INTERMED ~ BLDG, DRAWINGS: C-1F Summary Exam Item NDE Number Categ Number Component Component Type Exam 505060 F-A F1.30R AFU-14 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: NO ID TAG ON STRUT.

505080 F-A F1.30R AFU-16 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3$ NO RECORDABLE INDICATIONS ACCEPTABLE. CGL S/N N633 N-EG-13312-81-377H.

505110 F-A F1.30R AFU-19 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. C&L N-EG-13312-81-3771.

505120 F-A F1.30R AFU-20 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

505170 F-A F1.30R AFU-25 OE VT-3 U-BOLT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

505180 F-A F1.30R AFU-26 OE VT-3 RIGID HANGER (NRC 50%)

95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE.

39

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6.Commercial Service Date ~Jul 1970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT.

C14.- AUX. FW PUMPS DISCH - ZNTERMED. BLDG. (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 505190 F-A F1.30R AFU-27 OE VT-3 RIGID RESTRAINT 95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-121. VT-3s NO RECORDABLE INDICATIONS 6 ZNSZGNZFZCANTf FILLET WELDS TO EXISTING 12WF53 ARE 5/16" ACCEPTABLE.

505200 F-A F1.30R AFU-28 OE VT-3 RIGID HANGER (NRC 50%) VT-3 95 -VT-3: OWNER ELECTED EXAM REJ: PIPE SUPPORT HAS APPROXIMATELY 1/2" PLAY 6 IS FREE TO MOYEN NOT SERVICE INDUCED. NCR94-121 GENERATED. VT-3: RE-EXAMf NO RECORDABLE INDICATIONS ACCEPTABLE.

505210 F-A F1.30R AFU-29 OE VT-3 GUIDE (NRC 50%)

95 -OWNER ELECTED EXPANDED EXAM FOR NCR94-121 VT-3: NO RECORDABLE INDICATIONS 6 ZNSZGNZFZCANTf 1/4" FILLET WELDS WERE >1/4 < 5/16 6 3/16 FILLET WELDS WERE >3/16 < 1/4 5/16" FILLET WELDS WERE >5/16" < 3/8" ACCEPTABLE 505230 D-B D2.20 AFU-100 (ZA) VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 505235 F-A F1.30R AFU-100 OE VT-3 GUIDE (ZA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE OTHER: ALL SHIMS NOTED ARE IN ADDITION TO DRAWINGS. THE 7/8" SHZMS HAVE

'/16" FILLER WELDS AND THE 1/4" SHIM HAS A 1/8" FILLET WELD SHIM SPECIFICATIONS ARE UNKNOWN.

40

Ra E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT ~ s C14. AUX. FW PUMPS DISCH - INTERMED. BLDG. (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 505360 F-A F1.30R AFU-38 OE VT-3 GUIDE (NRC 50%)

95 -VT-3 NO RECORDABLE INDICATIONS 6 INSIGNIFICANTS SHIM USED ON BOTTOM OF PIPE 6 IS WELDED TO ITEM P2 - ACCEPTABLE 505370 F-A F1.30R AFU-39 OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

BDS 410 F-A F1.30R AFU-43 VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE. CGL S/N 633, N-EG-13312-81-377J.

505520 F-A F1.30R AFU-54 OE VT-3 RIGID RESTRAINT (NRC 50't )

95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE. S/N N6336 N-EG-13312-81-348-33.

505560 F-A F1.30R AFU-106 OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

505580 D-B D2.40 AFU-108 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE

Re Ee GINNA NUCLEAR POWER PLANT Inservtce Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 145 9

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197C 6.National Board Number for Unit ~NA ATTACHMENT I CLAS S 3 COMPONENTS CONT ~

C14. AUX. FW PUMPS DISCH INTERMED. BLDG. (Cont. )

Summary Exam Item NDE Number Categ Number Component Component Type Exam 505585 F-A F1.30V AFU-108 OE VT-3 VARIABLE SPRING (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. 136 DEG. F , SETTING =

N-EG-13312-82-296.

1.45 = 104 g'S C&L TYPE B SIZE lf ID/

C15 ~ TURB AUX FW PUMP DISCHARGE DRAWINGS: C-1 e Summary Exam Number 505612 Categ F-A Item Number F1.30R Component AFU-87 GUIDE (NRC 50%)

Component Type OE NDE Exam VT-3 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

C16 ~ AUX'W PUMPS DISCH INTERMED ~ BLDG'RAWINGS: C-1 Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 505640 F-A F1.30R AFU-64 OE VT-3 GUIDE (NRC 50't) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE:

DISTANCE BETWEEN PIPE & GUIDE NORTH SIDE =0"f SOUTH, EAST

& WEST < 1/16" & NOT 0".

505680 F-A F1.30R AFU-68 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. C&L S/N 6339 N-EG-13312-91-348-40.

42

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT ~ t C16. AUX. FW PUMPS DISCH>> INTERMED. BLDG. (Cont.)

Summary. Exam Item Number Categ Number Component Component Type Exam 505690 F-A F1.30R AFU-69 OE GUIDE (NRC 50t) 95 -VT-3: NO RECORDABLE INDICATIONS - ACCEPTABLE. NOTE:

DISTANCE BETWEEN PIPE & GUIDE IS AS FOLLOWS NORTH SIDE 1/8", SOUTH SIDE = Oms EAST 6 WEST SIDES = 1/16".

505710 F-A F1.30R AFU-71 OE VT-3 RIGID RESTRAINT (NRC 50%) ~

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

505760 F-A F1.30V AFU-76 OE VT-3 VARIABLE SPRING (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. 84 DEG. F., SETTING 0.85 = 2451'S. ID NEG 13312 82 306B, TYPE B.

505840 D-B D2.20 AFU-93 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE.

505845 F-A F1.30R AFU-93 OE VT-3 GUIDE (IA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE. OTHER: ALL SHIMS NOTED ARE IN ADDITION TO DRAWINGS, THE 7/8" SHIMS HAVE 3/16" FILLET WELDS AND THE 1/4" SHIM HAS A 1/8" FILLET WELD.

SHIM SPECIFICATIONS ARE UNKNOWN.

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT ~ s C16. AUX. FW PUMPS DISCH - INTERMED. BLDG. (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 505940 F-A F1.30R AFU-85 OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE NOTE:

LIMITATION, GROUT CONCEALING PART OF COLUMN TO BEAM WELD 506040 F-A F1.30R AFU-120 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. S/N N663.

ID P N-EG-13312-81-345-8.

C17 ~ STANDBY AUX FW FRM PEN 1 1 9 AUX FW PUMP C DRAWINGS: C-21 Summary Exam Item NDE Number Categ Number Component Component Type Exam 507240 F-A F1.30R AFU-261 (AFW-74) OE VT-3 U-BOLT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

507250 F-A F1.30R AFU-262 (AFW-75) OE VT-3 U-BOLT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

507290 F-A F1.30R AFU-266 (AFW-79) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

507350 F-A F1.30R AFU-272 (AFW-85) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D B.National Board Number for Unit N~A ATTACHMENT I CLASS 3 COMPONENTS CONT ~

C17. STANDBY AUX FW FRM PEN 119 - AUX FW PUMP C (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 507390 F-A F1.30R AFU-164 (AFW-89) OE VT-3 GUIDE (NRC 50%,)

95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE.

507445 F-A F1.30R AFU-153 (AFW-120) OE VT-3 GUIDE (NRC 50%)

95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE 507500 F-A F1.30R AFU-159 (AFW-98) OE VT-3 GUIDE (NRC 50%)

95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: SHIM PLATE BETWEEN ITEM gl 6 ZTEM f2 ZS TACKED.

507520 F-A F1.30R AFU-158 (AFW-100) OE VT-3 GUIDE (NRC 50%)

95 -VT-3! NO RECORDABLE INDICATIONS - ACCEPTABLE.

507560 F-A F1.30R AFU-196 (AFW-104) OE VT-3 GUIDE (NRC 50t) 95 -VT-3$ NO RECORDABLE INDICATIONS ACCEPTABLE.

45

Re E ~ GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Rec[.) ~N A S.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT t C18. STANDBY AUX FW FRM PEN 123 AUX FW PUMP D DRAWINGS'-25 Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 508145 F-A F1.30R AFU-231 (AFW-51) OE VT-3 GUIDE (IA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE BASELINE EXAM PERFORMED AFTER RE-INSTALLATION OF SUPPORT, NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: DAMAGE IDENTIFIED ON PIPE ADJACENT SUPPORTS NCR95 025 GENERATEDS AREA CONDITIONED, SEE PACKAGE.

508146 D-B D2.20 AFU-231 (AFW-51) (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

508147 F-A F1.30R AFU-232 (NEW) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. INSIG: NO SHIM ITEM S4 ACCEPTABLE.

508150 F-A F1.30R AFU-234 (NEW) OE VT-3 U-BOLT (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE. CGL ID N-EG-13312-81-377N.

508170 F-A F1.30R AFU-237 (AFW-55) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

508260 .F-A F1.30R AFU-246 (AFW-64) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certi.ficate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT. t C18. STANDBY AUX FW FRM PEN 123 - AUX FW PUMP D (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 508330 F-A Fl 30R AFU-253 (AFW-71) OE VT-3 RIGID HANGER (NRC 50't) 95 -VT-3s NO RECORDABLE INDICATIONS ACCEPTABLE.

508360 F-A F1.30R AFU-179 (AFW-119) OE VT-3 GUIDE (NRC 50'4) 95 -VT-3s NO RECORDABLE INDICATIONS ACCEPTABLE OTHER:

NOTE TOLERANCES BETWEEN PIPE AND SUPPORT [SETTINGS PER DRAWING IN ()] NORTH 0 (1/8 )6 EAST 1/8 (1/16 )6 SOUTH 3/16 (0 )6 WEST 0 (1/32 ) ~

508390 F-A F1.30R AFU-182 (AFW-112) OE GUIDE (NRC 50IL) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE OTHER:

NOTE, NO SHIM PLATE ITEM g9.

508435 F-A F1.30R AFU-187 (AFW-121) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE 508450 F-A F1.30R AFU-189 ('AFW-106) OE VT-3 GUIDE (NRC 50%)

95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE OTHER:

NOTE, ITEM f7 SHIM PLATE HAS FULL LENGTH FILLET WELD, NOT TACK WELD.

47

0 Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.)'%~A B.commercial Service Date ~Jul 197D 6.National Board Numtec for Unit jNA ATTACHMENT I CLASS 3 COMPONENTS CONT s C19 ~ TURBINE DRIVEN AUX ~ FW PUMP SUCTION DRAWINGS: C-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508500 F-A F1.30R AFU-1 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3! NO RECORDABLE INDICATIONS & INSIGNIFICANTf PAINT IS STARTING TO BLISTER DUE TO LIGHT CORROSION ON ITEMS P4 &

PS ACCEPTABLE C&L ID'S N-EG-13312-82-311-I, N-EG-13312-82-311-J.

508510 F-A F1.30R AFU-2 OE VT-3 RIGID RESTRAINT (NRC 50t) 95 -VT-3: NO RECORDABLE INDICATIONS & OTHERf 4" LINE HAS 2 WELDED LUGS AT 0 & 180 DEG. TO RIGID RESTRAINT. S/N N633, N-EG-13312-81-348-2 ACCEPTABLE.

C20. SW SUPPLY TO SAFW PUMP C DRAWINGS! C-28 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508815 D-B D2.20 SWU-590 (SW-122) (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

508817 F-A F1.30R SWU-590 (SW-122) OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT a

Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 199D B.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT. t C21 ~ MOTOR DRIVEN AUX, FW PUMP SUCTION DRAWINGS: C-33 Summary Exam Item Number Categ Number Component Component Type Exam 508600 F-A F1.30R SWU-284 OE VT-3 RIGID RESTRAINT (NRC 50%)

95 -VT-3! NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: CGLf N-EG-13312-81-178B, NO SIZE LABELED'22.

SW SUPPLY TO SAFW PUMP D DRAWINGS: C-28 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508930 D-B D2.20 SWU-514 (SW-142) (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

508933 F-A F1.30R SWU-514 (SW-142) ASME VT-3 GUIDE (IA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE. OTHER ITEM P2 ANGLE IS IN CONTACT WITH CONDUIT AT WALL. USE-AS-IS PER ENGINEERING.

C23 ~ STANDBY AUX. FW, SW SUPPLY TO SAFW PUMP D DRAWINGS: C-28 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508960 F-A F1.30R SWU-522 (SW-140) OE VT-3 GUIDE 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Per'iod, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 C.ommercial Service Date ~Jul 197C S.National Board Number for Unit ~NA ATTACHMENT I.

CLASS 3 COMPONENTS CONT. t C24 ~ MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE DRAWINGS'-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 509020 D-B D2.20 MSU-64 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3! NO RECORDABLES INSIGNIFICANT 6 OTHERS TOP LUG BENT 5 DEG'.f 3/16" CLEARANCE, SOUTH LUG 1.8" CLEARANCE. BOTTOM TIGHT TO g7f NORTH TIGHT TO g5. DCR GENERATED TO UPDATE DRAWING FOR 2 ADDITIONAL LUGS ACCEPTABLE 509025 F-A F1.30R MSU-64 OE VT-3 RIGID RESTRAINT (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE C25. MAIN STEAM LOOP A TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 509160 D-B D2.30 MSU-78 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: TEMP. 76 DEG. 'F.; SETTING 3 1/8". NO RECORDABLE INDICATIONS ACCEPTABLE.

509165 F-A F1.308 MSU-78 OE VT-3 MECHANICAL SNUBBER (IA) 95 -VT-3: TEMP. 76 DEG. F.f SETTING 3 1/8", NO RECORDABLE INDICATIONS ACCEPTABLE.

50

Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report, 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commercial Service Date ~Ju1 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLAS S 3 COMPONENTS CONT .  !

C26e AUX FW PUMP A FLOW CONTROL BYPASS DRAWINGS: C-1G Summary Exam Item NDE Number Categ Number Component Component Type Exam 510035 D-B D2.20 AFU-60 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

510040 F-A F1. 30R AFU-60 OE VT-3 GUIDE (IA) 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

C27. AUX FW PUMP B FLOW CONTROL BYPASS DRAWINGS: C-1H Summary Exam Item NDE Number Categ Number Component Component Type Exam 510065 D-B D2.20 AFU-128 (IA) ASME VT-3 INTEGRAL ATTACHMENT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

510070 F-A F1.30R AFU-128 OE VT-3 GUIDE (IA) 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE.

51

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 Commercial Service Date ~Jul

~ 1970 S.National Board Number for Unit ~NB ATTACHMENT I D. HIGH ENERGY COMPONENTS t Dl>> MAIN STEAM LOOP A OUTSIDE CV DRAWINGS t B-9A Summary Exam Item Number Categ Number Component Component Type Exam 200020 HE-DB Ll AUG VT-1 REDUCER-TO-TEE MT RT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS. RT: NO RECORDABLE

& INSIGNIFICANTS POROSITY & SLAG. NO APPARENT CHANGE SINCE t

LAST EXAMINATION ACCEPTABLE D2 ~ MAIN STEAM OUTSIDE CV DRAWINGS: HE-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200025 HE-DB L2 AUG VT-1 TEE-TO-PIPE MT RT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS ACCEPTABLE- RT-NO RECORDABLE & INSIGNIFICANTS SLAGS POROSITYS WASHOUTS NO CHANGE SINCE LAST EXAMINATION - ACCEPTABLE D3 ~ MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10 Summary Exam Item Number Categ Number Component Component Type Exam 200045 HE-DB Pl AUG VT-1 REDUCER-TO-TEE RT MT 95 -MT: NO RECORDABLE, LIM: L=23"-35" DUE TO SUPPORT 90t.

VT-1: NO RECORDABLE & INSIGNIFICANT L=56 1/2", W=ll 1/2" UP, 2 INDICATIONS FROM LINE UP LUG-1/8 X2 1/2X 1/64. RT: NO RECORDABLE & INSIGS POROSITYS PEEN MARKSS WASHOUTS NO CHANGE-ACCEPTABLE. a 52

R. E. GINNA NUCLEAR POWER PLANT

/

Inservice Inspection Report 1990-1999 Interval, S'econd Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I HIGH ENERGY COMPONENTS CONT D4, FEEDWATER TURBINE BUILDING DRAWINGS: HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200050 HE-DB M3 AUG VT-1 PIPE-TO-TEE UT MT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS. UT: NO RECORDABLE

& GEOMETRYS COUNTERBORE, CROWN & ROOT GEOMETRY. ZERO DEGREE SCAN PERFORMED IN '92., > 90% COVERAGE ACCEPTABLE.

D5 ~ FEEDWATER LOOP A OUTSIDE CV DRAWINGS HE-5 Summary Exam Item Number Categ Number Component Component Type Exam 200055 HE-DB M4 AUG VT-1 TEE-TO-REDUCER ~ UT MT 95 -VT-1 & MT; NO RECORDABLE INDICATIONS. UT NO RECORDABLE

& GEOMETRYS COUNTERBORE & ROOT GEOMETRY, > 90't COVERAGE ACCEPTABLE.'6.

FEEDWATER LOOP B OUTSIDE CV DRAWINGS'E-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200075 HE-DB Al AUG VT-1 TEE-TO-REDUCER UT MT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS. UTs NO RECORDABLE, INSIGNIFICANT & GEOMETRYS COUNTERBORE & SLAG INCLUSION, 90't COVERAGE ACHIEVED ACCEPTABLE.

53

Ra E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I HIGH ENERGY COMPONENTS CONT D7e MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200160 HE-CB L AUG VT-1 3519 VALVE-TO-REDUCER RT MT 95 -VT-1 & MT: NO RECORDABLE INDICATIONS. RT: NO RECORDABLES" INSIGNIFICANT & OTHER GOUGE IN BASE METAL AT 71"f POROSITY NO CHANGE SINCE LAST EXAM ACCEPTABLE.

D8 ~ MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type ~ Exam 200220 HE-CB P AUG VT-1 3518 VALVE-TO-REDUCER RT MT 95 -MT: NO RECORDABLE INDICATIONS. VT-1: NO RECORDABLE &

INSIGNIFICANTS LINE-UP LUG. RT: NO RECORDABLE &6 INSIGNIFICANT; POROSITY, SLAG, BASE METAL INDICATION WHERE TEMPORARY ATTACHMENT LOCATED 9 44". NO CHANGE SINCE LAST EXAM ACCEPTABLE.

D9 ~ MAIN STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200280 HE-CB Cl AUG VT-1 ELBOW-TO-PIPE UT MT 95 -MT: NO RECORDABLE. VT-1: INSZGNIFZCANT; MINOR PITTZNG ON PIPE < 1/32 ~ UT NO RECORDABLE & GEOMETRYs ROOTS COUNTERBORE, WELD CROWN GEOMETRY/REDIRECTED BEAM. > 90%

COVERAGE OBTAINED ACCEPTABLE.

54

IO R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection. Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

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 HIGH ENERGY COMPONENTS CONT.

D9. MAIN STEAM TURBINE BUILDING (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 200285 HE-CB D AUG VT-1 PIPE-TO-ELBOW UT MT 95 -MT: NO RECORDABLE. VT-1: INSIGNIFICANT MINOR PITTING I

1 /32 ON P PE ~ UT NO RECORDABLE 9 GEOMETRY 6 OTHERS ROOTS COUNTERBORE 9 WELD CROWN 5 MODE CONVERS ION 5 6 SLAG INCLUSION ~

90% COVERAGE ACCEPTABLE.

D10. FEEDWATER TURBINE BUILDING DRAWINGS: HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200320 HE-CB M2 AUG VT-1 ELBOW-TO-PIPE UT MT 95 -VT-1 6 MT:,NO RECORDABLE INDICATIONS. UT: NO RECORDABLES GEOMETRY 6 OTHERS'ROWN 6( ROOT GEOMETRY, COUNTERBORE 6 MODE CONVERSION COUNTERBORE, ) 90't COVERAGE ACHIEVED ACCEPTABLE.

Dlla FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-11 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200455 HE-CB Z3 AUG VT-1 PIPE-TO-ELBOW RT MT 95 -VT-1, MT 6 RT: NO RECORDABLE INDICATIONS ACCEPTABLE.

55

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East ve. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.Commercial Service Date ~Jul 197C S.National Board Number for Unit ~NA.

ATTACHMENT I HIGH ENERGY COMPONENTS CONT. t Dll. FEEDWATER LOOP A OUTSIDE CV (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 200460 HE-CB Z4 AUG VT-1 ELBOW-TO-PIPE UT MT 95 -VT-1 6 MT: NO RECORDABLE INDICATIONS. UTs NO RECORDABLE GEOMETRY: ROOT, COUNTERBORE, ROUGH ROOT, SPOT INDICATION AT WELD CROWN, ) 90't COVERAGE ACCEPTABLE D12. FEEDWATER LOOP B OUTSIDE CV DRAWINGS: B-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200575 HE-CB Ol AUG VT-1 ELBOW-TO-PIPE RT MT 95 -VT-l, MT 6f RT: NO RECORDABLE INDICATIONS ACCEPTABLE.

200580 HE-CB ---- P AUG VT-1 PIPE-TO-ELBOW RT MT 95 -MT: NO RECORDABLE INDICATIONS. VT-1 NO RECORDABLE 6f ZNSZGNZFZCANTS MINOR CORROSION. RT: NO RECORDABLE 6 ZNSZGNZFZCANTS POROSITY & SLAG, NO APPARENT CHANGE SINCE LAST EXAMINATION ACCEPTABLE.

56

R. E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 6 Co.mmercial Service Date ~Jul 197C S.National Board Number for Unit N~A ATTACHMENT I HIGH ENERGY COMPONENTS CONT ~

D13 ~ MAIN STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Exam Item NDE Number Categ Number Component Component Type Exam 201420 HE-CS *F1.20V MS-45 (S21) OE VT-3 VARIABLE SPRING 95 -VT-3: TEMP. 68 DEG. F., SETTING 1/2" = 4825 if'Ss NO RECORDABLE INDICATIONS ACCEPTABLE. BASELINE, REMOVED FOR ACCESS OF HE WELD C1.

201440 HE-CS *F1.20V MS-46 (S22) OE VT-3 VARIABLE SPRING (IA)

I 95 VT 3 TEMP ~ 7 1 DEG ~ F ~ s SETTING 1/2 f VS 2 S ZE 17 6 NO RECORDABLE INDICATIONS ACCEPTABLE. BASELINE, REMOVE FOR ACCESS OF HE WELD D.

201441 HE-IA *C3.20 MS-46 (S22) (ZA) OE MT INTEGRAL ATTACHMENT 95 -MT: NO RECORDABLE INDICATIONS IN LIMITED EXAM. 7 1/2" OF WELD IN BETWEEN ZA (BOTH SIDE) NOT ACCESSIBLE FOR MT VISUAL PERFORMED APPROX 90% INSPECTED ACCEPTABLE.

D14. FEEDWATER LOOP B OUTSIDE CV DRAWINGSe B-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201860 HE-CS *F1.20S FWU-38 OE VT-3 MECHANICAL SNUBBER 95 -VT-3: BASELINE EXAM AFTER RE-INSTALLATION TEMP. 68 DEG.

F.f SETTING 3 1/2". NO RECORDABLE INDICATIONS ACCEPTABLE.

57

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 197D B.National Board Number for Unit ~NA ATTACHMENT I E. LEAKAGE TESTING E1 ~ LEAKAGE EXAMINATIONS CLASS 1 f 2 f 3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 411000 B-P IWB5221 PT-7 LEAKAGE TEST OF ASME VT-2 REACTOR COOLANT SYSTEM 95 -VT-2: TEST SATISFACTORYf DEFICIENCIES CORRECTED DURING TESTg SEE EXAM SHEET FOR DETAILS ACCEPTABLE.

t 411400 HE-LK -- MS HIGH ENERGY AUG 95 -VT-2: NO RECORDABLE INDICATIONS, ACCEPTABLE.

411600 C-H IWC5221 FW OUTSIDE CONTAINMENT ASME VT-2 95 -VT-2: NO RECORDABLE INDICATIONS -TEST ACCEPTABLE.

411700 D-B IWD5221 AUX FW "A" PUMP ASME VT-2 95 -VT-2: NO RECORDABLE INDICATIONS, ACCEPTABLE.

412100 D-B IWD5221 STANDBY AUXILIARY ASME VT-2 FEEDWATER PUMP "D" 95 -VT-29 NO RECORDABLE & INSIGNIFICANT PACKING LEAK ON V9708B & V9704B. GASKET LEAK BETWEEN V9714B & V9715B.

COMPLETE TEST PERFORMED IN 2 PARTS TEST SATISFACTORY.

412500 C-H IWC5221 SAFETY INJECTION "A" ASME VT-2 PUMP IN/OUT CONTAINMENT 95 -VT-2: NO RECORDABLE & OTHER) BORIC ACID RESIDUE ON VALVES 828A, 828B & 12400. PACKING/STEM DRY. FLANGE AT FE-294 AT INTERFACE, RANDOM 360 DEGREES TO BE DECONNED &

CHECKED ON PT-8.8. TEST SATISFACTORY.

58

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I LEAKAGE TESTING . CONT.

El. LEAKAGE EXAMINATIONS CLASS 1,2,3 (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 413000 C-H IWC5221 CONTAINMENT SPRAY ASME VT-2 A PUMP DISCHARGE 95 -VT-2: NO RECORDABLE 6 INSIGNIFICANTs DRIED BORIC ACID ON V831As V857Bs V857CS V893A & V893B ~ PACKING LEAK 6 DRY BORIC ACID RESIDUE ON V862A. BODY TO BONNET HAS BORIC ACID RESIDUE AT BOTTOM OF JOINT. ACCEPTABLE.

413100 C-H IWC5221 CONTAINMENT SPRAY ASME VT-2 B PUMP DISCHARGE 95 -VT-2: NO RECORDABLE 6 INSIGNZFICANT PACKING LEAK BORIC ACID RESIDUE ON V860C 6 V869A. SWAGE-LOK TEE UPSTREAM OF LT-921 HAS BORIC ACID RESIDUE. ACCEPTABLE.

413150 C-H IWC5221 SPRAY ADDITIVE ASME VT-2 NOAH TANK 95 -VT-2: NO RECORDABLE INDICATIONS, ACCEPTABLE 413600 D-B IWD5221 AUX COOLING INSIDE ASME VT-2 CONTAINMENT 95 -VT-2: NO RECORDABLE 6 INSIGNIFICANT V754B HAS PACKING DRY RESIDUE. ACCEPTABLE.

413700 D-B IWD5221 AUX COOLING OUTSIDE ASME VT-2 CONTAINMENT 95 -VT-2: -TEST SATISFACTORY, SEE EXAM SHEET FOR DETAILS.

NOTE: WASTE EVAPORATOR ISOLATED, NOT BEING USED.

ACCEPTABLE.

59

e 1990-1999 R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

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 LEAKAGE TESTING CONT ~ t El. LEAKAGE EXAMINATIONS CLASS 1,2,3 (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 414000 D-A IWD5221 SERVICE WATER ASME VT-2 OUTSIDE CONTAINMENT 95 -VT-2 NO RECORDABLE 6 INSIGNIFICANT "A" LOOP BURIED PIPE EXAMINED USING ID PIPE CRAWLER. ID GOOD CONDITION-NO LEAK PATHS OBSERVED. REMOVED RUST ON PACKING GLAND ON V4627.

A Ec D SW PUMP BOUNDARIES PERFORMED -ACCEPT. PARTIAL EXAM.

414100 D-A IWD5221 SERVICE WATER TO ASME VT-2 AUX FW PUMP "A" 95 -VT-2t NO RECORDABLE INDZCATIONS. ACCEPTABLE.

414600 C-H IWC5221 CHARGING 6 SEAL WATER ASME VT-2 FROM PUMPS (IN/OUT CV) 95 -VT-2t NO RECORDABLE 6 INSIGNIFICANTS'ERFORMED DURING PT7 ~ PACKING GLAND BORON RESIDUE V281AS V2875 V277AS V291 V288. BODY-BORON RESIDUE PIC-183 6 BODY TO BONNET ON V357".

PACKZNG LEAK ON V392B, FIXED DURING TEST. ALL DECONNED-WILL BE RECHECKED.

415500 D-B IWD5221 SPENT FUEL POOL ASME VT-2 COOLING-A 95 -VT-2t NO RECORDABLE & INSIGNIFICANTS CHECK VALVE V8655 HAS BODY TO BONNET LEAK WITH BORIC ACID RESIDUE. VT-3 ON BOLTING WHEN VALVE ID OPENED, WORK REQUEST WRITTEN ACCEPTABLE 415550 D-B IWD5221 SPENT FUEL POOL ASME VT-2 COOLING-B 95 -VT-2t NO RECORDABLE 6 INSIGNIFICANTS FULL EXAMINATION BOUNDARY HAS BEEN COMPLETED, TEST SATISFACTORY. SEE EXAMINATION RECORD FOR DETAILS.

60

Re E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.Commercial Service Date ~Jul 1979 S.National Board Number for Unit ~NA ATTACHMENT I F~ SNUBBER PROGRAM COMPONENTS g Flu STEAM GENERATOR B DRAWINGS: A-7F Summary Exam Item NDE Number Categ Number Component Component Type Exam 600120 SN-VT SGB-3 AUG VT-3 HYDRAULIC SNUBBER 95 VT 3 NO RECORDABLE INDICATIONS 5 TEMP 67 DEG F 5 SETTING 39 3/8", S/N AH-2 ACCEPTABLE.

600121 SN-FT SGB-3 AUG FT HYDRAULIC SNUBBER 9P -FT- OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOg 19404251.

F2 ~ AUX ~ FW PUMPS DISCH INTERMED ~ BLDG ~ DRAWINGS: C-1E Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 600240 SN-VT AFU-34 AUG VT-3 MECHANICAL SNUBBER 95 -VT-3: TEMP. 70 DEG. F., SETTING 2 7/8", S/N 14448. NO RECORDABLE INDICATIONS ACCEPTABLE.

600241 SN-FT AFU-34 AUG FT MECHANICAL SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

SNUBBER DEGRADED AND REPLACED. WOP 19404236.

600280 SN-VT AFU-75 AUG VT-3 MECHANICAL SNUBBER 95 -VT-3: TEMP. 73 DEG. F., SETTING 2 1/8", S/N 20924. NO RECORDABLE INDICATIONS ACCEPTABLE 61

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995) a

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~

F2 ~ AUX. FW PUMPS DISCH - INTERMED. BLDG. (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 600281 SN-FT AFU-75 AUG FT MECHANICAL SNUBBER 95 -FT! OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOP 19404237.

600400 SN-VT AFU-123 AUG VT-3 MECHANICAL SNUBBER 0

95 VT 3 TEMP ~ 73 DEG ~ F 5 SETTING 2 5 S/N 22485 ~ NO RECORDABLE & INSIGNIFICANTS SNUBBER HAS MOVEMENT IN BOTH DIRECTIONS - ACCEPTABLE.

600401 SN-FT AFU-123 AUG FT MECHANICAL SNUBBER 95 -FT! OTHER FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

SNUBBER DEGRADED AND REPLACED WOg 19404238.

F3 ~ STEAM GENERATOR B BLOWDOWN LINE DRAWINGS: B-31 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600460 SN-VT BDU-16 AUG VT-3 MECHANICAL SNUBBER 95 -VT-3! BASELINE EXAM AFTER REINSTALLATION DUE TO BLOWDOWN REPLACEMENT. TEMP. 68 DEG. F., SETTING 2 7/Bms S/N 10182.

SNUBBER INSTALLED 180 DEGREES FROM DRAWING, NO RECORDABLE INDICATIONS ACCEPTABLE.

600461 SN-FT BDU-16 AUG FT MECHANICAL SNUBBER 95 -FT! OTHER FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WON 19404239.

62

R. E ~ GINNA NUCLEAR POWER PLANT Znservice Inspects.on Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 197D 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT F4. 2" CVCS RELIEF LINE TO PRT DRAWINGSa B-32 Summary Exam Item Number Categ Number Component Component. Type Exam 600940 SN-VT CVU-80 AUG VT-3.

MECHANICAL SNUBBER 95 VT 3 TEMP ~ 74 DEG ~ F 9 SETTING 1 1/2 f S/N 235189 NO RECORDABLE INDICATIONS ACCEPTABLE 600941 SN-FT CVU-80 AUG FT MECHANICAL SNUBBER 95 -FT: OTHER FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

REPLACED SNUBBER DEGRADED, WOP 19404240.

F5 ~ CVCS LETDOWN LINE TO MZX BED DEMZN DRAWINGS: B-36 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601080 SN-VT CVU-372 AUG VT-3 MECHANICAL SNUBBER 95 VT 3 TEMP ~ f 69 DEG F f SETTING 3/4 S/N 9478 ~ NO RECORDABLE INDICATIONS - ACCEPTABLE.

9 601081 SN-FT CVU-372 AUG FT MECHANICAL SNUBBER 95 -FT: OTHER FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

SNUBBER DEGRADED AND REPLACED, WOÃ 19404241 63

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F6. FEEDWATER LOOP A INSIDE CV DRAWINGS'-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601110 SN-VT FWU-5 AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: TEMP 69 DEG F SETTING 1/2 EXT 3 f S/N

~ ~ ~ 6 2500-10-152. NO RECORDABLE INDICATIONS ACCEPTABLE.

601111 SN-FT FWU-5 AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOP 19404249.

F7. FEEDWATER LOOP B OUTSIDE CV DRAWINGS'-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601270 SN-VT FWU-44 AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: BASELINE EXAM AFTER REINSTALLATION. TEMP. 72 DEG F., S/N G43864-02-20, SETTING 3 15/16me SPECIFICATION STATES 3". NCR95-045 GENERATED, NOT SERVICE INDUCED. DISPOSITIONED USE-AS-IS PER ENGINEERING. NO RECORDABLE, OTHER 6 REJECT

-ACCEPTABLE.

601271 SN-FT FWU-44 AUG FT HYDRAULIC SNUBBER 95 -FT! OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOI.

19404250.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periodf Third Outage (1995)

1. Owner Rochester Gas 67 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 Co.mmercial Service Date ~cul 197D S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

FS ~ MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10A Summary Exam Item NDE Number Categ Number Component 'Component Type Exam 601390 SN-VT MSU-12 AUG VT-3 MECHANICAL SNUBBER 95 -VT-3s TEMP 59 DEG. F , SETTING 3 1/4", S/N 9400. NO RECORDABLE INDICATIONS ACCEPTABLE.

601391 SN-FT MSU-12 AUG FT MECHANICAL SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOE 19404244.

601429 SN-VT ---- MSU-18 (NORTH) AUG VT-3 MECHANICAL SNUBBER 95 -VT-3: TEMP 59 DEG F., SETTING 2 1/4", S/N 7478. NO RECORDABLE INDICATIONS ACCEPTABLE.

601430 SN-VT ---- MSU-18 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 95 VT 3 TEMP ~ 59 DEG ~ F f SETTING 2 1/4 5 S/N 7 197 ~ NO RECORDABLE INDICATIONS ACCEPTABLE.

601431 SN-FT MSU-18 (NORTH) AUG FT MECHANICAL SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. WOP 19404246.

601432 SN-FT ---- MSU-18 (SOUTH) AUG FT MECHANICAL SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER FAILED. SNUBBER WO 19404245. REQUIRED TO TEST MSU-19 NORTH REPLACED NCR95-017, WO 19501218. FUNCTIONAL TEST OF SNUBBER - PER RETEST IN 1996.

65

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periods Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commeccial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~ t F8. MAIN STEAM LOOP B OUTSIDE CV (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 601439 SN-VT MSU-19 (NORTH) AUG VT-3 MECHANICAL SNUBBER 95 -VT-3s BASELINE FOR REINSTALLATION, FT EXPANDED TEST TO RESOLVE NCR95-017 (MSU-18). TEMP. 55 DEG. F f SETTING 3"f S/N 9369. NO RECORDABLE INDICATIONS ACCEPTABLE 601441 SN-FT ---- MSU-19 (NORTH) AUG FT MECHANICAL SNUBBER 95 -FT$ OTHER FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF MSU-18 SOUTH ACCEPTABLE. WO 19501218 6 NCR95-017. EXPANDED EXAM.

F9 MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601550 SN-VT MSU-44 AUG VT-3 MECHANICAL SNUBBER 95 -VT-3s TEMP. 76 DEG. F., SETTING 3 1/2", S/N 1468, NO RECORDABLE INDICATIONS ACCEPTABLE.

601551 SN-FT MSU-44 AUG FT MECHANICAL SNUBBER 95 -FTs OTHERS FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

WOP19404243.

0 66

R. E, GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1976 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~

F10 e MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601570 SN-VT MSU-57 AUG VT-3 MECHANICAL SNUBBER 95 VT 3 TEMP 74 DEG F s SETTING 3 RECORDABLE INDICATIONS ACCEPTABLE.

1/4 s S/N 27182 'O 601571 SN-FT MSU-57 AUG FT MECHANICAL SNUBBER 95 -FT: OTHERN TEST FAILED, SNUBBER REPLACED UNDER REQUIRED TO TEST MSU-60 PER NCR95-039, WO¹'9404247.

WO¹19501414. FUNCTIONAL TEST OF SNUBBER ACCEPTABLE. RETEST IN 1996.

Fll ~ MAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601590 SN-VT MSU-60 AUG VT-3 MECHANICAL SNUBBER 95 VT 3 BASELINE EXAM DUE TO FT TESTING EXPANSION f TEMP ~

72 DEG. Fes SETTING 3 5/8", PSA-3, 5" STROKE. NO RECORDABLE INDICATIONS ACCEPTABLE.

601591 SN-FT MSU-60 AUG FT MECHANICAL SNUBBER 95 -FT: OTHER FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF MSU-S7, EXPANDED EXAM. WO 19501414 Ec NCR95-039.

ACCEPTABLE.

67

e 1990-1999 R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 C.ommercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F12. MAIN STEAM LOOP A TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601630 SN-VT MSU-78 AUG VT-3 MECHANICAL SNUBBER 95 VT 3 TEMP ~ 76 DEG ~ F 5 SETTING 3 1/8 5 S/N 85765 PSA-10, 6" STROKE. NO RECORDABLE INDICATIONS ACCEPTABLE-601631 SN-FT MSU-78 AUG FT MECHANICAL SNUBBER 95 -FT: OTHER( FUNCTIONAL TEST OF SNUBBER ACCEPTABLE.

WOP19404242.

F13. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD INCV DRAWINGS: C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601940 SN-VT AFU-208 (AFW-13) AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: TEMP. 63 DEG. F., SETTING 2", S/N 12907. NO RECORDABLE INDICATIONS ACCEPTABLE.

601941 SN-FT ---- AFU-208 (AFW-13) AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER 5'AILED, REPLACED SNUBBER WOI 19404248. NCR95-044 REQUIRED EXPANSION TO AFU-229, N-616 & PS-6. RETEST IN.'96 ACCEPTABLE.

68

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT t F149 STANDBY AUX FW THRU PEN 119 TO A S/G FWHD INCV DRAWINGSt C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601970 SN-VT AFU-224 (AFW-28) AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: BASELINE EXAM DUE TO FT TESTING EXPANSION. TEMP.

68 DEG ~ F f SETTING 2 1/2 f FLUID LEVEL 75'tf S/N 12905 RECORDABLE INDICATIONS ACCEPTABLE.

'O 601971 SN-FT AFU-224 (AFW-28) AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF AFU-229 -EXPANDED EXAM FAILED. WOI 19501481 NCR95-047. REPLACED SNUBBER. REQUIRED TO TEST AFU-226 PER NCR95-049 6 WOg 19501483. RETEST IN 1996.

601980 SN-VT AFU-226 (AFW-27) AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3$ BASELINE EXAM DUE TO FT TESTING EXPANSION TEMP.

67 DEG. F., SETTING 3 1/2", S/N 12401. NO RECORDABLE INDICATIONS ACCEPTABLE.

601981 SN-FT AFU-226 (AFW-27) AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERS FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF AFU-224. EXPANDED EXAM ACCEPTABLE. WOÃ 19501483 6 NCR95-049.

69

R, E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Nervice Date ~Jul 1970 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~

F15 ~ PRESS eRELIEF FM PRESS. TO RELIEF MANIFOLD DRAWINGS'-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602080 SN-VT N616 AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: BASELINE EXAM DUE TO FT TESTING EXPANSION (NCR94 034) ~ TEMP ~ 58 DEG ~ F ~ 5 SETTING 2 5/8 5 FLUID LEVEL 75%, NO RECORDABLE & OTHERN COTTER PIN ON HEAD -OK, PHR-12 SUPPORT IS WELDED TO THE WALL PLATE OF N616-NO BOLTS ACCEPTABLE.

602081 SN-FT N616 AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERf FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF AFU-208, EXPANDED EXAM ACCEPTABLE. WOE 19501446 6 NCR95-044.

F16. 3-IN. PRESSURIZER RELIEF LINE DRAWINGS: A-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602120 SN-VT -- PS-6 AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3: BASELINE EXAM DUE TO FT TESTING EXPANSION TEMP.

69 DEG F ~ 5 SETTING 3 5/8 5 S/N PD87767 1239 'EW COTTER PIN INSTALLED. NO RECORDABLE INDICATIONS ACCEPTABLE.

602121 SN-FT PS-6 AUG FT HYDRAULIC SNUBBER 95 -FT: OTHERN FUNCTZONAL TEST OF SNUBBER REQUIRED BY FAILURE OF AFU-2085 EXPANDED EXAM ACCEPTABLE. WOP 19501447 6 NCR95-044.

70

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 Co.mmercial Service Date ~cul 1970 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~

F17 STANDBY AUX FW THRU PEN 119 TO A S/G FWHD IN DRAWINGS: C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602500 SN-VT AFU-229 AUG VT-3 HYDRAULIC SNUBBER 95 -VT-3 BASELINE EXAM DUE TO FT TESTING EXPANSION TEMP 69 DEG ~ F s SETTING 2 1/4 s FLUID LEVEL 50'ts S/N 21009 RECORDABLE INDICATIONS - ACCEPTABLE

'O 602501 SN-FT AFU-229 AUG FT HYDRAULIC SNUBBER 95 -FT! OTHERS FUNCTIONAL TEST OF SNUBBER REQUIRED BY FAILURE OF AFU-208, EXPANDED EXAM FAILED. WOg 19501445 &

NCR95-044. REPLACED SNUBBER, REQUIRED TO TEST AFU-224 PER NCR95-047 & WOE 19501481. RETEST IN '96.

71

Re E ~ GINNA NUCLEAR POWER PLANT k

Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A S.commercial Service Date ~Jul 197C S.National Board Numtec for Unit ~NB ATTACHMENT I G SEISMIC SUPPORTS'l

~ RCP SEAL WATER RETURN - RELIEF TO PRT DRAWINGS: SS-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 700110 SS-CS *F1.20R CVU-125 AUG VT-3 GUIDE 6 IA 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE G29 RC PRESSURE RELIEF MANIFOLD TO PRT DRAWINGS: SS-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 700140 SS-CS *F1.20R CVU-130 AUG VT-3 RIGID HANGER 6 IA 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

G3 . MAINSTEAM DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 700490 SS-CS *F1.20R MSU-53 OE VT-3 RIGID SUPPORT 6 IA 95 -VT-3: NO RECORDABLE & INSIGNIFICANTs LOOSE PARTS, HOLD DOWN BOLTS SOUTHEAST 6 SOUTHWEST ARE LOOSE, ACCEPTABLE PER NCR 94-059. NOT SERVICE INDUCED.

700510 SS-CS *F1.20R MSU-47 OE VT-3 RIGID SUPPORT 6 IA 95 -VT-3s NO RECORDABLE 6 INSIGNIFICANTs JACKING BOLTS LOOSE, LIGHT RUST. LOOSE BOLTS ACCEPTABLE PER NCR 94-0626 NOT SERVICE INDUCED ACCEPTABLE.

72

0 1990-1999 Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, r

Third Outage (1995)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A 5 C.ommercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I SEISMIC SUPPORTS Cont.

G3. MAINSTEAM (Cont.)

Summary Exam Item NDE Number Categ Number Component Component Type Exam 700520 SS-CS *F1.20R MSU-48 OE VT-3 RIGID SUPPORT & IA 95 -VT-3s NO RECORDABLE &f INSIGNIFICANTS LOOSE JACK BOLT)

LIGHT RUST. ACCEPTABLE PER NCR 94-063. NOT SERVICE INDUCED ACCEPTABLE.

G4 ~ RESIDUAL HEAT REMOVAL DRAWINGS: B-21 Summary Exam Item NDE Number Categ Number Component Component Type Exam 700580 SS-CS *F1.20R RHU-87 OE VT-3 RIGID SUPPORT & IA 95 -VT-3$ NO RECORDABLE INDICATIONS ACCEPTABLE INSIGs CORROSION, LIGHT RUST ON BASE PLATE ACCEPTABLE.

700590 SS-CS *F1.20R RHU-90 OE VT-3 RIGID SUPPORT & IA 95 -VT-3sNO RECORDABLE INDICATIONS ACCEPTABLE. INSIGs CORROSION, RUST & CHIPPED PAINT ON BASE PLATE ACCEPTABLE.

G5e SeW. TO AC WATER CHILLERS DRAWINGS: C-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 700740 SS-CS *F1.20V SWU-364 OE VT-3 VARIABLE SPRING & IA 95 -VT-3 NO RECORDABLE INDICATIONS ACCEPTABLE. TEMP. 55 DEG. F., SETTING = 1.05 = 1456 if'Sf N-EG-13312-82-308 TYPE Bf SIZE 10 ~ NOTEs PLATE g3 TO BEAM (WSX35) WELD IS WELDED ALL AROUND ~

73

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periods I

Third Outage (1995)

1. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) ~N A B.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NA ATTACHMENT I SEISMIC SUPPORTS Cont.

G6. STANDBY AUX FEEDWATER DRAWINGS: C-28A Summary Exam Item NDE Number Categ Number Component Component Type Exam 700790 SS-CS *F1. 20R SWU-525 AUG VT-3 U-BOLT 95 -VT-3: NO RECORDABLE INDICATIONS ACCEPTABLE.

74

0 1990-1999 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

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 H~ STEAM GENERATOR EDDY ClJRRENT EXAMINATIONS-Hl ~ STEAM GENERATOR A Summary Exam Item NDE Number Categ Number Component Component Type Exam 800000 B-Q B16.20 OPEN GENERATOR TUBES ASME ET PREV. IDENT. DEGRAD ET 20 95 -ET: SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

800150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20'%OTATING RANDOM ET SAMPLE 95 -ET< SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

800200 SG-ET ---- OPEN GENERATOR TUBES OE ET 100% OF ALL UNSLEEVED ET TUBES 95 -ETs SEE 1995 EDDY CURRENT REPORT FOR DETAILS 800350 B-Q B16.20 SLEEVED GENERATOR ASME ET TUBES ET 20% ROT. RAN. SAM. ET EACH TYPE SLEEVE ET 95 -ET: SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

a 800360 -- ---- WEAR IND. COLD OE ET LEG-2ND/3RD SP R1C10-RlC12, R2C10 6 R2C12, R3C10-R3C12 95 -ET: ALL TUBES INSPECTED DURING 1994. TUBES Rlclo Ec R1C12 TUBES INSPECTED 1995. NO DETECTABLE DEFECTS IDENTIFIED ACCEPTABLE.

75

R. E ~ GINNA NUCLEAR POWER PLANT r

Inservice Inspection Report 1990-1999 Interval, Second Periods Third Outage (1995)

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester NY 14649

2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519

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 STEAM GENERATOR EDDY CURRENT EXAMINATIONS CONT ~

H2, STEAM GENERATOR B Summary Exam Item NDE Number Categ Number Component Component Type Exam 801000 B-Q B16.20 OPEN GENERATOR TUBES ASME ET PREV. IDENT. DEGRADE ET 20%

95 -ET: SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

801150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20% ROTATING RANDOM ET SAMPLE 95 -ET: SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

801200 SG-ET ---- OPEN GENERATOR TUBES OE ET 100% OF ALL UNSLEEVED ET 100% OF ALL UNSLEEVED 95 -ET! SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

801350 B-Q B16.20 SLEEVED GENERATOR ASME ET TUBES ET 20% ROT. RAN. SAM ET EACH TYPE SLEEVE ET 95 -ET: SEE 1995 EDDY CURRENT REPORT FOR DETAILS.

76

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Rcdluircd by the Provisions of thc ASMECode Section XI 1.Owner Rochester Gas g Electric Cor . Date 24 Gul 1995 89 East Ave. Rochester NY 14649 Sheet of 24

2. Plant R. E. Ginna Nuclear Power Plattt Vnit 1503 Lake Road Ontario NY 14519 Address Repair Organization P.O. No., Job No., ctc.

3. Work Performed by Type Code Symbol Stamp N A Name Authorization No. N A Expiration Date N A Address

4. Identification

d. (l of System Appllo Ol C to olo Cod (b) Applicable Edition of Section

~lp~ Edloo,~

XI Utilized for Repairs or Replaccmcnts 1986 Add d, Code Case

6. Identification of Components Repaired or Replaced and Replacement Components ASME Repaired Code National Replaced Stamped Name of Name of Manufacturer Board Other Year of (Ycs Component Manufacturer Serial No. No. Idcnti Cication Build Replaccmcnt or No)

7. Description of Work

8. Tests Conducted:(a) Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Prcssure psi Test Temp. 'F NOTE: Supplcmcntal shccts in form of lists, skctchcs, or drawings may be used, provided (I) size is 8-1/2 in. x 11 in., (2) information in items I through 6 on this rcport is included on each shcct, and (3) each sheet is numbered and the number of shccts is recorded at the top of'this form.

( ) Sce ATI'ACHMENTII" FOR APPLICABLE INFORMATION (12/82) This Form (E00030) may bc obtained from thc Order Dept., ASME,345 E. 47th St., New York, N. Y.10017 I

FORM NIS-2 (Back) 9.Remarks Applicable Manufacturer's Data Reports to bc attached CERTIFICATE OF COMPLIANCE Wc certify that the statements made in thc report are correct and this conlortns to the rules of thc ASME Code,Section XI. repair or replacement Type Code Symbol Stamp N/A I Ccrtificat of u o

' N/A Expiration Date N/A n No.

Si ned F.A.Klc acki ISI En ineer Date 24 Jul 19 95 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I,the undcrsigncd, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Ncw York and employed by HSBI/kl Cn. of Hartford CT. have inspcctcd the components dcscribcd in this Owner's Rcport during the period

/ to W 9M and state that to the best of my knowledge and bclicf, the Owner has performed examinations and taken corrective mcasurcs dcscribcd in this Owner's Rcport in accordance with the inspection plan and as required by the ASMECodc,Section XI.

By signing this certilicate neither thc Inspector nor his ernploycr makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Rcport. Furthcrmorc, ncithcr thc Inspector nor his cmploycr shall be liable in any manner for any personal injury or property damage or a loss of any kind arising froin or conncctcd with this inspection.

AWE 8. N .6ccr Commissions Inspector's Signature National Board, State, Province, and Endorsements Date 7 19 5'~

(e) See ATI'ACHMENTII" FOR APPLICABLE INFORMATION

(~') Repair, Replacement or Modification as idcntilied within "ATTACHMENTII

Ro E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owners Rochester Gas 8 Electric Co . 89E. Ave. Rochester N.Y. 14649

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: 1986 No Addenda ATTACHMENT II 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.

Replacement or If Modification; the deficiency results in a Code Repair, 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 GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995) 1 Owner! Rochester Gas & Electric Co

~ . 89E. Ave. Rochester N.Y. 14649

2. Plant! R.E. Qiana 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 A "Corrective Action Activity" may occur when a component under the RR&M 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 & Electric, Ginna Station 2 ~ Ginna Station Projects Department Nuclear Power Services Philadelphia, Pa.

3. ITI Movats 2825 Cobb International Blvd.

Kennensaw, Ga. 30144-5512 4 ~ 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, Third Outage (1995)

1. Owner! Rochester Gas 8 Electric Co . 89E. Ave. Rochester N.Y. 14649 2 Plantt R.E. Ginna Nuclear Power Plant 1503 Lake Rd.

~ Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilised 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.

1~ ASME Class: 3 ~S stem: SW GORR No.: 95-E-001 Construction Code:

Work Performed B :

ASME 1

Section III '86; B31.1 '73; B16.34 Name of Com onent: V4620, Swivel Nut Work Descri tion Remarks: An "Approved Equivalent" Replacement was initiated for the Swivel Nut associated with V4620 and to reattach the disc to the stem. This activity was controlled by WO k 19402994 & NCR 94-106. Construction Code VT examination was performed and acceptable. Upon activity conclusion, a VT-2 Leakage Examination was performed & acceptable.

2. ASME Class: 3 ~Sstem: SW GORR No.: 95-E-002 Construction Code: ASME Section Work Performed B : 2 III '86; B31.1 '73; B16.34 Name of Com onent: V4603 Relief Re uest: g 25 Work Descri tion Remarks: A Modification activity was initiated to replace V4603 with a Nozzle Check Valve and a Flange with extended length. This activity was controlled by EWR 5284B and SM 5284B.2 . Construction Code RT NDE was performed and acceptable in accordance with the specified Relief Request. A VT-2 Leakage Examination was performed and acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

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

~

Modificationss 1986 No Addenda ATTACHMENT II 3 ~ ASME Class: 2 ~S stem: MS GORR No.: 95-E-003 Construction Code: ASME Work Performed B : 1 Section III '74/'86 Name of Com onent: MSU-18 (South) Mechanical Snubber Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated for the Mechanical Snubber associated with Component Support MSU-18 (South). This activity was controlled by WO g 19404245 and NCR 95-017. Upon reinstallation, a Visual Baseline examination was performed and acceptable.

4. ASME Class: 2 ~S stem: SAEW GORR No.: 95-E-005 Construction Code:

Work Performed B :

ASME 1

Section III '74/'86 Name of Com onent: AFU-208 Hydraulic Snubber Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated for the Hydraulic Snubber associated with Component Support AFU-208. This activity was controlled by WO g 19404248 and NCR 95-044. Upon reinstallation, a Visual Baseline examination was performed and acceptable.

5. ASME Class: 2 ~S stem: MS GORR No.: 95-E-006 Construction Code: ASME Section Work Performed B : 1 III '74/'86 Name of Com onent: MSU-57 Mechanical Snubber Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated for the Mechanical Snubber associated with Component Support MSU-57. This activity was controlled by WO g 19404247 and NCR 95-039. Upon reinstallation, a Visual Baseline examination was performed and acceptable.

Ra E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995) 1 Owner! Rochester gas & Electric Co

~ . 89E. Ave. Rochester N.Y. 14649

2. Plantt R.E. Qiana Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 Applicable Edition of Section XI Utilized for Repairs, Replacements or

~

Modificationss 1986 No Addenda ATTACHMENT II

6. ASME Class: 2 ~S stem: SAFW GORR No.: 95-E-007 Construction Code: ASME Section Work Performed B : 1 III '74/'86 Name of Com onent: AFU-229 Hydraulic Snubber Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated for the Hydraulic Snubber associated with Component Support AFU-229. This activity was controlled by WO g 19501481 and NCR 95-047. Upon reinstallation, a Visual Baseline examination was performed and acceptable.

7 ~ ASME Class: 3 ~Sstem: SW GORR No.: 95-E-009 Construction Code:

Work Performed B :

ASME 1

Section III 86F B31 1

~ 73 B16 34

~

Name of Com onent: V4604 Relief Re uest: g 25 Work Descri tion Remarks: A Modification activity was initiated to replace V4604 with a Nozzle Check Valve and a Flange with extended length. This activity was controlled by EWR 5284B and SM 5284B.3 . -ASME Section III Construction Code RT NDE was performed and acceptable in accordance with the specified Relief Request. A VT-2 Leakage Examination was performed and acceptable. (See GORR 95-T-024).

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

1. Owner! Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649

2. Plants R.E. Qiana Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 Applicable Edition of Section XI Utilized for Repairs, Replacements or

~

Modifications t 1986 No Addenda ATTACHMENT II

8. ASME Class: 1 ~S stem: RCS-S/G GORR No.: 95-E-010 Line: N/A Construction Code:

Work Performed B :

ASME 5

Section III '86 Name of Com onent: Steam Generator "A & B" (EMSO1A, EMSO1B)

Tubes, Explosive Sleeves/Plugs.

Work Descri tion Remarks: During the Eddy Current Examination of Steam Generator "A & B", tubes containing defects were identified and determined to be candidates for B&W bimetallic explosive sleeves or plugs. A total of 75 B&W explosive sleeves and 3 B&W explosive plugs was installed in the "A" Steam Generator. A total of 91 B&W explosive sleeves and 8 B&W explosive plugs was installed in the "B" Steam Generator. The location of these defective tubes are identified within the Eddy Current "1995 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 Plugs. Eddy Current Sleeve Examinations are also utilized to verify proper weld location and provides comparison to ensure weld soundness.

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Ownert Rochester Gas 8 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 Utilised for Repairs, Replacements or Modificationss 1986 No Addenda ATTACHMENT II

9. ASME Class: 1 ~S stem: RCS-S/G GORR No.: 95-E-011 Line: N/A Construction Work Performed B :

Code: ASME 4

Section III '86 Name of Com onent: Steam Generator "B" (EMS01B) Tubes, Welded Plugs.

Work Descri tion Remarks: During the Eddy Current Examination of Steam Generator "B", a total of 10 tubes containing defects were identified and determined to be candidates for CE welded plugs. A total of ten (10) welded CE Plugs were installed in the "B" Steam Generator. The location of these defective tubes are identified within the Eddy Current "1995 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.

10. ASME Class: 3 ~S stem: MS GORR No.: 95-T-001 Construction Code: B31.1 '73/'86; B16.34 Work Performed B : 1 Name of Com onent: V3519, Studs & Nuts Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated to install new Studs & Nuts associated with V3519. This activity was controlled by WO g's 19401812, 19402976 and NCR 94-103. Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

Ra E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owner! Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649

2. Plantt 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 Class: No.: 95-T-003 11.

'": ' "-"'/'-

ASME 2 ~S stem: CVCS-Letdown Code: VIII '65;

'onstruction W

GORR 676257; B31.1 '55.

Work Performed B : 1 Name of Com onent: V203 Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated to install a rebuilt spare Relief Valve associated with V203. This activity was controlled by WO g's 19402556, 19401923, 19401901 & 19401833. Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

12. ASME Class: 3 ~Sstem: MS ~

GORR No.: 95-T-004 Construction Code: B31.1 '86; B16.341 SP-5291

.Work Performed B : 1 Name of Com onent: V3518 Studs & Nuts Work Descri tion Remarks: A Like-for-Like Replacement activity was initiated to install new Studs & Nuts associated with V3518. This activity was controlled by WO g 19402162.

Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

13. ASME Class: 3 ~Sstem: SW GORR No.: 95-T-005 Line: N/A Construction Code: Gilbert Specs RO-2204; SP-5291 Work Performed B : 1 Name of Com onent: PSW01C (SW Pump C)

Work Descri tion Remarks: Service Water Pump C Bowl Assembly with Shaft was replaced with a previously rebuilt items. Also; some bolting was replaced with approved equivalent bolts. This activity was controlled by WO g's 19402122, 19321060 and TSEE 91-546. Upon reinstallation, an ASME Section XI IWA 5244 Flow Test was performed and acceptable under PT 2.7.1 10

Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Peri.od, Third Outage (1995)

l. Owner: Rochester Gas 5 Electric Co . 89E. Ave. Rochester N.Y. 14649

2. Planti R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontari.o N.Y. 14519 3 Applicable Editi:on of Section XI Utilised for Repairs, Replacements or

~

Modificationss 1986 No Addenda ATTACHMENT II

14. ASME Class: 3 ~S stem: SW GORR No.: 95-T-006 Line: N/A Construction Code: Gilbert Specs RO-2204; SP-5291 Work Performed B : 1 Name of Com onent: PSW01A (SW Pump A)

Work Descri tion Remarks: Service Water Pump A Bowl Assembly, Discharge Case and Shaft was replaced with previously rebuilt items. This activity was controlled by WO g's 19403555 and 19402161. Upon reassembly, an ASME 'Section XI IWA 5244 Flow Test was performed and acceptable under PT 2.7.1 No.: 95-T-007

15. ASME Class:

Construction 2 ~S Code:

stem: SI

/'/'"

ASME III 83W85/ '86.

GORR Work Performed B : 1 Name of Com onent: V874E & Piping downstream V1820C.

Work Descri tion Remarks: A Like-for-Like replacement activity was initiated to install a new globe valve (V874E) with associated piping. This activity was controlled by NCR94-169 and WO g 19403601. Construction Code VT & PT examinations were performed and acceptable. An ASME Section XI hydrostatic test with accompanying VT-2 examination was performed under RSSP 15.6 and acceptable.

16. ASME Class: 2 ~Sstem: Sl GORR No.: 95-T-008 Construction Code: ASME Work Performed B : 1 III 83W85 Name of Com onent: V891C Hinge Pin.

Work Descri tion Remarks: A Like-for-Like replacement activity was initiated for the associated Hinge Pin of V891C. This activity was controlled by WO g's 19403641 and 19403627. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

11

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Periods Third Outage (1995) 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 Utilised for Repairs, Replacements or Modificationst 1986 No Addenda ATTACHMENT II

17. ASME Class: 2 ~S stem: Blowdown GORR No.: 95-T-009 Construction Code: ASME Work Performed B : 1 III '74/86 Name of Com onent: BDU-21, Rigid Support Work Descri tion Remarks: A replacement activity was initiated for BDU-21 rigid support that was inadvetingly removed and required reinstallation. This activity was controlled by WO.g 19403648 and NCR94-102. Construction Code examinations were performed and acceptable. An ASME Section XI visual Baseline examination was performed and acceptable.

18. ASME Class: 3 ~Sstem: CCW GORR No.: 95-T-010 10H-AC5-152 Construction Code:

Work Performed B :

ASME 1

III '86; B16.34 Name of Com onent: V780 A/B Flange Studs Work Descri tion Remarks: A Like-for-Like replacement activity was initiated for Flange Studs associated with Valves 780 A 6 B. This activity was controlled by WO g 19402526. Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

19. ASME Class: 3 ~S stem: SW GORR No.: 95-T-011 Line: N/A Construction Code: Gilbert Specs RO-2204; SP-5291 Work Performed B : 1 Name of Com onent: PSW01C (SW Pump C)

Work Descri tion Remarks: Service Water Pump C Bowl Assembly with Shaft was replaced with previously rebuilt items. This activity was controlled by WO g's 19404042 and 19403611. Upon reassembly, an ASME Section XI IWA 5244 Flow Test was performed and acceptable under PT 2.7.1

R. E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owners Rochester Gas E Electric Co . 89E. Ave. Rochester

2. Plantt R.E. Qiana Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14649 N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II

20. ASME Class: 3 ~S stem: SW GORR No.: 95-T-013 Line: N/A Construction Code: Gilbert Specs RO-2204; SP-5291; II '86.

Work Performed B : 1 Name of Com onent: PSW01B (SW Pump B)

Work Descri tion Remarks: Service Water Pump B Bowl Assembly, Intermediate Shaft, Impeller Shaft, Suction Bell and associated Bolting was replaced with previously rebuilt or new items. This activity was controlled by WO g's 19402721 and 19404138. Upon reassembly, an ASME Section XI IWA 5244 Flow Test was performed and acceptable under PT 2.7.1

21. ASME Class: 3 ~Sstem: SW GORR No.: 95-T-014 Construction Code: ASME Work Performed B : 1 III 86) B31 1 ~ 55( RO 2167 Name of Com onent: Expansion Joint SSW04, Supports SWU-629/633 Work.Descri tion Remarks: A replacement activity was initiated for a new Expansion Joint, modify support. SWU-633 and the replacement of miscellaneous items such as bolts, nuts ect.

This activity was controlled by EWR 5284B, TSR93-520, NCR94-128, SM-5284B.2 & WOg 19404933. After installation, Construction Code VT examinations as well asSection XI baseline examinations were performed and acceptable. Also; ASME Section XI Leakage examination was performed and acceptable. (Note: see GORR 95-E-002) 22 'SME Class: 3 ~S stem: CCW GORR No.: 95-T-016 Construction Code: ASME Work Performed B : 1 III '74/'86 Name of Com onent: CCU-159 Rigid Restraint.

Work Descri tion Remarks: A replacement activity was initiated to install washers in CCU-159, Rigid Restraint Component Support, and also to torque Hilti Bolts. This activity was controlled by WO g 19404910 and NCR94-125. Upon installation, an ASME Section XI Baseline VT examination was performed and acceptable.

13

4 tl R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

1. Owners Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649 2 Plantt R.E. Ginna Nuclear Power Plan8 1503 Lake Rd.

~ Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilised for Repairs, Replacements or Modificationss 1986 No Addenda ATTACHMENT II

23. ASME Class: 3 ~Sstem: AFW GORR No.: 95-T-017 Construction Code: ASME Work Performed B : 3 III '86; B31.1 '73; B16.34 Name of Com onent: V4000A Stem & Disc.

Work Descri tion Remarks: A replacement activity was initiated to install a new Stem & Disc associated with Valve 4000A. This activity was controlled by WO g's 19402916 and 19402936. Body to Bonnet weld area was prepped and a new Seal Weld was applied. Construction Code PT examination was performed and acceptable. Upon completing the reassembly, an ASME Section XI Leakage examination was performed and acceptable.

24. ASME Class: 3 ~S stem: SAFE GORR No.: 95-T-018 Construction Code: ASME Work Performed B : 3 III '74/'86 Name of Com onent: V9703B Stem & Disc.

Work Descri tion Remarks: A replacement activity was initiated to install a new Stem & Disc associated with Valve 9703B. This activity was controlled by WO g 19402953. Body to Bonnet weld area was prepped and a new Seal Weld was applied. Construction Code PT examination was performed and acceptable. Upon completing the reassembly, an ASME Section XI Leakage examination was performed and acceptable.

25. ASME Class: 3 ~S stem: SW GORR No.: 95-T-020 Construction Code: B31.1 '73; B16.34; ASME Work Performed B : 1 III '86.

Name of Com onent: V4622.

Relief Re uest: g 25 Work Descri tion Remarks: An Approved Equivalent replacement activity was initiated to install a spare valve from stock for V4622. This activity was controlled by NCR94-009, TE93-548 &

WO g 19400868. Construction Code VT & PT (Root & Final Weld) examinations were performed and acceptable. An ASME Section XI Leakage examination was performed and acceptable.

14

R. E ~ OINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

1. Owners Rochester Gas a Electric Co . 89E. Ave. Rochester N.Y. 14649

2. Plants R.E. Oinna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilised for RePairs, Replacements or Modificationss 1986 No Addenda ATTACHMENT II

26. ASME Class: 1 ~Sstem: Pressurizer GORR No.: 95-T-021 Construction Code: ASME Work Performed B : 3 III '83/'85/'86.

Name of Com onent: V515.

Work Descri tion Remarks: An Approved Equivalent replacement activity was initiated to install a new valve. This activity was controlled by NCR94-068, EWR 3755 & WO ¹ 19402868.

Construction Code RT & PT examinations were performed and acceptable. ASME Section XI Baseline PT examination as well as a Hydrostatic Test with accompanying VT-2 examination was performed and acceptable.

27. ASME Class: 1 ~S stem: Pressurizer GORR No.: 95-T-022 Construction Code:

Work Performed B :

ASME 3

III '83/'85/'86.

Name of Com onent: V516.

Work Descri tion Remarks: An Approved Equivalent replacement activity was initiated to install a new valve. This activity was controlled by NCR95-073 & WO ¹ 19402865. Construction Code RT & PT examinations were performed and acceptable. ASME Section XI Baseline PT examination as well as a Hydrostatic Test with accompanying VT-2 examination was performed and acceptable.

28. ASME Class: 3 ~S stem: SW GORR No.. 95-T-023 Construction Code: ASME Work Performed B : 3 III '86; B31.1 '73 Name of Com onent: V4607 Work Descri tion Remarks: A.Like-for-Likereplacement activity was initiated for V4607 Bolting & Stem. Weld Repairs were also performed to the Valve Seats & Disc. This activity was controlled by WO ¹ 19221485 & Movats DR 95-05/-06/-08/-14.

Construction Code PT examinations for the Weld Repairs of the Seat & Disc were performed and acceptable. Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

15

R. E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owners Rochester Gas 6 Electric Co . 89E. Ave. Rochester N.Y. 14649

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: 1986 No Addenda ATTACHMENT II

29. ASME Class: 3 ~sstem: SW GORR No.: 95-T-024 Construction Code:

Work Performed B :

ASME 1

III '86F B31.1 '55; RO-2167 Name of Com onent: Expansion Joint SSW05, Supports SWU-630/634 Work Descri tion Remarks: A replacement activity was initiated for a new Expansion Joint, modify supports SWU-630/6343 and the replacement of miscellaneous items such as bolts, nuts ect. This activity was controlled by EWR 5284B, TSR93-520, SM-5284B.3 & WOg 19500499. After installation, Construction Code VT examinations for the supports as well asSection XI baseline examinations were performed and acceptable. Also; ASME Section XI Leakage examination was performed and acceptable. (Note: see GORR 95-E-009)

30. ASME Class: 3 ~Sstem: SW GORR No.: 95-T-026 Construction Code: ASME Work Performed B : 3 III '86; B31.1 '73; B16.34 Name of Com onent: V4608 Work Descri tion Remarks: A Like-for-Like replacement activity was initiated for V4608 Stem. Weld Repairs were also performed to the Valve Seats & Disc. This activity was controlled by WO 19221483. Construction Code PT examinations for the Weld Repairs of the Seat & Disc were performed and acceptable. Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

31. ASME Class: 3 ~S stem: FW GORR No.: 95-T-027 Line: 4-FW-900-1 Construction Code: B31.1 '73; B16.34; SP-5291F ASME III '86.

Work Performed B : 3 Name of Com onent: V4271 Work Descri tion Remarks: A Replacement activity was initiated to install a new Stem, Cage & Plunger associated with V4271.

This activity was controlled by TSR90-126 & WO g 19402472.

Upon reinstallation, an ASME Section XI Leakage examination was performed and acceptable.

16

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

1. Owner: Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649 2 Plantt 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 32 'SME Class: 3 ~S stem: SAFE GORR No.: 95-T-029

.Construction Code:

Work Performed B  :

ASME 3

III '74/'86 Name of Com onent: V9701B Work Descri tion Remarks: A Replacement activity was initiated to install a new Stem Assembly associated with V9701B. This activity was controlled by WO g 19402948. Upon reinstallation, an ASME Section XI VT-2 examination was performed and acceptable.

33. ASME Class: 2 ~S stem: SAFW GORR No.: 95-T-030 Construction Code: ASME Work Performed B : 3 III '74/'86 Name of Com onent: V9704B Work Descri tion Remarks: A Like-for-Like replacement activity was initiated for V9704B Stem. The work activity also covered the reapplication of the Body to Bonnet Seal Weld. This activity was controlled by WO g 19402959. Construction Code PT examination for the Seal Weld was performed and acceptable. An ASME Section XI VT-2 examination was performed,and acceptable.

34. ASME Class: 2/3 ~S stem: SAFW GORR No.: 95-T-031 Construction Code: ASME Work Performed B : 3 III '74/'86 Name of Com onent: V9704A; AFU-231 Work Descri tion Remarks: A replacement activity was initiated for V9704A Stem and the reapplication of the Body to Bonnet Seal Weld. Component Support AFU-231 was also removed and reinstalled in order to provide access for the original work scope. This activity was controlled by WO g 19402956.

Construction Code PT examination for the Seal Weld and VT examination for the support was performed and acceptable. ASME Section XI Baseline VT examination for the support and VT-2 examination was performed and acceptable.

17

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

1. Owners Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649

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

~

Modificationst 1986 No Addenda ATTACHMENT II

35. ASME Class: 3 ~S stem: SW GORR No.: 95-T-032 Construction Code: ASME Work Performed B : 3 III '86; B31.1 '73; B16.34 Name of Com onent: V4668A Work Descri tion Remarks: A replacement activity was initiated for V4668A Stem. This activity was controlled by, WO ¹ 19221535. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

36. ASME Class: 3 ~S stem: SW GORR No.: 95-T-033 Construction Code: ASME Work Performed B : 3 III '86; B31.1 '73; B16.34 Name of Com onent: V4561A Work Descri tion Remarks: A replacement activity was initiated for V4561A. This activity was controlled by WO ¹ 19402895.

Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

37. ASME Class: 3 ~S stem: MS GORR No.: 95-T-034 Construction Code: ASME Work Performed B : 1 & 3 III '86; B31.1 '73/'86; B16.34 Name of Com onent: V3518 Work Descri tion Remarks: A replacement activity was initiated for V3518 Shaft & Keys. Weld repairs were also performed to the Disc Arm and the application of Tack Welds to the Nut to Disc Post. This Activity was controlled by WO ¹ 19402322 and NCR95-021. Construction Code PT Examinations were performed on the welded areas and acceptable. Upon reassembly, an ASME Section XI Leakage examination (ISI Exam 95411400) was performed and acceptable.

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

1. Owner! Rochester Gas & Electric Co . S9E. Ave. Rochester N.Y. 14649

2. Plantt 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

38. ASME Class: 3 ~S stem: RCS GORR No.: 95-T-035 Construction Code: B31.1 '73/'86; B16.34; VIII '65; W E-676279 Work Performed B : 1 Name of Com onent: V434 Work Descri tion Remarks: This activity was initiated to replace V434 with a rebuilt unit, no internal valve components were replaced. This activity was controlled by WO g 19402658.

Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

39. ASME Class: l ~S stem RCS GORR No.: 95-T-036 Construction Code: B31.1 '73/'86; B16.34; VIII '65; W E-676279 Work Performed B : 1 Name of Com onent: V435 Work Descri tion Remarks: This activity was initiated to replace V435 with a rebuilt unit, no internal valve components were replaced. This activity was controlled by WO g 19402659.

Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

40. ASME Class: 3 ~Sstem: SW GORR No.: 95-T-037 Construction Code: B31.1 '73/'86; SP-5291 Work Performed B : 1 Name of Com onent: Blind Flange Nuts/Bolts Downstream of V4640 Work Descri tion Remarks: This activity was initiated to replace associated Nuts/Bolts of Blind Flange Downstream of V4640. This activity was controlled by WO g 19500531. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

1. Owners Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649

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: 1986 No Addenda ATTACHMENT II

41. ASME Class: 3 ~S stem: DG GORR No.: 95-T-038 Construction Code: B31.1 '73/'86; SP-5291; ASME VIII Work Performed B : 1 Name of Com onent: V5960 & 1 Flange Nut/Bolt Work Descri tion Remarks: This activity was initiated to replace one Nut/Bolt on a Flange as well as for replacing V5960. This activity was controlled by WO g 19402512. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

42. ASME Class: 2 ~S stem: MS GORR No.: 95-T-039 Construction Code: B31.1 '73; SP-5291; B16.34; ASME III '86 Work Performed B : 3 Name of Com onent: V3505A Work Descri tion Remarks: This activity was initiated to replace the Stem & Disc associated with V3505A. This activity was controlled by WO I 19501151. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

43. ASME Class: 3 ~S stem: CVCS/CCW GORR No.: 95-T-040 Line: N/A Construction Code: ASME VIII Work Performed B : 1 Name of Com onent: ECH05, Non-Regen Hx.

Work Descri tion Remarks: This activity was initiated to replace two (2) Studs on the Non-Regenerative Heat Exchanger.

This activity was controlled by WO g 19221031. Upon reassembly, an ASME Section XI Leakage examination was performed and results were unacceptable. An Action Report (95-202) was generated.

20

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owners Rochester Gas a Electric Co . 89E. Ave. Rochester N.Y. 14649

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 Modificationss 1986 No Addenda ATTACHMENT II

44. ASME Class: 3 ~S stem: AFW GORR No.: 95-T-041 Construction Code: B31.1 '73; SP-5291; ASME IIX '86 Work Performed B : 3 Name of Com onent: V4010 Work Descri tion Remarks: This activity was initiated to replace the Di'sc Assembly associated with V4010. This activity was controlled by WO g 19402939. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

45. ASME Class: 2 ~S stem: MS 6B-MS-600-1B Construction Code: B31.1 '73; Work Performed B : 3 ASME III '77/75 & '86 Name of Com onent: V3411 6 V3410 Work Descri tion Remarks: This replacement activity was initiated to install a Diffuser/Pilot Plug in V3411 and a Stem Pilot Assembly in V3410. These activities were controlled by.

WO g's 19402924 and 19402925. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

46. ASME Class: 2 ~Sstem: CS GORR No . 95-T-043 Line: 3A-SI-301 Construction Code: SP-5291; Work Performed B : 1 ASME III '74/'86 Name of Com onent: CSU-72, Component Support Work Descri tion Remarks: This activity was initiated to install a nut on Component Support CSU-72. This activity was controlled by WO g 19501405. Upon assembly, proper torque verification was performed and acceptable. No additional ASME Section XX Baseline Examinations were performed since this Component Support is located on an Exempt Line.

21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owner: 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 XI Utilized for Repairs, Replacements or Modifications! 1986 No Addenda ATTACHMENT II

47. ASME Class: 2 ~S stem: CVCS GORR No.: 95-T-044 Construction Code: B31.1 '73/'86; B16.34 Work Performed B : 1 Name of Com onent: V371 Work Descri tion Remarks: This activity was initiated to install a Plug/Stem Assembly associated with V371. This activity was controlled by WO ¹ 19501329. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

48. ASME Class: 2 ~S stem: HHS GORR No.: 95-T-045 Line: 150-4 Construction Code': B31.1 '55; ASME III '86; SP-5291 Work Performed B : 1 Name of Com onent: Capped Penetrations 301 & 303 Work Descri tion Remarks: This activity was initiated to remove HHS System piping and capping Penetrations 301 and 302.

The work was controlled by WO ¹ 19320570 & TSR93-067.

Construction Code VT & PT examinations were performed and acceptable associated with the end caps. Upon completion of this activity, an Appendix J Pressure Test was performed &

acceptable.

49. ASME Class: 3 ~Sstem: MS GORR No.: 95-T-046 Corrective Action Activity 1.5D-MS-600-1 Construction Code: B31.1 73I ASME III 86 B16 34) SP 5291 Work Performed B : 1 Name of Com onent: V8527 & V8528 Work Descri tion Remarks: A replacement activity was initiated to install new valves associated with V8527 & V8528. These activities were controlled by WO ¹'s 19404707 and 19403598.

Construction Code VT & MT examinations were performed and acceptable. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable. An Action Report (95-171) was generated for the improper application of ASME Section XI Leakage examination. Relief Request ¹30 was also generated.

22

Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Third Outage (1995)

l. Owners Rochester Gas & Electric Co . S9E. Ave. Rochester N.Y. 14649 2 ~ Plantt R.E. Qiana Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 ~ Applicable Edition of Section XI Utilised for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II

50. ASME Class: 3 ~S stem: AFW GORR No.: 95-T-047 Construction Code: B31.1 '73:

Work Performed B : 3 ASME III '86; B16.34; SP-5291 Name of Com onent: V4007 Work Descri tion Remarks: This activity was initiated to install a new Stem & Seat Rings associated with V4007. This activity was controlled by WO g 19501545. Upon reassembly, an ASME Section XI Leakage examination was performed and acceptable.

51. ASME Class: 2 ~Sstem: SI GORR No.: 95-T-048 Construction Code:

Work Performed B :

B31.1 '73; B16.34; 1

ASME III '86 Name of Com onent: V1820C Work Descri tion Remarks: This activity was initiated to replace V1820C. This activity was controlled by WO g 19403628.

Construction Code VT & PT examinations were performed and acceptable. Upon completion of this activity, an ASME Section XI Hydro Test and accompanying VT-2 examination was performed and acceptable.

23

S R~ E 'GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Third Outage (1995)

1. Owner: Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649

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: 19S6 No Addenda ATTACHMENT II

52. ASME Class: 2 ~S stem: S/G Blowdown GORR No.: 95-T-049 Line: "B" Loop Construction Code: B31.1 '73; ASME III '74/'86.

Work Performed B : 1 & 2 Name of Com onent: S/G Blowdown "B" Loop; Piping & Supports, inside Containment.

Code Case: N-416 Work Descri tion Remarks: A replacement activity on the S/G Blowdown Loop "B" piping (2") and Component Supports inside containment was initiated. Piping material was upgraded from Carbon Steel to Chrome-Moly. This activity was controlled by WO g 19500287, TSR94-116, EWR 4499 and SM94-116.1.

Construction Code VT & MT examinations on the 2" Socket Welds as well as RT & VT examinations on the one (1) Butt Weld were performed and acceptable. Existing Component Supports (BDU-5, BDU-11, BDU-15, & BDU-16) were removed for this activity and later reinstalled had Construction Code VT examinations performed and acceptable. An ASME Section. XI Leakage examination was performed and acceptable in accordance with Code Case N-416.

24

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, second Period, Third Outage (1995)

ATTACHMENT III EROSION/CORROSION (MINWALL) PROGRAM

SUMMARY

This section provides Erosion/Corrosion examination details and information corresponding to items inspected during the 1995 Outage.

A total of 96 items were examined. The breakdown of this total is as follows:

Com onent T e Total Number Pipes 51 Elbows 34 Reducers 6 Tees 4 Ex ansion Joint 1 Total 96 The following lists identifies systems of examined components, system component result summaries, and component result details.

S stems of Examined Com onents:

Component thickness measurements were performed on the following systems.

DWG NO. SYSTEMS M-1 A/B F.W. PUMP DISCHARGE TO 5 A/B HEATERS M-2 5 A/B F.W. HEATERS TO F.W. HEADER M-4A FEEDWATER CLEANUP TO CONDENSER FROM 5A/B HP HEATERS M-4B FEEDWATER CLEANUP TO CONDENSER & CONDENSATE DEM. RINSE M-7A HEATER DRAIN TANK DISCHARGE M-10 LOW PRESSURE DOWNCOMERS (WEST CONDENSER)

M-10A LOW PRESSURE DOWNCOMERS TO L.P.H. (WEST CONDENSER)

M-10B LOW PRESSURE DOWNCOMERS (EAST CONDENSER)

M-10C LOW PRESSURE DOWNCOMERS TO L.P.H. (EAST CONDENSER)

M-11A MSR 1A & 1B 2ND PASS DRAIN M-15A MSR 1A 4TH PASS TO 5A HEATER M-15B MSR 1B 4TH PASS TO 5A HEATER

0 0

R E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

ATTACHMENT III S stems of Examined Com onents: Cont.

DWG NO. SYSTEMS M-16 MSR 1A & 1B 4TH PASS TO CONDENSER M-31 MSR 1A & 1B TO HEATER DRAIN TANK & CONDENSER M-41A 5A HP HEATER DRAIN TO 4A LP HEATER M-41B 5B HEATER DRAIN TO 4B HEATER M-75 STEAM EXTRACTION TO 5A & 5B HEATERS M-81 FEEDWATER DISCHARGE (TURBINE BLDG)

M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

M-90 FEEDWATER CLEAN UP (CV-18)

M-91 FEEDWATER CLEAN UP (CV-19)

M-105 HEATING STEAM S stem Com onent Result Summaries:

The following break down by system provides general results on the component types that were examined.

DWG NO. SYSTEM M-1 A/B FoW PUMP DISCHARGE TO 5 A/B HEATERS Components Examined: Results: 4 of Nominal 2 Elbows 4 Acceptable 2 Pipes M-2 5 A/B F.W. HEATERS TO F W. HEADER Components Examined: Results: 4 of Nominal 2 Elbows 1 Acceptable 2 Pipes 3 >88

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

ATTACHMENT III S stem Com onent Result Summaries: Cont.

DWG NO. SYSTEM M-4A FEEDWATER CLEANUP TO CONDENSER FROM 5A/B HP HEATERS Components Examined:'esults: 4 of Nominal 1 Pipe 1 >88 M-4B FEEDWATER CLEANUP TO CONDENSER & CONDENSATE DEM. RINSE Components Examined: Results: > of Nominal 2 Elbows 2 >88 2 Pipes 2 88-82 2 Reducer 1 82-76 1 76-70 M-7A HEATER DRAIN TANK DISCHARGE Components Examined: Results: 4 of Nominal 2 Elbows 1 Acceptable 1 Expansion Joint 4 >88 1 Pipe 1 Reducer M-10 LOW PRESSURE DOWNCOMERS (WEST CONDENSER)

Components Examined: Results: 4 of Nominal 1 Pipe 1 <65 M-10A LOW PRESSURE DOWNCOMERS TO L.P H (WEST CONDENSER)

Components Examined: Results: 4 of Nominal 5 Pipes 1 82-76 4 <65 M-10B LOW PRESSURE DOWNCOMERS (EAST CONDENSER)

Components Examined: Results: % of Nominal 1 Pipe 1 <65 M-10C LOW PRESSURE DOWNCOMERS TO L.P.H (EAST CONDENSER)

Components Examined: Results: ~ of Nominal 3 Pipes 1 70-65 2 <65

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

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ATTACHMENT III S stem Com onent Result Summaries: Cont.

DWG ~

NO. SYSTEM M-11A MSR 1A & 1B 2ND PASS DRAIN Components Examined: Results: 9 of Nominal 1 Elbow 2 >88 1 Pipe M-15A MSR 1A 4TH PASS TO 5A HEATER Components Examined: Results: 4 of Nominal 4 Elbows 10 >88 5 Pipes 1 Tee M-15B MSR 1B 4TH PASS TO 5A HEATER Components Examined: Results: 4 of Nominal 1 Elbow 1 >88 M-16 MSR 1A & 1B 4TH PASS TO CONDENSER Components Examined: Results: 4 of Nominal 1 Pipe 1 88-82 M-31 MSR 1A & 1B TO HEATER DRAIN TANK & CONDENSER Components Examined: Results: 4 of Nominal 5 Elbows 13 >88 7 Pipes 1 Tee M-41A 5A HP HEATER DRAIN TO 4A LP HEATER Components Examined: Results:  % of Nominal 3 Elbows 5 >88 2 Pipes M-41B SB HEATER DRAIN TO 4B HEATER Components Examined: Results: 4 of Nominal 3 Elbows 4 >88 2 Pipes 1 88-82

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Peri.od, Third Outage'(1995)

ATTACHMENT III S stem Com onent Result Summaries: Cont.

DWG ~

NO SYSTEM M-75 STEAM EXTRACTION TO 5A 5B HEATERS Components Examined: Results: c of Nominal 2 Elbows 1 Acceptable 3 Pipes 1 Unacceptable 1 Tee 2 >88 1 76-70 1 70-65 M-81 FEEDWATER DISCHARGE (TURBINE BLDG)

Components Examined: Results: 4 of Nominal 2 Elbows 5 >88 3 Pipes 1 88-82 2 Reducers 1 <65 M-88D'S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

Components Examined: Results: 4 of Nominal 2 Elbows 7 >88 6 Pipes 1 76-70 1 Tee 1 <65 M-90 FEEDWATER CLEAN UP (CV-18)

Components Examined: Results: 4 of Nominal 1 Elbow 1 82-76 1 Pipe 1 76-70 M-91 FEEDWATER CLEAN UP (CV-19)

Components Examined: Results: 4 of Nominal 1 Elbow 1 >88 1 Reducer 1 88-82 M-105 HEATING STEAM Components Examined: Results: 4 of Nominal 1 Elbow 3 >88 2 Pipes

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval,

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Second Period, Third Outage (1995)

ATTACHMENT III Com anent 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 J = Expansion Joint Drawing No. M-1 System: A/B FW PUMP DISCHARGE TO 5A/B HEATER-

.Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 200270 27 P 0.938 0.604 NA >88 VT 200280 28 E 0.938 0.703 NA >88 VT P 0.938 0.604 NA >88 VT 200300 30 E 0.938 0.701 NA >88

'Drawing No. M-2 System: 5 A/B FEEDWATER HEATERS TO FEEDWATER HEADER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 201130 13 E 0.938 0.704 NA >88 VT 201140 14 P 0.938 0.605 0.864 >88 UT 201150 15 E 0.938 0.705 0.961 >88 UT 201160 16 E 0.938 0.710 1.009 >88 UT Drawing No. M-4A System: FEEDWATER CLEANUP TO CONDENSER/EAST WALL Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 203310 31 P 0.500 0.250 0.603 >88 UT

R E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Periodi Third Outage (1995)

ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-4B System: FEEDWATER CLEANUP TO CONDENSER/EAST WALL Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 204510 51 R 0.500 0.594 0.350,0.416 0.491 88-82 UT 204520 52 E 0.594 0.416 0.503 88-82 UT 204590 59 E 0.594 0.416 0. 467. 82-76 UT 204600 60 P 0.594 0.416 0.571 >88 UT 204630 63 R 0.594 0.688 0.416,0.482 0.467 76-70 UT 204640 64 P 0.688 0.482 0.675 >88 UT Drawing No. M-7A

~

System: HEATER DRAIN TANK DISCHARGE Comp.~ Comp. Nominal Nominal Minimum Percent NDE

~ ~ ~

Summary ~ Minimum Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 207010 01 E 0.688 0.278 0.695 >88 UT 207020 02 P 0.688 0.274 0. 646 >88 UT 207030 03 E 0. 688 0.278 0.630 >88 UT 207045 04A J 0.688 NA NA VT 207050 05 R 0.688 0.750 0.278,0.303 0.786 >88 UT Drawing No. M-10 System: LOW PRESSURE DOWNCOMERS Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 211060 1F P 0.375 0. 113 0.236 (65 UT

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-10A System: STEAM EXTRACTION TO 2A LPH Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 212180 18 P 0.375 0. 113 0.150 <65 UT 212190 19 P 0.375 0. 113 0. 140 <65 UT 212250 25 P 0.375 0.113 0.285 82-76 . UT 212260 26 P 0.375 0. 113 0.156 <65 UT 212270 27 P 0.375 0. 113 Holes <65 UT t Drawing No. M-10B Summary Number 213060 2F Drawing No. M-10C P

System:

Comp. Comp. Nominal ID T e Wall 1 0.375 System:

LOW PRESSURE Nominal Wall 2 DOWNCOMERS Minimum Allowable

0. 113 STEAM EXTRACTION TO 2B LPH Minimum Percent Readin 0.159 NDE Nominal Meth

<65 UT Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE

~

Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 214130 13 P 0.375 0.113 0.254 70-65 UT 214140 14 P 0.375 0.113 0.120 <65 UT 214150 15 P 0.375 0.113 Holes <65 UT Drawing No. M-11A System: MSR 1A & 1B 2ND PASS DRAINS Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 215080 08 E 0.432 0.268 0.390 >88 UT 215090 09 P 0.432 0.267 0.401 >88 UT

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ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-15A System: MSR 1A 4TH PASS TO HEATER 5A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 226010 01 P 0.432 0. 266 0.499 >88 UT 226020 02 E 0.432 0.266 0.385 >88 226025 2A P 0.432 0.266 0.398 >88 UT 226030 03 E 0.432 0.266 0.397 >88 UT 226040 04 P 0. 432 0.266 0.390 >88 UT 226090 09 E 0. 300 0.171 0.284 >88 UT 226100 10 -

P 0.300 0.168 0.275 >88 UT 226105 10A E 0.300 0. 175 0.266 >88 UT 226110 11 T 0.300 0. 171 0.289 >88 UT 226120 12 P 0.300 0. 168 0.284 >88 UT Drawing No. M-15B System: MSR 1B 4TH PASS TO HEATER 5B, Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 227210 73 E 0.300 0.169 0.273 >88 UT Drawing No. M-16 System: MSR 1A & 1B 4TH PASS DRAIN TO CONDENSER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 228010 01 P 0.300 0.168 0.263 88-82 UT

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995) 1 ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-31 System: MSR 1A & 1B TO HEATER DRAIN TANK Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 260090 09 E 0.432 0. 168 0.473 >88 UT 260100 10 P 0.432 0. 166 0.417. >88 UT 260110 11 E 0.432 0. 168, 0.414 >88 UT 260120 12 P 0.432 0.166 0.418 >88 UT 260247 24C P 0.432 0.378 0.403 >88 UT

'60250 25 E 0.432 0.378 0.420 >88 UT 260260 26 P 0.432 0.378 0.412 >88 UT e 260270, 260280 27 28 T

P 0.432 0.432 0.378 0.378 0.448 0.390

>88

>88 UT UT 260281 28A E 0.432 0.378 0.387 >88 260282 28B P 0.432 0.378 0.408 >88 UT 2'60283 28C E 0.432 0.378 0.388 >88 UT 260370 37 P 0.432 0.378 0.419 >88 UT Drawing No. M-41A System: 5A H.P.H. DRAIN TO 4A L.P.H.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 290012 1A E 0. 687 0.601 0.688 >88 UT 290013 1C E 0.687 0.432 0.601,0.378 0.678 >88 UT 290014 1D P 0.432 0.378 0. 412 >88 UT 290015 1E E 0.432 0.378 0. 417 >88 UT, 290017 1F P 0.432 0.378 0.411 >88 UT 10

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval,

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second PeriodI Third Outage (1995)

ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-41B 8ystem: 5B H.P.H. DRAIN TO 4B L.P.H.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth

-291012 "

40A E 0.687 0.601 0.656 >88 UT 291013 40C E 0.687 0.432 0.601;0.378 0.621 >88 UT 291014 40D P 0'.432 0.378 0.418 >88 UT 291015 40E E 0.432 0.378 0.406 >88 UT 291016 40F P 0.432 0.378 0.380 88-82 UT Drawing No. M-75

~

~ System: STEAM EXTRACTION TO 5A & 5B H.P.H.

Summary Comp. Comp. Nominal

~ ~ Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 303120 12 P 0.375 0.232 0.264 76-70 UT 303130 13 E 0.375 0.231 0.353 >88 UT 303140 14 E 0.375 0.225 NA OK VT 303150 15 P 0.375 0.214 NA OK VT 303170 17 T 0.375 0.230 0.367 >88 UT 303205 20A P 0. 375 0.230 0.254 70-65 UT Drawing No. M-81 System: FEEDWATER DISCHARGE Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 390060 06 R 0.844 0.938 0.570,0.705 0.475 <65 UT 390065 06A P 0.938 0.697 0.848 >88 UT 0.710 0.954 >88 UT 390090 09 P 0.938 0.605 0.863 >88 UT 11

R. E GINNA NUCLEAR POWER PLANT r

Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-81 (Cont.)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 390210 21 R 0.844 0.938 0.637,0.699 0.720 88-82 UT 390230 23 E 0.938 0. 697 0.855 >88 UT 390240 24 P 0.938 0. 605 0.875 >88 UT Drawing No. M-88D System: BLOWDOWN TO BLOWDOWN TANK (TURBINE BLDG.)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 385140 14 P 0.300 0. 170 0.291 >88 UT 385150 15 E 0.300 0. 170 0.284 >88 UT 385160 16 P 0.300 0. 168 0.297 >88 UT 385392 ,. 39B P 0.337 0. 144 0.251 76-70 UT 385530 53 P 0.300 0. 170 0.283 >88 UT 385540 54 E 0.300 0. 170 0.291 >88 UT 385550 55 P 0.300 0.168 0.284 >88 UT 385757 75B P 0.337 0.169 0.303 >88 UT 385800 80 T 0.500 0.500 0.285,0.258 0.265 <65 UT Drawing No. M-90 System: FW RECIRC CV-18 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth.

300410 40 E 0. 432 0.334 0.340 82-76 UT 300440 43 P 0.432 0.287 0.317 76-70 UT 12

i ~

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Third Outage (1995)

ATTACHMENT III Com onent Result Details: Cont.

Drawing No. M-91 System: FW RECIRC CV-19 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent'NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 300790 33 R 0 ~ 337 0 ~ 432 0 ~ 223 I 0 ~ 338 0 ~ 342 >88 UT 300820 36 E 0. 432 0.333 0.374 88-82 UT Drawing No. M-105 System: House Heating System Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Meth 331010 01 P 0.237 0. 166 0.223 >88 UT 331020 02 E 0.237 0.166 0.240 >88 UT P 0.237 0.166 0.218 >88 UT 13