ML17263A339

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Inservice Insp Rept for Third Interval (1990 - 1999) Second Period,First Outage (1993) at Re Ginna Nuclear Power Plant.
ML17263A339
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/07/1993
From:
ROCHESTER GAS & ELECTRIC CORP.
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ML17263A338 List:
References
NUDOCS 9308050002
Download: ML17263A339 (249)
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ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUES ROCHESTERi NY 14649 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE THIRD INTERVAL ( 199 0 - 1999 )

SECOND PERIOD i FIRST OUTAGE ( 19 93 )

AT R. E. GINNA NUCLEAR POWER PLANT REVISION 0 JUNE 7, 1993 9308050002 930722 PDR ADQCK 05000244 6 , PDR

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

SECOND PERIODS FIRST OUTAGE (1993)

OWNERS DATA SHEET Date: 7 June, 1993 Owner: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 Plant Location and Unit No.: R. E. Ginna Nuclear Power Plant Unit One 1503 Lake Road Ontario, New York 14519 Commercial 0 eratin Date: July 1970 A licable Code: ASME Section XI,, 1986 Edition, No Addenda

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

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 ISI Expanded Examinations Snubbers Visual Examinations Functional Testing Erosion/Corrosion (Minwall)

Attachment I ISI Program Summary Attachment II 1 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, First Outage (1993)

INTRODUCTION AND SYNOPSIS Inservice Inspection (ISI) activities during the 1993 Refueling Outage were performed on components within Class 1, 2, 3, High Energy Piping, Steam Generator Tubes and Snubbers. The examinations were initiated on March 12, 1993 and activities concluded on May 6, 1993. Examination methods included Visual Examination (VT), Liquid Penetrant (PT), Magnetic Particle Examination (MT), Ultrasonic Examination (UT), Radiographic Examination (RT), and Eddy Current Examination (ET). Functional Testing (FT) and System Pressure Tests were also performed.

Personnel involved included the RG&E Materials Engineering and Inspection Services Section, Quality Inspection Services, NDX Corporation, Sonic Systems Incorporated, Master Lee Services Allen Nuclear Associates, Ginna Station Quality 'orporation, Control and the Ginna Station Results/Test Group. Additional Support Personnel involved, included individuals from the following departments: Ginna Station, Insulators, Maintenance, Electricians, Pipe Fitters, Health Physics, Turbine Maintenance, RGGE General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering Services Department.

SUMMARY

OF WORK ACCOMPLISHED:

Upon conclusion of the 1993 Outage, 33% of required examinations for the Third Interval ISI Program have been completed. A detailed component summary of all outage ISI activities with their associated results can be found within "Attachment I".

CLASS 1 COMPONENTS:

A total of 81 Class 1 Components were examined during the 1993 Outage. The examinations for these components consisted of 32 VT-1's, 10 VT-3's, 14 PT's, 9 MT's, 1 RT and 61 UT's. A total of 127 examinations were performed on Class 1 Components.

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

"CLASS 1 COMPONENTS: Cont.

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

Item S stem Descri tion Plant Line Reactor Pressure Vessel Interior Pressurizer, Manway Bolting Steam Generator A & B, Inlet/Outlet Manway Nuts & Studs Reactor Coolant System Loop A 31-RC-2501-A Pressurizer Spray Lines 3A-RCS-2501-B 2E-CH5-2501 2-CH5-2501 H. P. Safety Injection Lines 10A-SI2-2501-A 2C-SI2-2501 Letdown Line 2A-CH4-2501 Alternate Charging Lines 2A-CH5-2501 2C-CH5-2501 2C-CH5-2502 2F-CH5-2501 Reactor Coolant Pump "A" Bolting, Nuts & Studs, Anchor Bolts Reactor Coolant Pump "B",

Flywheel & Pawls; CLASS 2 COMPONENTS:

A total of 79 Class 2 Components were examined. The examinations for these components consisted of 7 VT-1's, 37 VT-3's, 31 PT's, 10 MT's, 2 RT's, and 17 UT's, for a total of 104 examinations.

I R. E. GINNA NUCLEAR POWER PLANT H S Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

CLASS 2 COMPONENTS: Cont.

Class 2 examinations were performed on the following items

/ systems and/or plant lines:

Item S stem Descri tion Plant Line Non-Regenerative Heat Exchanger Support Legs Seal Water Return Filter Support Legs Reactor Coolant Filter Support Legs Pulse Dampener 8C-CH-2502 Seal Water Injection Filter ¹1, Circumferential Weld; Main Steam Loop A Lines 30A-MS-600-1A 6E-MS-600-1A Main Steam Loop B Lines 30B-MS-600-1B 6B-MS-600-1B Feedwater Loop A Line 14A-FW-900-1A Feedwater Loop B Lines 18B-FW-900-1B 14B-FW-900-1B L.P. Safety Injection Lines 10 -SI-151 8A-SI-151 8B-SI-151 8D-SI-301 6A-AC-601 Residual Heat Removal Lines 10 -AC-601 10A-AC-601 8D-AC-601 8F-AC-151 8FF-AC-151 8X-AC-601 6C-AC-601 6E-AC-151

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

CLASS 2 COMPONENTS: Cont.

Item S stem Descri tion Plant Line H.P. Safety Injection Lines 3A-SI-1501 3B-SI-1501 3C-SI-1501 3E-SI-1501 2D-SI-1501 2R-SI-2501 2S-SI-2501 2T-SI-2501 2U-SI-2501 Containment Spray Lines 6D-SI-301 6L-SI-301 Service Water Lines 8A-SW-125 8B-SW-125 8E-SW-125 8F-SW-125 8J-SW-125 Standby Auxiliary Feedwater Lines 3C-FW-902S-1A 3C-FW-902S-1B CLASS 3 COMPONENTS:

A total of 49 'Class 3 Components were examined by the VT-3 visual technique.

Class 3 examinations were performed on the following items

/ systems and/or plant lines:

Item S stem Descri tion Plant Line Component Cooling Lines 14B-AC5-152 14C-AC5-152 10I-AC5-152 Auxiliary Cooling Lines 8A-AC6-152 6C-AC6-152 6H-AC6-152

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

CLASS 3 COMPONENTS:

Item S stem Descri tion Plant Line Service Water Lines 20D-SWO-125-1 14I-SWO-125-1 8D-SWO-125-1 8E-SWO-125-1 Auxiliary Feedwater Lines 5A-FW7-900-1 3A-FW7-900-1A 3A-FW7-900-1B 3F-FW7-900-1 3H-FW7-900-1 3K-FW7-900-1 1.5A-FW7-900-1 Standby Auxiliary Feedwater Lines 4A-FW8-152S-A 4B-FW8-152S-B 4K-SWO-152S 3A-FW8-902S-A 3A-FW8-902S-B 3C-FW8-902S HIGH ENERGY COMPONENTS:

Components associated with the High Energy Program were examined during the 1993 Outage. The examinations for these items consisted of 14 VT-1's, 6 VT-3's, 15 MT's, 7 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 Main Steam Lines 36 -MS-600-1 30A-MS-,600-1A 30B-MS-600-1B 24A-MS-600-1A 24B-MS-600-1A 24B-MS-600-1B Feedwater Lines 20 -FW-900-1 14A-FW-900-1A 14B-FW-900-1A 14B-FW-900-1B 8 -FW-900-1

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

STEAM GENERATOR TUBING:

Eddy Current Examinations were performed on tubes in the A and B Steam Generators.

The following Eddy Current examinations were performed during the 1993 Outage:

1. Open Generator Tubes, Previous indications greater than or equal to 20: were examined to the extent of degradation as a minimum.
2. Open Generator Tubes, 20% 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.

The following information summarizes the planned and completed Eddy Current work scope for Steam Generators A & B:

STEAM GENERATOR A:

Steam Generator "A" Ins ection Summar Prior To Correction:

Total Tubes 3260 Out of Service (Plugged) 185 Sleeved Tubes 555 Open Unsleeved Tubes 2520

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

STEAM GENERATOR TUBING: Cont.

Steam Generator "A" Planned and Com leted Work Sco e:

Req'd Number Number Mini Procrm ' ~Ins t'd ~Com 1t'd Hot Leg to 1st TSP 2520 2520 2520 100 ~ 0+o Full Length (20% Random) 696 696 696 100. 04 Roll Transition MRPC 2520 2520 2520 100.0M U-Bend MRPC (Rows 1&2) 165 165 165 100.0~o Previous Ind. > 20: 81 81 81 100.0<o Sleeves 117 117 117 100.0~o Deplugged Tubes (F/L) 0. O~o

.1 Per Appendix B Requirement 2 0 Comp3.ete = Tubes Inspected/Required Minimum STEAM GENERATOR B:

Steam Generator "B" Ins ection Summar Prior To Correction:

Total Tubes 3260 Out of Service (Plugged) 314 Sleeved Tubes 1133 Open Unsleeved Tubes 1813

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R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

STEAM GENERATOR TUBING: Cont.

Steam Generator "B" Planned and Com leted Work Sco e:

Req'd Number Number Min Procrm'd ~Ins t'd ~Com 1t'd Hot Leg to 1st TSP 1813 1813 1813 100 ~ O~o Full Length (20: Random) 416 416 416 100 ~ O~o Roll Transition MRPC 1813 1813 1813 100.

0%'00.0%

U-Bend MRPC (Rows 1&2) 144 144 144 Previous Ind. > 20> 27 27 27 100 '~o Sleeves 232 232 232 100.04 Deplugged Tubes (F/L) 48 48 48 1 0 0 ~ 0 ~o 1 Per Appendix B Requirement 2  : Complete = Tubes Inspected/Required Minimum Steam Generator Eddy Current Examination details are documented in the Rochester Gas 6 Electric Report titled "Summary Examination Report for the 1993 Steam Generator Eddy Current Inspection".

SYSTEM PRESSURE TESTS:

H drostatic Testin No ISI Hydrostatic tests were performed during the 1993 Outage.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

SYSTEM PRESSURE TESTS: Cont.

Leaka e Testin A total of eleven (11) leakage examinations were performed during the 1993 outage. The leakage tests included; one (1)

Class 1, Reactor Coolant System (PT-7) examination, and ten (10)

Class 2 and 3 examinations.

Four (4) leakage examinations were performed prior to 31 December 1992 in order to fulfillthe First Period requirements of the Third Interval Program. The four leakage examinations performed for First Period credit are; Summary Examination Examination Number Results 414300 Service Water to Turbine Acceptable.

Driven Aux. Feedwater Pump.,

414700 Letdown System.- Acceptable 415500 Spent Fuel Pool Cooling. Acceptable 415550 Spent Fuel Pool Cooling- Acceptable B Loop.

ISI Ex anded Examinations:

During the 1993 Ginna Outage, one (1) component was determined to be a "Service Induced" Reject.

The component was:

~Setem Line Com onent Pressurizer System 3-RC-602R Hydraulic Snubber, PS-9 Due to the classification of a "Service Induced" Reject, additional examinations were performed similar to the requirements specified within IWF-2430 of ASME Section XI for this non-class support. The results of the additional examinations were acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM:

Visual Examinations:

A total of 149 Snubber component supports were examined during the 1993 outage. These examinations were performed to satisfy Ginna Station Technical Specification requirements.

Snubber visual examinations were performed on the following items

/ systems and/or plant lines:

Item S stem Descri tion Plant Line Steam Generator "A" Steam Generator "B" Turbine Driven Auxiliary Feedwater Pump Suction Line 4A-CD-150-1C Auxiliary Feedwater Pump Discharge Intermediate Building Lines 3K-FW7-900-1 3A-FW7-900-1A 3J-FW7-900-1 3B-FW-900-1B 3A-FW7-900-1B 3A-FW-900-1A 3B-FW-900-1A Steam Generator 1B Blowdown Line 2C-MS-600-1B.

Auxiliary Cooling Line 4S-AC6-152 Auxiliary Cooling System from Pump Cooling Outlet to Penetration 126 Line 3E-AC6-152 Auxiliary Cooling Line 4T-AC6-152 2-IN. Letdown Line 2A-CH4-2501 2-IN. Charging Line 2G-CH5-2502 10

"t R. ED GINNA NUCLEAR POWER PLANT

'Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item S stem Descri tion Plant Line 2-IN. Alternate Charging Line 2F-CH5-2501 CVCS Relief Line 2E-CH-601 Reactor Coolant Pump "1B" Seal Water Line 2AB-CH-2502 Reactor Coolant Pump "1A" Seal Water Line 2P-CH-2501 CVCS Letdown Lines 2H-CH-601 2A-CH4-151 Feedwater Loop "A" Line 14A-FW-900-1A Feedwater Loop "B" Line 14B-FW-900-1B Main Steam Loop "A" Line 30A-MS-600-1A Main Steam Loop "B" Line 30B-MS-600-1B Main Steam Loop "A", Atmospheric Vent Line 6B-MS-600-1A Main Steam Loop "B", Atmospheric Vent Line 6B-MS-600-1B Main Steam Supply to Auxiliary Feedwater Pump Turbine Lines 6A-MS-600-1 6A-MS-600-1A 6B-MS-600-1 6B-MS-600-1B Low Head Safety Injection Line 6-AC-601 11

R. E.'GINNA NUCLEAR POWER PLANT Inservice,Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item S stem Descri tion Plant Line Residual Heat Removal Line 10A-RCO-2501-A Residual Heat Removal Line SB-AC-601 Residual Heat Removal Line 10-AC-601 Residual Heat Removal Line 6D-AC-601 Residual Heat Removal Line 10E-AC-601 Residual Heat Removal Line 10G-AC-601 Residual Heat Removal, Pump "A" Suction Line 10GG-AC-151 Residual Heat Removal Line 10D-AC-601 Residual Heat Removal Line 6K-AC-151 Low Head Safety Injection Line 10-SI-151 Safety Injection, Pump "A" Suction Line 4-SI-301 Safety Injection Line 8H-SI-151 High Pressure Safety Injection Lines 10A-SI2-2501-A 10A-SI2-2501-B Service Water to AGB Diesel Generator Water Coolers Line 10B-SWO-125-1 12

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item S stem Descri tion Plant Line Service Water Line SL-SW-125 Service Water-Intermediate Building from 16" Header to Penetrations 312-320, Line SA-SWO-125-1 Standby Auxiliary Feedwater from Penetration 123 to B S/G Feedwater Header, Line 3C-FW-902S-1B Standby Auxiliary Feedwater from Penetration 119 to A S/G Feedwater Header Line 3C-FW-902S-1A Pressurizer Relief from Pressurizer to Relief Manifold Lines 6AP-RC-602 6BP-RC-602 Power Pressurizer Relief Lines 3BP-RC-602 3B-RCS-2501 Pressurizer Relief Line 3A-RCS-2501 CVCS Line 2X-CH-2501 Standby Auxiliary Feedwater Lines 3C-FW-902S-1A 3C-FW-902S-1B 13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 .Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM: Cont.

Functional Testin A total of 25 snubbers were Functionally Tested (FT) during the 1993 outage. From this total number, fifteen (15) snubbers were required by the original schedule and ten (10) snubbers were due to successive/augmented testing. From the fifteen (15) originally scheduled, twelve (12) were Mechanical Snubbers and three (3) were Hydraulic Snubbers.

For the 1993 Outage, one hydraulic snubber (AFU-205) failed functional testing. This failure will require a successive test to be performed on AFU-205 during the 1994 Outage.

The Scope of Snubber Functional Testing for the 1994 Outage will be the normal schedule requirements along with the " one identified additional snubber (AFU-205).

Snubber Functional Testing (FT) were performed on the following items and/or system lines during the 1993 Outage.

Item S stem Descri tion Plant Line Steam Generator "B" Auxiliary Cooling System Line 3E-AC6-152 Charging Line 2G-CH5-2502 Pressurizer Relief Line 2E-CH-601 Letdown Line 2H-CH-601 2A-CH4-151 14

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

SNUBBER PROGRAM: Cont.

Functional Testin Item S stem Descri tion Plant Line Main Steam Lines 30B-MS-600-1B 30A-MS-600-1A 6B-MS-600-1B 6B-MS-600-1A 6B-MS-600-1 6B-MS-600-1B 6A-MS-600-1 Residual Heat Removal Line 10 -AC-601 10GG-AC-151 10A-RCO-2501-B Service Water Line SA-SWO-125-1 Standby Auxiliary Feedwater Line 3C-FW-902S-1B Power Pressurizer Relief Lines 3BP-RC-602 3B -RCS-2501 EROSION CORROSION MINWALL PROGRAM:

A total of 192 components were examined prior to or during the 1993 Outage. The breakdown of this total number are as follows:

Com onent T e Total Number Pipes 84 Elbows 41 Reducers 36 Tees 21 Caps 4 Tanks 2 Nozzles 2 Heater Shells 2 15

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First, Outage (1993)

EROSION CORROSION MINWALL PROGRAM: Cont.

Component thickness measurements were performed on the following systems:

DWG.

NO. SYSTEM M-1 A/B FW Pump Discharge to 5 A/B Heaters M-7B Condensate Pump & Heater Drain Tank Discharge to Feedwater Suction.

M-11A MSR 1A & 1B 2nd Pass Drain M-11B MSR 2A & 2B 2nd Pass Drain M-12A MSR 1A & 1B 2nd Pass to 5A Heater & Condenser M-12B MSR 2A & 2B 2nd Pass to 5B Heater & Condenser M-15B MSR 1B 4th Pass to 5A Heater M-17A MSR 2A 4th Pass to 5B Heater M-17B MSR 2B 4th Pass to 5B Heater M-18 MSR 2A & 2B 4th Pass to Condenser M-21 Steam Extraction to Preseparator Tank B & 4B L.P.H.

M-22 Steam Extraction to Preseparator Tank A & 4A L.P.H.

M-31 MSR 1A & 1B to Heater Drain Tank & Condenser M-32 MSR 2A & 2B to Heater Drain Tank M-41A 5A H.P. Heater Drain to 4A L.P. Heater M-41B 5B Heater Drain to 4B Heater M-45 Preseparator A/B to Heater Drain Tank & Condenser M-46B Preseparator A/B to Heater Drain Tank M-48 Auxiliary FW Pump A to Discharge Lines M-49 Auxiliary FW Pump B to Discharge Lines M-50 M.D. Aux. FW Pumps to T.D. F.W. Pumps Crossover M-71 Mainsteam from S/G 1A (Intermediate Building)

M-72 Mainsteam to Turbine (Turbine Building)

M-75 Steam Extraction to 5A & 5B Heaters M-81 Feedwater Discharge (Turbine Building)

M-82 Feedwater Discharge (Intermediate Building)

M-88D S/G Blowdown to Flash Tank (Turbine Building)

M-89A S/G 1A Blowdown Line (Inside Containment)

M-89B S/G 1B Blowdown Line (Inside Containment)

M-89C S/G 1B Blowdown Line (IC) to PEN. 322 16

R. E. GINNA NUCLEAR POWER PLANT

'Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

EROSION CORROSION MINWALL PROGRAM: Cont.

DWG.

NO SYSTEM M-90 Feedwater Clean Up (CV-18)

M-91 Feedwater Clean Up (CV-19)

M-92 Main Feedwater Pump Recirc.

M-93 Feedwater By-Pass Line M-98 S/G Blowdown Tank to Condenser M-99 Turbine Gland Steam from Generator 6 Governor Ends to Gland Steam Condenser M-100 Turbine Gland Steam Mainsteam to Turbine Generator 6 Governor Ends.

M-101 Turbine Gland Steam Condenser to Main Condenser A M-102 FW Heater Vents (Extraction Steam) from Heater Drain Tank to Extraction Steam Heater 4 M-103 Feedwater Heater Drain System from H.D. Pumps Discharge to H.D. Tank M-104 Condensate L.P. FW Heaters from L.P. FW Heaters 3 to L.P. FW Heaters 4 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: C -'7-Q Frank A. Klepacki Date ISI Engineer 17

R. Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

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: Z~L'C' 'Ci~ c/p ANII's Signature Date Approved By: ~ V Mi hae J. Saporit Manager, Materials Engineering NDE Level III 18

FORM NIS-1 OWNER>S REPORT FOR INSERVICE INSPECTIONS As required by thc Provisions of the ASME Code Rules Owner Rochester Gas 8 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 (Yamc and Address of I'lant)
3. Plant Unit 1 4. Owner Ccrtil>cate of Authorization (if required) N A
5. Commercial Service Date Jul 1970 f>. Yational Board Number for Unit N A
7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial Yo. Province No. Board No.

(*) SEE "ATTACHMENT I" Yotc: Supplcmcntal shccts in form of lists. sketches. or drawin< s may bc used, provided (I) size is 8-1/2 in. x I I in., (2) information in items I through 0 on this rcport is included m> each sheet. and (3) each shcct is nun>hcrcd and Ihc nun>l>cr of sheets is recorded at thc lop of this forn>.

8f>) 'Il>is form (IAI0~0) 7 n>ay bc obtained from thc Order Dept..

~ ASMI'2 I aw Driv. Box 2300. I'airficM. NJ07007-2300

/

I

FORM NIS-1 (Back)

Applicable Editions of Section XI 1986 Addenda No 1990 to 1999 Abstract of Examinations, Include a list of examinations and a statcmcnt concerning status of work rcquircd I'r current interval. (*)

Abstract of Conditions Yotcd. (*)

13. Abstract of Corrective Mcasurcs ltccommcndcd and Taken. (*)

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

Certificate of Authorization No.

Date 7 Jllrte (if applicablc) 19 93 N A Signed Iteejtcs<e< (oM>>

Owner Expiration Date L~~<<< B* N A c>g <+gt'Q CERTIFICATE OF INSERVICE INSPECTION I, thc undersigned, holding a valid commission issued by thc Yational Board of Boiler and Pressure Vessel Inspectors and thc State or I'rovincc or Yew York and cmploycd by llartford Stcam Boiler lns ction 8 Insurance Com ~n . of I-lartford Cf. have inspcctcd Ihc components dcscribcd in this Owner's IIcport during Ihc period to , and state that to thc best of my knowlcdgc and bclicf. thc Owner has pcrformcd aminations and taken corrcctivc Incasilrcs described in this Owner's l<cport in accordance with thc inspection plan and as rcquircd by thc SME Code.Section XI.

By signing this certificate ncithcr thc Inspccior nor his cmploycr makes any warranty. cxprcsscd or implied. concerning thc examinations and corrcctivc measures dcscril>cd in this Owner's Rcport. Eurihcrmorc. ncithcr thc Inspccior nor his cmploycr shall hc liable in any manner (or any personal injury or property damage or a loss of any kind arisin< from or connected with this inspection, Commissions M cP WPcP'ational Inspector's Signature Board. State, Province. and Lndorscmcnts Date IO 5'3

(*) SEE "ATTACHMENT I"

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I A. CLASS 1 COMPONENTS:

Al. REACTOR PRESSURE VESSEL DRAWINGS: A-1 Summary Exam Item NDE Number Categ Number Component Component: Type Exam 000701 B-N-1 B13.10 R.P.V. OE VT-3 VESSEL INTERIOR 93-REACTOR VESSEL: FLANGE SURFACE, VESSEL WALL FROM TOP OF FLANGE TO TOP OF UPPER CORE BARREL-ACCEPTABLE. UPPER INTERNALS ON STAND-NO RECORDABLE INDICATIONS-ACCEPTABLE. CORE BARREL IN VESSEL-ACCEPTABLE. VIDEO TAPE 781 AND 82. VT ACCEPTABLE.

A2. PRESSURIZER DRAWINGS: A'-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 005600 B-G-2 B7.20 MANWAY BOLTING OE VT-3 (16 TOTAL) UT MT 93-BASELINE: VT: INSIGNIFICANT, BOLTS 1 9 HAVE LINEAR INDICATIONS.

BOLT g8 HAS 7/16 LONG INDICATION, FORGING LAP-ACCEPTABLE. MT/UT NO RECORDABLE INDICATIONS ACCEPTABLE. 7 BOLTS REMOVED: VT/MT/UT: NO RECORDABLE INDICATIONS. UT: EXAMINED FROM BOTH ENDS ACCEPTABLE.

A3. STEAM GENERATORS DRAWINGS: A-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 006430 B-G-2 B7.30 INLET MANWAY NUTS AUG VT-1 NUTS (16 TOTAL) UT MT 93-VT: INSIGNIFICANTS SURFACE RUST Pl 6 16 ACCEPTABLE. MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

NOTE: "COMPONENT TYPE" IS DEFINED AS FOLLOWS!

"ASME"= ITEM REQUIRED BY ASME SECTION XI CODE "AUG" = AUGMENTED PROGRAM ITEM REQUIRED BY NRC COMMITMENT "OE" = OWNER ELECTED NON MANDATORY EXAMINATIONS 3

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

STEAM GENERATORS (CONT.) DRAWINGS: A-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 006435 B-G-2 B7.30 INLET MANWAY STUDS AUG VT-1 STUDS (16 TOTAL) UT MT 93-VT'NSIGNIFICANT, MINOR THREAD DAMAGE < 1/32" DEEP ON STUD f14 TOPS gl MIDDLE, 810 TOP & iF12 - BOTTOM; ACCEPTABLE. MTS NO RECORDABLE INDICATIONS ACCEPTABLE. UT; NO RECORDABLE INDICATIONS- EXAMINED FROM BOTH ENDS ACCEPTABLE.

006530 B-G-2 B7.30 OUTLET MANWAY NUTS AUG VT-1 NUTS (16 TOTAL) UT MT 93-VT/MT/UTS NO RECORDABLE INDICATIONS - ACCEPTABLE.

006535 B-G-2 B7.30 OUTLET MANWAY STUDS AUG VT-1 STUDS (16 TOTAL) UT MT 93 VT INSIGNIFICANT MINOR THREAD DAMAGE6 < 1 /32 6 ANY AREA AT THE TOP OF STUD NUMBER 3, 1, 4, 5, 14, 6 9 ACCEPTABLE. MT/UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

007430 B-G-2 B7.30 INLET MANWAY NUTS AUG VT-1 NUTS (16 TOTAL) UT MT 93-VT; INSIGNIFICANT - LIGHT RUST ON STUD NUMBER 8, 9, 6 10 ACCEPTABLE.

MT/UT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

Ra E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 197D S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

STEAM GENERATORS (CONT.) DRAWINGS: A-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 007435 B-G-2 B7.30 INLET MANWAY STUDS AUG VT-1 STUDS (16 TOTAL) UT MT 93 VT INSIGNIFICANT MINOR THREAD DAMAGE ON THE TOP OF STUD NUMBER 3 f 6 f

& 15'T THE BOTTOM OF STUD NUMBER 7. LIGHT RUST ON NUMBER 10 MIDDLE ACCEPTABLE. MT/UTS NO RECORDABLE INDICATIONS ACCEPTABLE.

007530 B-G-2 B7.30 OUTLET MANWAY NUTS AUG VT-1 NUTS (16 TOTAL) UT MT 93-VTS ZNSIGNIFICANT LIGHT RUST ON NUT f13 & g14f ACCEPTABLE. MT/UT NO RECORDABLE INDICATIONS ACCEPTABLE.

007535 B-G-2 B7.30 OUTLET MANWAY STUDS AUG VT-1 STUDS (16 TOTAL) UT MT 93-VTS INSIGNIFICANT MINOR THREAD DAMAGE ON TOP OF STUD g2f g3 & g7. LIGHT RUST ON THREADS ON STUD g9 MIDDLES f15 TOP ACCEPTABLE'T/UTj NO RECORDABLE INDICATIONS ACCEPTABLE.

A4. REACTOR COOLANT SYSTEM-LOOP A DRAWINGS! A-3B Summary Exam Item NDE Number Categ Number Component Component Type Exam 011300 B-J B9.11 PL-FW-IX ASME UT ELBOW-TO-ELBOW PT 93-REJECT; LINEAR INDZCATION & INSZGNIFICANT ROUNDED INDICATION. REEXAM AFTER SURFACE PREPARATIONS INSIGNIFICANTS INDICATION IS 3/32 LONGS ACCEPTABLE PER IWB-3514-2. SLAG POCKET IS FROM FABRICATION & NOT SERVICE INDUCED ACCEPTABLE'Tf GEOMETRYf ROOT & NO RECORDABLE INDICATIONS ACCEPTABLE'

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit jNA 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 020400 F-C F3.00 RCU-10 ASME VT-3 RIGID RESTRAINT 93-VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

020900 F-C F3.00 RCU-8 ASME VT-3 VARIABLE (SPRING) 93 TEMP ~ 61 DEG F ~ 6 SETTING 2 1/4 245 18 g S ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

021300 F-C. F3.00 RCU-6 ASME VT-3 VARIABLE (SPRING) 93-VTf NO RECORDABLE INDICATIONS 6 NON-SERVICE INDUCED REJECT: REJECT LOCKNUT UPPER BOLT OF PIPE CLAMP LACK OF THREAD ENGAGEMENT -2 THREADS.

ON RESOLUTIONf ISIM 016 3 31 93f CLAMP LOADED IN SHEARf 1 NUT FOR LOADINGf 1 FOR LOCKING IF TIGHT AGAINST LOAD NUTf USE AS IS PER ENGINEERING TEMP ~ 61 DEG ~

F., SETTING 2 3/8" = 405 g'S ACCEPTABLE.

A6. 2-IN. PRESSURIZER SPRAY LINE DRAWINGS: A-11 Summary Exam Item NDE Number Categ Number Component Component Type Exam 022500 F-C F3.00 CVU-65 ASME VT-3 VARIABLE (SPRING) 93-TEMP. 60 DEG. F., SETTING 1-1/2" = 179 g'S. CORNER LADA, S/N N-EG-13312-81-382. VTf NO RECORDABLE INDICATZONS ACCEPTABLE.

022700 F-C F3.00 CVU-67 ASME VT-3 RIGID RESTRAINT 93 VTf NO RECORDABLE INDICATIONS 6 INSIGNIFICANTf NO ZD TAG ACCEPTABLE ~

0 e

R. E. GINNA NUCLEAR POWER'LANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 ~oui 1970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

2-IN. PRESSURIZER SPRAY LINE (CONTe) DRAWINGS: A-ll Summary Exam Item NDE Number Categ Number Component Component Type Exam 022800 F-C F3.00 CVU-68 ASME VT-3 RIGID RESTRAINT 93-VT; NO RECORDABLE INDZCATZONS ACCEPTABLE.

023600 B-j B9.40 11 ASME PT ELBOW-TO-PIPE 93-PT'O RECORDABLE INDICATIONS ACCEPTABLE.

024700 B-K-1 B10.10 CVU-76 OE PT RIGID RESTRAINT IA 93 PTf INSIGNIFZCANTf ROUND INDICATION L 2 1/2 5 W 1/4 f 1/16 DIA f~

DOWNSTREAM SIDE OF SUPPORT ACCEPTABLE.

024750 F-C F3.00 CVU-76 ASME VT-3 RIGID RESTRAINT 93-VT'O RECORDABLE INDICATIONS 6 INSIGNIFICANT; MISALIGNMENT < 5 DEG.

ACCEPTABLE.

026000 B-J B9.40 27 AUG PT PIPE-TO-REDUCER RT 93 PT INSIGNIFICANT5 ROUND INDICATION 1/8 DIAMETERS L 1 3/4 5 W 3/4 DOWNSTREAM ACCEPTABLE PER IWB 35 14 2 ~ RT INS IGNIFI CANT 5 POROSITY 5 UNDERCUT 5 INTERNAL CONCAVITY5 TUNGSTEN ACCEPTABLE

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 1 COMPONENTS CONT.

Aj. H.P. SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 034300 B-J B9.11 H 'ASME UT PIPE-TO-VALVE 867A PT 93-PT/UT'O RECORDABLE INDICATIONS ACCEPTABLE.

A8. H.P. SAFETY INJECTION LINE DRAWINGS: A-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 040100 B-J B9.40 ASW-5 ASME PT PIPE-TO-ELBOW 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

A9. 2-IN. LETDOWN LINE DRAWINGS: A-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 044500 B-J B9.40 17 ASME PT TEE-TO-PIPE 93-PT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

A10. 2-IN. ALTERNATE CHARGING DRAWINGS: A-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 053000 B-J B9.40 35 ASME PT PIPE-TO-ELBOW 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

053200 B-J B9.40 37 ASME PT PIPE-TO-VALVE 383A UT 93-PT: REJECT 2 LINEAR INDICATIONS IN VALVE BODY. NCR93-102 GENERATED.

METALLURGICAL EXAM PERFORMED 6 DETERMINED TO BE A "MAN DEFECT" AND NOT SERVICE INDUCED'E EXAM AFTER BLENDINGf INSIGNIFICANTf POROSITY ACCEPTABLE'Tf OTHER THICKNESS MEASUREMENTS FOUND WALL TO BE AT THE REQUIRED MINIMUM WALL.

053300 B-J B9.40 38 AUG PT 383A VALVE-TO-PIPE UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: EXAM DEFERRED TO '94.

053700 B-J '9.40 42 ELBOW-TO-PIPE ASME PT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

054300 F-C F3.00 CVU-50 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANTf CHIPPED PAINT ACCEPTABLE.

055100 B-J B9.40 11 AUG PT 393 VALVE-TO-PIPE UT 93 PT NO RECORDABLE 6 INSIGNIFICANTj IND ¹1 f UNDERCUT 1/8 L X 1/64 DPf L 4 1/4 W 1/2 DOWNSTREAM ~ IND ¹2 7 UNDERCUT 1/8 L X 1/64 DPS L 4 3/4 6 W 1/2 6

DOWNSTREAM - ACCEPTABLE. UTf EXAM DEFERRED TO '94.

9

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.

All. REACTOR COOLANT PUMP A DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056701 B"G-1 B6.200 NUT ¹1 OE VT-1 BOLTZNGS REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNZFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINEDS NO RECORDABLE INDICATIONS ACCEPTABLE'56702 B-G-1 B6.200 NUT ¹2 VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, ZNSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LZMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90't COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056703 B-G-1 B6.200 NUT ¹3 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, ZNSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAM1NED, >90't COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056704 B-G-1 B6.200 NUT ¹4 VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDf >90't COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

10

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056705 B-G-1 B6.200 NUT ¹5 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS GOUGES. SMALL AMOUNT OF Ec PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056706 B-G-1 B6.200 NUT ¹6 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSZGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90'%OVERAGE OBTAINED, NO RECORDABLE INDICATZONS-ACCEPTABLE.

056707 B-G-1 B6.200 NUT ¹7 VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSZNG, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056708 B-G-1 B6.200 NUT ¹8 OE VT-1 BOLTING, REMOVED MT UT I

93 VT OUTS IDE OF NUT ONLY f INS IGN FICANT M 1 NOR NICKS 6 GOUGES SMALL AMOUNT OF

~

PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1979 S.National Board Number for Unit N~A ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056709 B-G-1 B6.200 NUT ¹9 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056710 B-G-1 B6.200 NUT ¹10 VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NZCKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING 6 /

1 6 OF NUT NOT EXAMINED f >9 0% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056711 B-G-1 B6.200 NUT ¹11 OE VT-1 BOLTING, REMOVED MT UT 93-VT OUTSIDE OF NUT ONLYS INSIGNIFICANT MINOR NICKS 6 GOUGES'MALL AMOUNT OF PAINT & OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90'%OVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056712 B-G-1 B6.200 NUT ¹12 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NZCKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE'T: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

12

R. Ee GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056713 B-G-1 B6.200 NUT 113 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056714 B-G-1 B6.200 NUT gl4 OE VT-1 BOLTING, REMOVED MT UT 93 VT I OUTS DE OF NUT ONLY 6 INS ZGNI F ICANT MINOR NICKS 6 GOUGES ~ SMALL AMOUNT OF PAZNT & OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90'%OVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056715 B-G-1 B6.200 NUT 815 OE VT-1 BOLTING, REMOVED MT UT 93"VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OZL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED- UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDf >90% COVERAGE OBTAINEDS NO RECORDABLE INDICATIONS ACCEPTABLE'56716 B-G-1 B6.200 NUT 416 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1970 6.National Board Number for Unit NjA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056717 B-G-1 B6.200 NUT ¹17 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT & 'OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056718 B-G-1 B6.200 NUT ¹18 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT &i OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90'%OVERAGE OBTAINED, NO, RECORDABLE INDICATIONS-ACCEPTABLE.

056719 B-G-1 B6.200 NUT ¹19 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT & OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSING, 1/6 OF NUT NOT EXAMINED, >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056720 B-G-1. B6.200 NUT ¹20 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSZDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS & GOUGES. SMALL AMOUNT OF PAINT & OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINEDS >90% COVERAGE OBTAINEDS NO RECORDABLE INDICATIONS ACCEPTABLE 14

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 ior Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056721 B>>G-1 B6.200 NUT ¹21 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MZNOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED'T:

LIMITED EXAM DUE TO PUMP HOUSINGB 1/6 OF NUT NOT EXAMINED6 >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056722 B-G-1 B6.200 NUT ¹22 OE VT-1 BOLTING, REMOVED MT UT 93-VT! OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NICKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGJ 1/6 OF NUT NOT EXAMINEDB >90% COVERAGE OBTAZNEDB NO RECORDABLE INDICATIONS ACCEPTABLE'56723 B-G-1 B6.200 NUT ¹23 OE VT-1 BOLTING, REMOVED MT UT 93-VT: OUTSIDE OF NUT ONLY, INSIGNIFICANT: MINOR NZCKS 6 GOUGES. SMALL AMOUNT OF PAINT 6 OIL RESIDUE-ACCEPTABLE'T: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUSINGS 1/6 OF NUT NOT EXAMINED'90'%OVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

056724 B-G-1 B6.200 NUT ¹24 OE VT-1 BOLTING, REMOVED MT UT 93 VT OUTS IDE OF NUT ONLY 6 INSIGNIFICANT MINOR NICKS 6 GOUGES SMALL AMOUNT OF ~

PAINT 6 OIL RESIDUE-ACCEPTABLE. MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:

LIMITED EXAM DUE TO PUMP HOUS ING g 1 / 6 OF NUT NOT EXAMINED6 >90% COVERAGE OBTAINED, NO RECORDABLE INDICATIONS-ACCEPTABLE.

15

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056801 B-G-1 B6.180 STUD ¹1 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056802 B-G-1 B6.180 STUD ¹2 OE UT BOLTINGS REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056803 B-G-1 B6.180 STUD ¹3 OE UT BOLTING f REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056804 B-G-1 B6.180 STUD ¹4 UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056805 B-G-1 B6.180 STUD ¹5 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

16

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056806 B-G-1 B6.180 STUD ¹6 OE UT BOLTING REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056807 B-G-1 B6.180 STUD ¹7 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT:,NO RECORDABLE INDICATIONS ACCEPTABLE.

056808 B-G-1 B6.180 STUD ¹8 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056809 B-G-1 B6.180 STUD ¹9 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056810 B-G-1 B6.180 STUD ¹10 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

17

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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. O~ner Certificate of Authorization (If Req.) ~N A S.commercial Service Date J~ul 797D S.National Board Number for Unit jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT.) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056811 B-G-1 B6.180 STUD Ill BOLTING, REMOVED UT VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056812 B-G-1 B6.180 STUD 412 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS-ACCEPTABLE. UT LIMITED EXAM, 83% VOLUME COVERED DUE TO INTERNAL CORROSION/OBSTRUCTIONSS COULD NOT EXAMINE BOTTOM 4 f UT CLEANING PROBE JAMMED IN STUD.

056813 B-G-1 B6.180 STUD f13 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056814 B-G-1 B6.180 STUD 414 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

t 056815 B-G-1 B6.180 STUD f15 OE UT BOLTZNG, REMOVED VT-1

'(24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

18

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 B.National Board Number tor Unit jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.

REACTOR COOLANT PUMP A (CONT ~ ) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056816 B-G-1 B6.180 STUD g16 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056817 B-G-1 B6.180 STUD 417 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE LIMITED EXAM OBSTRUCTIONa 904 OF VOLUME COVERED'56818 B-G-1 B6.180 STUD 118 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE. LIMITED EXAM, 80% OF VOLUME COVERED DUE TO INTERNAL CORROSION/OBSTRUCTIONN COULD NOT EXAMINE BOTTOM 4 ~ UT CLEANING PROBE JAMMED IN STUD.

056819 B-G-1 B6.180 STUD f19 OE UT BOLTING I REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056820 B"G-1 B6.180 STUD 120 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

19

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit jNA ATTACHMENT I CLASS 1 COMPONENTS CONT.  !

REACTOR COOLANT PUMP A (CONTe) DRAWINGS: A-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 056821 B-G-1 B6.180 STUD 7(l'21 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056822 B-G-1 B6.180 STUD f22 OE UT BOLTINGB REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER- NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056823 B-G-1 B6.180 STUD 423 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

056824 B-G-1 B6.180 STUD f24 OE UT BOLTING, REMOVED VT-1 (24 TOTAL) MT 93-VT/MT: OTHER: NOT REMOVED/NOT EXAMINED. UT: NO RECORDABLE INDICATIONS ACCEPTABLE'57300

---- ANCHOR BOLTS OE UT BOLTS 93-UT: NO RECORDABLE INDICATIONS 6 OTHER: EXAMINED IN PLACE - ACCEPTABLE.

BOLTING MEASURES 24" IN LENGTH.

20

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 1 COMPONENTS CONT.

A12. REACTOR COOLANT PUMP B DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 058100 FLYWHEL RG-1.14 FLYWHEEL AUG PT 212-3D19156"G01-02 UT 93-PT: NO RECORDABLE INDICATIONS IN BORE OR KEYWAYS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

058110 FLYWHEL RG-1.14 ANTI-ROTATION PAWLS AUG PT PAWLS (5) 93-ONLY 5 PAWLS ON THIS FLYWHEEL. PT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

B. CLASS 2 COMPONENTS:

Bl. NON-REGENERATIVE HEAT EXCHANGER DRAWINGS: B-2 Summary Exam Item NDE Number Categ j Number Component Component Type Exam VT-3 072280 L1 OE SUPPORT LEG ¹ 1 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

072285 ---- ---- L2 OE VT-3 SUPPORT LEG ¹ 2 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE. NOTE: SOME GENERAL LIGHT SURFACE CORROSION ACCEPTABLE.

072290 ---- ---- L3 OE VT-3 SUPPORT LEG ¹ 3 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 Becvice Date ~Jul 197D B.National Board Number Bor Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B2. SEAL WATER RETURN FILTER DRAWINGS: B-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 072570 L3 OE VT-3 SUPPORT LEG ¹ 3 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

072800 ---- ---- L3 OE PT SUPPORT LEG ¹ 3 93-PT: INSIGNIFICANTr RIGHT WELD L = 5-1/2"g CL ROUND INDICATION IN STOP 1/32me LEFT WELD L = 5", CL ROUND INDICATION IN STOP ACCEPTABLE.

B3. REACTOR COOLANT FILTER DRAWINGS: B-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 074700 L4 OE PT SUPPORT LEG ¹ 4 93-PT: INSIGNIFICANT; AT THE START OF THE LOWER LEG WELD CRATER LINEAR.

ALLOWABLE PER IWC 3510-3, FABRICATION INDICATION ACCEPTABLE.

074780 L4 VT-3 SUPPORT LEG ¹ 4 93-VT: INSIGNIFICANT; UNDERCUT < 1/32" DEEP ON LEG SIDE OF WELD ACCEPTABLE.

22

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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. O~ner Certificate of Authorization (If Req.) ~N A B.Commercial Service Date ~Jul 1970 B.National Board Number for Unit NjA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B4. PULSE DAMPENER DRAWINGS: B-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 077200 C-F-1 C5.11 6 OE PT PIPE-TO-ELBOW UT 93-LIMITATION FROM 0" - 11" DUE TO WELD SPATTER & PULSE DAMPENER SUPPORT LEG. PT:

NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B5 ~ SEAL WATER INJECTION FILTERS DRAWINGS: B-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 078000 LHSWSWIF-1 OE UT LOWER-HD-TO-SHELL CIRC. WELD 93 UT NO EXAM FROM 4 1/2 8 1/2 9 15 19 1/2 9 25 29 1/4 DUE TO SUPPORT LEGS. NO RECORDABLE INDICATIONS & GEOMETRY, GEOMETRY DUE TO SURFACE CONFIGURATION, WELD METAL & ROOT ACCEPTABLE.

B6. MAIN STEAM LOOP A DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 082700 C-F-2 C5.81 G2-BC-1 OE VT-1 6" BRANCH WELD MT 93-VT & MT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

083000 C-F-2 C5.81 G3-BC-1 MT 6" BRANCH WELD VT-1 93-VT & MT: NO RECORDABLE INDICATIONS NO CHANGE SINCE LAST INSPECTION ACCEPTABLE.

23

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B7. MAIN STEAM LOOP A 6-ZN. RISERS DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 084210 G3-BC3-A-BT OE VT-1 BOLTING (<2") MT UT 93-VT/MT: NO RECORDABLE INDICATIONS - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLEf SCANNED FROM BOTH ENDSf FIRST THREAD ENGAGEMENT Q 1 3/4 2 1/4.

BS. MAIN STEAM LOOP B DRAWINGS: B-10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 086325 F-C F3.50 MSU-12 ASME VT-3 MECHANICAL SNUBBER 93 S/N 94006 TEMP 48 DEG F 6 SETTING 3 5/16 ~ VT INSIGNIFICANTf NO ID . TAG PIGEON FECES ON SNUBBER SUPPORT ACCEPTABLE.

086330 C-C C3.20 MSU-12 ASME MT STANCHION TO PIPE IA 93-MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

090000 C-F-2 C5.81 L3-BC-3 OE MT 6" BRANCH WELD VT-1 93-VT: INSIGNIFICANTf UNDERCUT <1/32" DEEP ACCEPTABLE. REJECT: ARC STRIKE 3/4" LONG 9 L=16", 5/8" LONG 8 L=26m. MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

SURFACE CONDITIONING PERFORMED 6 RE EXAMINEDf VT ZNSZGNIFICANTf ARC STRIKES/

UNDERCUT REMOVED - ACCEPTABLE. MT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

REJECT IS NOT SERVICE INDUCED.

24

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 RecI.) ~N A B.commercial Service Date J~ul 197U B.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

MAIN STEAM LOOP B (CONT.) DRAWINGS: B-10A Summary Exam Item NDE Number Categ Number Component Component Type Exam 090200 C-F-2 C5.51 M ASME RT PIPE-TO-VALVE 3516 VT-1 MT 93-VT:INSIGNIFICANT; GENERAL GRINDING MARKS - ACCEPTABLE PER 1984 HIGH ENERGY EXAM

SUMMARY

SHEET NUMBER 200205. MT: ZNSIGNIFICANTf'EMAINS OF WELDED LUGS

- ACCEPTABLE PER HIGH ENERGY

SUMMARY

SHEET NUMBER 200205. RT: INSIGNIFICANT'ORESf SLAG 6 FILM ARTIFACTS ACCEPTABLE 090220 BWA OE MT 3" BRANCH WELD 93-MT: REJECT; LINEAR INDICATION AT L = 9 1/4", W = 1/2" UP, 3/16" ROUND.

RE-EXAM AFTER SURFACE CONDITIONING, WELD SIZE NOT REDUCED, WELL OVER 3/8" BY GAGE ACCEPTABLE. REJECT WAS DETERMINED TO BE NOT SERVICE INDUCED.

B9. MAIN STEAM LOOP B TO AUX FW PUMP TURBINE DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 090420 F-C F3.00 MSU-57 ASME VT-3 MECHANICAL SNUBBER 93-S/N 10161, TEMP. 70 DEG. F., SETTING 3 1/4", PSA-3. VT: NO RECORDABLE INDICATIONS-ACCEPTABLE.

25

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B10. FEEDWATER LOOP A DRAWINGS: B-11

)a Summary Exam Item NDE Number Categ Number Component Component Type Exam 091200 C-F-2 C5.51 2 ASME RT 3995 VALVE-TO-PIPE VT-1 MT 93-VT/MT: NO RECORDABLE INDICATIONS ACCEPTABLE. RT: INSIGNIFICANT POROSITY /

SLAG, MINOR EROSION OF BACKING RING NOTED ACCEPTABLE.

B11 ~ FEEDWATER LOOP B DRAWINGS: B-14 Summary Exam Item NDE Number Categ Number Compo'>ent Component Type Exam 094900 F-C F3.50 FWU-44 ASME VT-3 HYDRAULIC SNUBBER 93-VT: REJECT'LGBGER FULLY EXTENDED 6 LOW FLUID LEVEL, T/C WRITTEN. RE-EXAM AFTER CORRECTIVE MAINTENANCE. S/N G43864-02-20, TEMP. 74 DEG.F., SETTING 3 5/8" - ACCEPTABLE. INSIGNIFICANT; HYDRAULIC RESERVOIR MOUNTED INVERTED ACCEPTABLE.

096825 F-C F3.50 FWU-57 ASME VT-3 MECHANICAL SNUBBER 93-VT: NO RECORDABLE INDICATIONS, SETTZNG 2 3/4mf TEMP. 45 DEG. F., PSA-10.

INSIGNIFICANT: PIGEON FECES COVERS SNUBBER - ACCEPTABLE.

097100 F-B F2 00 F FWU-58 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE. INSIGNIFICANT PIGEON FECES COVERS RESTRAINT ACCEPTABLE.

26

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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.coaeeercial service Date J~ul 1970 S.National Board Number for Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

FEEDWATER LOOP B (CONTv) DRAWINGS: B-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 099900 C-F-2 C5.51 BB ASME VT-1 ELBOW-TO-NOZZLE MT UT 93-VT:INSIGNIFICANTS GRINDMARK < 1/32" DEEP. INSULATZON LUGS 9 +/- 1 1/2" FROM CL OF WELD Q 19 1/2 f 39 f TDCS TWELL 8 44 ACCEPTABLE'T NO RECORDABLE INDICATIONS ACCEPTABLE. UT: GEOMETRY'OOT/COUNTERBORE NO RECORDABLE INDICATIONS ACCEPTABLE. EXAM VOLUME> 90% ACCEPTABLE.

B12 L.PE SAFETY INJECTION LINE 8D-SI-301 DRAWINGS: B-16A Summary Exam Item NDE Number Categ Number Component Component Type Exam 106950 F-B F2.00 SIU-101 ASME VT-3 GUIDE 93 VT NO RECORDABLE INDICATIONSf NORTH GAP 1 /16 f SOUTH GAP < 1 1 6 /

ACCEPTABLE.

B13. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 108710 F-C F3. 50 RHU" 1 ASME VT-3 VARIABLE SPRING 93 VT NO RECORDABLE INDICATIONS 6 INSIGNIFICANTf TEMP ~ 61 DEG ~ F ~ f SETTING 3/4 818 LBS, LABEL PAINTED ACCEPTABLE.

108950 ---- ---- 16A PT 2" BRANCH WELD 93-PT ZNSIGNIFICANTS POROSITY ON 10 PIPES L Of W 3/4 f 1/8 DZAMETER UPSTREAM ACCEPTABLE.

27

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1979 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B14. 6-IN. SAFETY INJ. SYS (LOW HEAD) DRAWINGS: B-18 Summary Exam Item NDE Number Categ Number Component Component Type Exam 110800 C-F-1 ---- 1 OE PT TEE-TO-PIPE UT 93-PT: INSIGNIFICANTS LINE UP LUG 1/2" LONG. (FABRICATION USE) 6 UNDERCUT/POROSITY FABRICATION INDICATION - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRYS COUNTERBORE ACCEPTABLES NO APPARENT CHANGE SINCE 1985 B15, L ~ P ~ SAFETY INJECTION LINE FROM RWST DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 120300 F-B F2.00 RHU-100 ASME VT-3 RIGID SUPPORT 93-REJECT: DOES NOT MEET 1/4" FILLET, THE ACTUAL WELD IS FULL PENETRATION, 360 DEGREES. NCR93-071 GENERATED. RESOLUTION; AN ACCEPTABLE FULL PENETRATION TYPE WELD DOES EXIST AT THE PROCESS PIPE TO STANCHION INTERFACE. USE-AS-IS PER ENGINEERING ON 4/1/93. THIS IS NOT SERVICE INDUCED.

120301 C-C C3. 20 RHU-100 ASME PT STANCHION TO PIPE ZA 93 PT INSIGNIFICANTS INDICATION gl f 1/8 START/STOPS L 3 f W C/L ROUND ~

INDICATION 0 2 1 / 1 6 START/ STOP L 9 9 8 3/8 9 W C/L ROUND ACCEPTABLE ~

B16. RESIDUAL HEAT REMOVAL LINE 8FF-AC-151 DRAWZNGS: B-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 126500 7 OE PT TEE-TO-CAP UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS, ALL INDICATIONS WERE BELOW 50% DAC 6( GEOMETRIC ZN NATURE ACCEPTABLE.

28

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 2 COMPONENTS CONT.

RESIDUAL HEAT REMOVAL LINE 8FF-AC-151 (CONT.) DRAWINGS: B-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 126700 9 OE PT TEE-TO-CAP UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS GEOMETRY: INDICATION ¹ 1 6 2 GEOMETRY FROM ID SURFACE 6 REDIRECTION. OTHER GEOMETRIC INDICATIONS SEEN BELOW 50% DAC OR OUTSIDE AREA OF INTEREST ACCEPTABLE.

B17. RESIDUAL HEAT REMOVAL LINE 6E-AC-151 DRAWINGS: B-21 Summary Exam Item NDE Number Categ Number Component Component Type Exam 128300 ---- ---- RHU-85 OE VT-3 RIGID SUPPORT 93 VT INS IGNIFICANT CHI PPED PAINTS LIGHT RUST ON BASE PLATE f RUST UNDER PIPES T/C GENERATED. WELD ON TOP PLATE 2 SIDES ONLY ACCEPTABLE.

128305 ---- ---- RHU-85 OE PT STANCHION TO PIPE IA 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B18. RESIDUAL HEAT REMOVAL LINE 8F-AC-151 DRAWINGS: B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 128800 7 OE PT TEE-TO-CAP UT 93 PT NO RECORDABLE I I ND CAT IONS 7 RESTRICTED BY CE ILING 6 WALL LIMITATION FROM

~

4 1/2" TO 15", GROUT ON WELD ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

29

R. Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 2 COMPONENTS CONT.

B19. RESIDUAL HEAT REMOVAL LINE 10A-AC-601 DRAWINGS: B-22 Summary Exam Item NDE Number Categ Number Component Component Type Exam 135300 C-F-1 12 OE PT ELBOW-TO-PIPE (PEN 140) UT 93-PT: NO RECORDABLE INDICATIONS - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

135900 C-F-1 ---- 16 OE PT PIPE-TO-ELBOW UT 93-PT: NO RECORDABLE INDICATIONS - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS GEOMETRYS INTERMITTENT ROOT GEOMETRY'OTE GEOMETRIC MODE CONVERSION SIGNAL SEEN OUTSIDE AREA OF INTEREST ACCEPTABLE.

B20. RESIDUAL HEAT REMOVAL LINE SD-AC-601 DRAWINGS: B-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 144900 C-F-1 5 OE PT VALVE 709B-TO-TEE UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B21. RESIDUAL HEAT RENOVAZS TO LOOP B COLD LEG DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 153200 F-B F2.10 RHU-54 ASME VT-3 RIGID SUPPORT 93 - VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

30

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1990 B.National Boned Number for Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG (CONT.) DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component; Component Type Exam 153220 C-C C3.20 RHU-54 ASME PT STANCHION WELD ZA 93 PT INSIGNIFICANTJ ROUNDED INDICATION L N 0 I W 0 N CL 1/8 DIAMETER ACCEPTABLE.

B22. RESIDUAL HEAT REMOVAL LINE 6C-AC-601 DRAWINGS: B-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 156000 F-B F2.40 RHU-105 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

B23. RESIDUAL HEAT REMOVAL LINE 8X-AC-601 DRAWINGS: B-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 158630 C-F-1 ---- 2A OE PT PIPE-TO-TEE UT 93-PT: NO RECORDABLE INDICATIONS - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY, ROOT GEOMETRY 360 DEGREE INTERMITTENT - ACCEPTABLE'OTE OTHER GEOMETRIC INDICATIONS SEEN BELOW 50% DAC.

31

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period,'irst Outage (1993)

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 ~NN ATTACHMENT I CLASS 2 COMPONENTS CONT.

B24. L.P. SAFETY INJECTION LINE FROM RWST DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 159100 F-B F2. 00 RHU-101 ASME VT-3 RIGID SUPPORT 93-VT: NO RECORDABLE INDICATIONS 6( INSIGNIFICANT'O ID TAG. REJECT: DRAWING SPECIFIES WELD ON 2 1/2 SIDE NOT 3 1/2 SIDE. NCR93-072 GENERATED. CONDITION ACCEPTABLE PER DA ME 93 0576 USE AS IS PER ENGINEERINGf NOT SERVICE INDUCED ACCEPTABLE.

159105 C-C C3 . 20 RHU-101 ASME PT STANCHION TO PIPE IA 93 PT INSIGNIFICANTf PINHOLES IN WELD CAPS L 3 3/4 6 W CLS CL 1/8 ROUNDS L = 4,1/4, W = CL, CL 1/16 ROUND. COLD LAP PRESSURE BOUNDARY SIDE OF FILLET WELD f W 13 1/4 6 W 1/8 6 1/8 LINEARf 1/8 ACCEPTABLE PER ASME SECTION XZ f IWB 3514 2 ~

B25. L.P. SAFETY INJECTION LINE 8B-SI-151 DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 159900 F-C F3.50 RHU-129 ASME VT-3 VARIABLE(SPRING) SUCCESSIVE 93 VT NO RECORDABLE INDICATlONSf S/N IDN EG 13312 81 372BS CORNER LADA SIZE 7 f TEMP. 75 DEG. F., SETTING 1.25" = 672 POUNDS,- ACCEPTABLE.

B26. L.P. SAFETY INJECTION LINE 8A-SI-151 DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 160430 3 OE PT 2" BRANCH WELD 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

32

0 0

0

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 B.National Board Number for Unit N~A ATTACHMENT I CLASS 2 COMPONENTS CONT.

B27. H.P. SAFETY INJECTION LINE 3A-SI-1501 DRAWINGS: B-37 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161100 F-C F3.50 SIU-84 ASME VT-3 VARIABLE SPRING 93 VT INS IGNI FI CANT 7 5/8 ROD XS RUBBING AGAINST CONDUIT 6 NO APPARENT WEAR 6 TEMP ~ 75 DEG F 7 SETTING 5 1 5 LBS 6 CORNER LADA SI ZE 7 ACCEPTABLE ~

161101 C-C C3. 20 SIU-84 ASME PT LUG TO PIPE IA 93-PT: NO RECORDABLE INDXCATIONS ACCEPTABLE.

161270 F-'B F2.30 SIU-75 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

161280 C-F-1 C5.21 19 OE PT PIPE-TO-ELBOW UT 93-PT/UT: NO RECORDABLE INDICATXONS ACCEPTABLE.

B28. H.P. SAFETY INJECTION LINE 2T-SI-2501 DRAWINGS: B-39 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161880 C-F-1 C5.30 16 OE PT ELBOW TO PIPE 93 PT INSIGNIFICANTf ROUND PIT 1/32 DEEP X 1/16 ROUND 6 L 3 7/86 W 1/166 UPSTREAM ACCEPTABLE.

161900 F-B F2.40 SXU-37 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

33

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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'ervice Date ~Jul 1970 S.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B29. H.P. SAFETY INJECTION LINE 2U-SI-2501 DRAWINGS: B-39 Summary Exam Item NDE Number Categ Number Component Component Type Exam 162170 F-B F2.30 SIU-31 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B30. H.P. SAFETY INJECTION LINE 3B-SI-1501 DRAWINGS: B-40 Summary Exam Item NDE Number Categ Number Component Component Type Exam 162630 C-F-1 C5.21 9 OE PT ELBOW-TO-PIPE UT 93-PT/UT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

B31. H.P. SAFETY INJECTION LINE 3C-SI-,1501 DRAWINGS: B-41 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163000 C-F-1 C5.21 1 OE PT TEE-TO-PIPE UT 93-PT/UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B32. H.P. SAFETY INJECTION LINE 3E-SI-1501 DRAWINGS: B-42 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163570 C-F-1 C5.21 8 OE PT VALVE 888B TO PIPE UT 93-PT/UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 B.National Board Number for Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

HaP ~ SAFETY INJECTION LINE 3E-SI-1501 (CONT.) DRAWINGS: B-42 Summary Exam Item NDE Number Categ Number Component Component Type Exam 163820 F-B F2. 10 SIU-58 ASME VT-3 RIGID SUPPORT SUCCESSIVE 93-VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

163830 F-B F2.30 SIU-57 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

B33. H.P. SAFETY INJECTION LINE 2D-SI-1501 DRAWINGS: B-44 Summary Exam Item NDE Number Categ Number Component Component Type Exam 164550 C-F-1 C5.30 6 OE PT PIPE TO VALVE 878C 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B34. H.P. SAFETY INJECTION LINE 2S-SI-2501 DRAWINGS: B-44 Summary Exam Item NDE Number Categ Number Component Component Type Exam 164670 F-B F2.30 SIU-26 ASME VT-3 ANCHOR 93-VTf'O RECORDABLE INDICATIONS ACCEPTABLE.

164672 C-C C3.20 SIU-26 ASME PT GUSSET TO PIPE IA 93-PT: INSIGNIFICANT: SMALL PORE AT EDGE OF WELD, MINIMAL BLEEDOUT ON THE PLATE SIDE, L= 2 3/8", W= -

3/16" DOWNSTREAM, ROUNDED 1/32" DIAMETER ACCEPTABLE.

35

R: E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B35 ~ H P ~ SAFETY INJECTION LINE 2R-SI-2501 DRAWINGS: B-45 Summary Exam Item NDE Number Categ Number Component Component Type Exam 164880 C-F-1 C5.30 8 OE PT PIPE TO TEE 2X2X2 93 PT INS IGNIFI CANT ROUND INDICATZON 1 /8 DZAMETERf L 4 6 W 3/8 DOWNSTREAM ACCEPTABLE PER IWB 3514-2. LIMITED EXAM PIPE SIDE GUIDE 6 PAINT AT. TOE OF WELD ACCEPTABLE.

164890 C-F-1 C5.30 9 ASME PT TEE TO REDUCER 93-PT: INSIGNIFICANTf INTERMITTENT UNDERCUT REVEALED BY VT (NOT PT) ON REDUCER.

INDICATION IS ROUNDED AT THE BOTTOM AND DOES NOT EXCEED THE MINWALL OF THE REDUCER. THIS ITEM HAS BEEN INSERVICE FOR SEVERAL YEARS AND IS A FABRICATION DEFECT ACCEPTABLE.

B36. CONTAINMENT SPRAY LINE: 6D-SI-301 DRAWINGS: B-46 Summary Exam Item NDE Number Categ Number Component Component Type Exam 166520 C-F-1 3 OE PT ELBOW-TO-PIPE UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS GEOMETRY, ROOT GEOMETRY ACCEPTABLE. NOTE: 2 INDICATIONS SEEN OUTSIDE AREA OF INTEREST.

B37. CONTAZNMENT SPRAY LINE: 6L-SZ-301 DRAWINGS: B-47 Summary Exam Item NDE Number Categ Number Component Component Type Exam 168000 1 OE PT 2" BRANCH WELD 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: WELD CROWN IS ROUGH AND HAS SOME VERY MINOR (< 1/32") UNDERCUTTING.

36

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 2 COMPONENTS CONT.

B38. SERVICE WATER LINE 8J-SW-125 DRAWINGS: B-51 Summary Exam Item NDE Number Categ Number Component Component Type Exam 173790 C-C C3.20 SWU-85 ASME MT GUIDE IA 93-MT: NO RECORDABLE INDICATIONS ACCEPTABLE. 4 LUGS EXAMINED, WELDED ONE SIDE ONLY AS PER DRAWING ACCEPTABLE.

173800 F-B F2.00 SWU-85 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

B39. SERVICE WATER LINE 8F-SW-125 DRAWINGS: B-52 Summary Exam Item NDE Number Categ Number Component Component Type Exam 174500 F-B F2.00 SWU-90 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B40. SERVICE WATER LINE 8E-SW-125 DRAWINGS: B-52B Summary Exam Item NDE Number Categ Number Component Component Type Exam 174840 C-F-2 C5.51 29 OE PT TEE-TO-REDUCER PARTIAL UT 93-PT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: RESCHEDULE TO 1994, INACCESSIBLE.

174910 F-C F3.00 SWU-54 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

37

R. E. GINNA NUCLEAR POWER PLANT Inservi;ce Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 197U 6.National Board Number for Unit jNA ATTACHMENT I CLASS 2 COMPONENTS CONT.

SERVICE WATER LINE 8E-SW-125 (CONT.) DRAWINGS: B-52B Summary Exam Item NDE Number Categ Number Component Component Type Exam 174980 F-C F3.00 SWU-50 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

175070 F-B F2.00 SWU-46 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT, LIGHT RUST ON LUGS ACCEPTABLE.

B41. SERVICE WATER LINE 8B-SW-125 DRAWINGS'-53 Summary Exam Item NDE Number Categ Number Component Component Type Exam 175410 F-B F2.00 SWU-39 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

175480 F-C F3.00 SWU-43 ASME VT-3 RIGID RESTRAINT 93-VT: INSIGNIFICANT: ANGLE IRON FOR CATWALK WITHIN 3/16" OF RIGID SUPPORT.

REJECT: PAINT ON SWIVEL SOCKETS. RESOLUTION: SLIGHT PAINT OVERSPRAY ON PADDLE IS ACCEPTABLE PROVIDING IT DOES NOT RESTRICT BUSHING MOVEMENT. USE-AS-IS PER ENGINEERING ACCEPTABLE.

38

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage,(1993)

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. O~ner Certificate of Authorization (If Req.) ~N A B.corttercial Service Date ~Jul 197D 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 2 COMPONENTS CONT.

B42. SERVICE WATER LINE 8A-SW-125 DRAWINGS: B-53A Summary Exam Item NDE Number Categ Number Component Component Type Exam 175670 F-C F3.00 SWU-13 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

175770" F-C F3. 00 SWU-18 ASME VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B43. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS: C-20 S umma ry Exam Item NDE Number Categ Number Component Component Type Exam 176080 AFU-215 (AFW-17 ) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS 6 OTHER: UNABLE TO INSPECT 4 SPOTS DUE TO LUG RESTRICTIONf 95't OF WELD AREA EXAMINED ACCEPTABLE'76081

---- AFU-215 (AFW-17) OE PT GUIDE - IA 93-PT: NO RECORDABLE INDICATIONS 6 OTHER: UNABLE TO INSPECT 4 SPOTS DUE TO LUG RESTRICTIONS, 95% OF WELD AREA EXAMINED - ACCEPTABLE.

176360 ---- ---- AFU-229 VT-3 HYDRAULIC SNUBBER 93 VT NO RECORDABLE INDICATIONS 6 ZNSIGNIFICANTf SETTING 2 1/4 f TEMP 71 DEG ~

F., SNUBBER INVERTED 90 DEGREES - ACCEPTABLE.

39

I (

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 CLASS 2 COMPONENTS CONT.

B44. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWINGS: C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 176460 AFU-201 (AFW-06) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

C. CLASS 3 COMPONENTS:

Cl. COMP. COOL.HT.EXCHS.TO RESIDUAL HT.EXCHS. DRAWINGS: C-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500540 D-B D2.20 CCU-139 ASME VT-3 GUIDE IA 93-VT: INSIGNIFICANT HEAVY CORROSION/SLAG. REJECT: 3/4" LUG WELD ON RIGHT SIDE MZSSING, NCR93-073 GENERATED. BASED ON FUNCTION OF SUPPORT, ALL LUG-PIPE WELDS ARE IN COMPRESSIONf MISSING WELD LENGTH HAS NO IMPACT TO OPERABILITYS USE-AS-IS PER ENGINEERING ACCEPTABLE.

500545 F-A F1.00 CCU-139 ASME VT-3 GUIDE 93-VT: INSIGNIFICANT: MINOR CORROSION ON GUIDE - ACCEPTABLE.

C2. AUX. COOL. WTR. TO PEN 124, 127,128 6 131 DRAWINGS: C-5 Summary Exam Item NDE

'Number Categ Number Component Component Type Exam 500710 D-B D2.20 CCU-151 ASME VT-3 RIGID RESTRAINT IA 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

40

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 d~ul 197D S.National Board Number for Unit Nja ATTACHMENT I CLASS 3 COMPONENTS CONT.

AUX ~ COOL ~ WTR ~ TO PEN 1249 127 f 128 6 13 1 (CONT ) DRAWINGS C 5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500715 F-C F3.00 CCU-151 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: STRUT END. APPROX. 1/64" AWAY FROM 12 CCW SUPPLY LINES POSSIBLE WEARS TO BE CHECKED ON T/C ACCEPTABLE'3.

COMP. COOL.PMPS.,SUC.FM RES.HT.EX.G SG.TK DRAWINGS: C-6 Summary Exam 1tem NDE Number Categ Number Component Component Type Exam 500790 D-B D2.40 CCU-160 ASME VT-3 VARIABLE SPRING IA 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

500795 F-C F3.00 CCU-160 ASME VT-3 VARIABLE SPRING 93 VT NO RECORDABLE INDICATIONSf TEMP 73 DEG ~ F ~ f SETTING 3/4 1923 g Sf Sl ZE 12 - ACCEPTABLE.

500840 D-B D2.40 CCU-169 ASME VT-3 VAR1ABLE SPRING IA 93-VT: NO RECORDABLE INDICATIONS; REJECT; FLAME CUT OD INTEGRAL ATTACHMENT CAUSED GOUGES IN ELBOW. NCR93-070 GENERATED. NON-CONFORMANCE IS ACCEPTABLE BASED ON DESIGN ANALYSIS ME-93-051. USE-AS-IS PER ENGINEERING, NOT SERVICED INDUCED.

500845 F-C F3.00 CCU-169 ASME VT-3 VARIABLE SPRING 93 TEMP 67 DEG F f SETTING 7 /8

~ 1 99 1 g S VT RE JECT f BROKEN COTTER PINS NOT SERVICE INDUCED. NCR93-070 GENERATED. RESOLUTION'EPLACED COTTER PIN, NO RECORDABLE INDICATIONS - ACCEPTABLE.

41

0 R~ E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT.

COMP. COOL.PMPS.,SUC.FM RES.HT.EX.R SG.TK (CONTa) DRAWINGS: C-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500850 D-B D2.20 CCU-170 ASME VT-3 GUIDE IA 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

500855 F-A F1.00 CCU-170 ASME VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

C4, AUX.COOL. IN & OUT FOR BORIC ACID EVAPOR. DRAWINGS: C-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 500920 D-B D2.20 CCU-129 ASME VT-3 ANCHOR IA 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

500925 F-A F1.00 CCU-129 ASME VT-3 ANCHOR 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

C5. AUX.COOL.WTR.FRM RV SUP.COOL.TO PEN 130 DRAWINGS: C-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 501400 CCU-17 OE VT-3 ANCHOR IA 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: PAINTED - ACCEPTABLE.

501405 CCU-17 OE VT-3 ANCHOR 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: PAINTED ACCEPTABLE.

42

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 7970 S.National Board Number for Unit jNA ATTACHMENT I CLASS 3 COMPONENTS CONT.

C6. SW COMP. COOL.& SP.FUEL PIT HT EXS.,DISCH DRAWINGS: C-ll Summary Exam Item NDE Number Categ Number Component Component Type Exam 501600 D-C D3.20 SWU-158 ASME VT-3 RIGID HANGER IA 93-VT: NO RECORDABLE INDICATIONS & INSIGNIFICANT: LIGHT OXIDATION ON COMPONENT LEGS ACCEPTABLE.

501605 F-A F1.00 SWU-158 ASME VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

I C7. SVC.WTRe-TO COMP. COOL.& SP.FL.PZT HT.EXS. DRAWINGS: C-12 Summary Exam Item NDE Number Categ Number Component Component. Type Exam 502039 D-B D2.20 SWU-208 ASME VT-3 RIGID HANGER IA 93-VT: NO RECORDABLE INDICATIONS & INSIGNIFICANT: LIGHT OXIDATION ON LUG ACCEPTABLE.

502040 F-C F3.00 SWU-208 ASME VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

C8 ~ SVC.WTR.-FROM PEN ~ 308,311,315 & 323 DRAWINGS: C-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 502400 D-B D2.20 SWU-291 ASME VT-3 RIGID RESTRAINT IA 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993) 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 197D 6.National Board Number for Unit jNA ATTACHMENT I CLASS 3 COMPONENTS CONT.

SVC WTR ~ FROM PEN ~ 308 f 3 1 1 f 3 15 a 323 (CONT ~ ) DRAWINGS: C-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 502405 F-C F3.00 SWU-291 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

502530 D-B D2.20 SWU-312 ASME VT-3 RIGID RESTRAINT IA 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

502535 F-C F3.00 SWU-312 ASME VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

C9. AUX. FW PUMPS DISCH - INTERMED. BLDG. DRAWINGS: C-1F Summary Exam Item NDE Number Categ Number Component Component Type Exam 505030 D-B D2.40 AFU-11 ASME VT-3 VARIABLE SPRING IA 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505035 F-C F3.00 AFU-11 ASME VT-3 VARIABLE SPRING 93-TEMP. 69 DEG. F., SETTING 395 LBS. VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505240 F-C F3.00 AFU-101 OE VT-3 MECHANICAL SNUBBER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

44

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 7970 6.National Board Number for Unit ~NA ATTACHMENT I CLASS 3 COMPONENTS CONT.

AUX. FW PUMPS DISCH INTERMED. BLDG. (CONT.) DRAWINGS: C-1F Summary Exam Item NDE Number Categ Number Component Component Type Exam 505250 F-A F1.00 AFU-102 OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505290 F-C F3.00 AFU-31 OE VT-3 MECHANICAL SNUBBER 93 S/N 24452 f TEMP ~ 70 DEG F~ f SETTING 2 f PSA 1 VT NO RECORDABLE INDICATIONS ACCEPTABLE.

505300 F-A F1.00 AFU-32 OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505480 F-A F1.00 AFU-50 OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505550 D-B D2. 20 AFU-105 ASME VT-3 ANCHOR IA 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

505555 F-A F1.00 AFU-105 ASME VT-3 ANCHOR 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505614 F-A F1.00 AFU-88 OE VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

45

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNN ATTACHMENT I CLASS 3 COMPONENTS CONT.

AUX. FW PUMPS DISCH INTERNED. BLDG. (CONT.) DRAWINGS: C-1F Summary Exam Item NDE Number Categ Number Component Component Type Exam 505630 F-C F3.00 AFU-63 OE VT-3 RIGID RESTRAINT 93-VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

505700 F-B F2.00 AFU-70 OE VT-3 RIGID SUPPORT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE. NOTE: S.E. HILTI CUT-OFF 6 GROUND FLUSH.

505730 F-C F3.00 AFU-73 OE VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

505740 F-C F3.00 AFU-74 OE VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505920 F-C F3.00 AFU-83 OE VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

505930 F-C F3.00 AFU-84 OE VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 nate ~Jul 1970 S.National Board Number for Unit jma ATTACHMENT I CLASS 3 COMPONENTS CONT.

C10. STANDBY AUX FW FRM PEN 119 AUX FW PUMP C DRAWINGS: C-22 Summary Exam Item NDE Number Categ Number Component Component Type Exam 507440 F-A F1.00 AFU-154 (AFW-95) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

507470 F-A F1.00 AFU-150 (AFW-122) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: ID TAG BROKEN OFF (LEFT LOOSE ON SUPPORT).

507510 F-A F1.00 AFU-157 (AFW-99) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

507550 F-A F1.00 AFU-195 (AFW-103) OE VT-3 GUIDE 93-VT: NO'RECORDABLE INDICATIONS ACCEPTABLE.

Cll. STANDBY AUX FW FRM PEN 123 - AUX FW PUMP D DRAWINGS: C-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508165 F-A F1.00 AFU-236 (AFW-54) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

508430 F-A F1.00 AFU-186 (AFW-108) VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

47

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 (Zf Req.) ~N A 6 Co.mmercial Service Date ~Jul 1970 B.National Board Number for Unit jNA ATTACHMENT I v

CLASS 3 COMPONENTS CONT.

STANDBY AUX FW FRM PEN 123 - AUX FW PUMP D (CONT.) DRAWINGS: C-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 508460 F-A F1.00 AFU-190 (AFW-123) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE. NOTE: TAG REMOVED, LAYING ON SUPPORT.

C12 ~ STANDBY AUX'Wf SW SUPPLY TO SAFW PUMP C DRAWINGS: C-28 Summary Exam Item NDE Number Categ Number Component Component Type Exam F-A F1.00 SWU-595 (SW-127) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

C13. STANDBY AUX. FW, SW SUPPLY TO SAFW PUMP D DRAWINGS: C-28 Summary Exam Item NDE Number Categ Number Compo~cent Component Type Exam 508945 F-A F1.00 SWU-519 (SW-137) OE VT-3 GUIDE 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

C14. SAFW PUMPS C & D SUCTION CROSSOVER DRAWINGS: C-29 Summary Exam Item NDE Categ 'umber Number Component Component Type Exam 508985 SWU-601 (SW-133) OE VT-3 ANCHOR - IA 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

508987 SWU-601 (SW-133) OE VT-3 ANCHOR 93-VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

R. E" GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1970 6.National Board Number for Unit jNA ATTACHMENT I D. HIGH ENERGY COMPONENTS:

Dl. MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: HE-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200005 HE-DB ---- D AUG VT-1 PIPE-TO-ELBOW PEN. 401 RT MT 93-VT: NO RECORDABLE ZNDICATIONS & INSIGNIFICANTS PITS 1/16" DIAMETER X < 1/32" DEEPS LIGHT GRIND MARKS'T NO RECORDABLE INDICATIONS ACCEPTABLE'T NO RECORDABLE INDICATIONS & INSIGNIFICANTj SLAGS POROSITYS INTERNAL CONCAVITY ACCEPTABLE.

200010 HE-DB ---- Dl AUG VT-1 ELBOW-TO-PIPE MT UT 93-VT: NO RECORDABLE INDICATIONS & INSIGNIFICANT: MINOR BASE METAL PITTZNG &

GRIND MARKSS AS GROUND CONDITIONS UNDERCUT < 1/32 ACCEPTABLE'T NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS &

GEOMETRYS'OOT & COUNTERBORE ACCEPTABLE.

D2. MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: HE-2A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200030 HE-DB D AUG VT-1 PIPE-TO-ELBOW PEN. 402 RT MT 93 VT & MT 5 NO RECORDABLE IND ICATIONS ACCEPTABLE ~ RTf NO RECORDABLE IND ICATIONS

& INSIGNIFICANTS SLAG & POROSITY ACCEPTABLE ~

49

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit ~NA ATTACHMENT I HIGH ENERGY COMPONENTS CONT.

D3. FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200070 HE-DB ---- AA AUG VT-1 PIPE-TO-PIPE UT MT 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: WELD PREP-MINOR GRIND MARKS 360 DEGREES ACCEPTABLE. MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY; COUNTERBORE 6 ROOT GEOMETRY ACCEPTABLE, D4. FEEDWATER LOOP B OUTSIDE CV DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200080 HE-DB F4 AUG VT-1 ELBOW-TO-PIPE UT MT 93-VT/MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS GEOMETRY; COUNTERBORE 6c ROOT GEOMETRY- ACCEPTABLE.

200090 HE-DB V AUG VT-1 ELBOW-TO-PIPE PEN. 404 UT MT 93-MT: NO RECORDABLE INDICATIONS ACCEPTABLE. VT: NO RECORDABLE INDICATIONS INSIGNIFICANT; MINOR GRIND MARKS DUE TO AS GROUND CONDITION, ALSO IN '90 ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY; COUNTERBORE 6 ROOT, ALSO ZN '90 - ACCEPTABLE.

50

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 HIGH ENERGY COMPONENTS CONT.

D5. MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: HE-1A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200145 HE-CB ---- H AUG VT-1 PIPE-TO-VALVE 3517 RT MT 93-VT & MT: NO RECORDABLE INDICATIONS ACCEPTABLE. RT: NO RECORDABLE INDICATIONS

& INSIGNIFICANT; SLAG & POROSITY, ACCEPTABLE.

200150 HE-CB ---- J VT-1 3517 VALVE-TO-PIPE UT MT 93-VT/MT: NO RECORDABLE INDICATIONS, NO CHANGE SINCE LAST INSPECTION ACCEPTABLE. RT: NO RECORDABLE INDICATIONS & INSIGNIFICANTs SLAG & POROSITY ACCEPTABLE.

D6. hOLIN STEAM LOOP B OUTSIDE CV DRAWINGS: HE-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200205 HE-CB M AUG VT-1 PIPE-TO-VALVE 3516 RT MT 93-VT: NO RECORDABLE INDICATIONS & INSIGNIFICANTS GENERAL GRIND MARKS & UNDERCUT FROM LUGS >1/32". MT: INSIGNIFICANTS REMAINS OF WELDED LUGS. VT & MT I

ACCEPTABLE PER 1 984 EXAM RT INS IGN FICANT9 PORES 6 INTERNAL CONCAVITY & SLAG ACCEPTABLE.

200210'E-CB ---- N AUG VT-1 3516 VALVE-TO-PIPE RT MT 93-VT: NO RECORDABLE INDICATIONS & INSIGNIFICANT'RIND MARKS FROM PREP & WELD SPATTER FROM LINE-UP LUGS-ACCEPTABLE. MT: NO RECORDABLE RT: NO RECORDABLE INDICATIONS & INSIGNIFICANT; SLAG INDICATIONS'CCEPTABLE.

ACCEPTABLE'1

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 797D 6.National Board Number for Unit jNA ATTACHMENT I HIGH ENERGY COMPONENTS CONT.

D7. MAIN STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Exam Item NDE Number Categ Number Component Component Type Exam 200260 HE-CB ---- A AUG VT-1 TEE-TO-PIPE UT MT 93 VT NO RECORDABLE INDICATIONS 6 INS IGNI FICANT( LIGHT GRIND MARKS f POROS ITY OPEN TO SURFACE 1/32" DIAMETER OR LESS ACCEPTABLE. MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE ZNDICATIONS, INSIGNIFICANT OTHER('OOT & COUNTERBORE GEOMETRY ACCEPTABLE.

D8. FEEDWATER TURBINE BUILDING DRAWINGS: HE-6 Summary Exam Item NDE Number Categ Number Component Component, Type Exam 200310 HE-CB M AUG VT-1 ELBOW-TO-PIPE MT UT 93-VT: NO RECORDABLE 6 INSIGNIF1CANT; ZNTERMITTENT UNDERCUT <1/32" 9 BOTH WELD TOES, MINOR COMPONENT MISMATCH 6 GRIND MARKS ACCEPTABLE. MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6(

6 ROOT - ACCEPTABLE.

GEOMETRY'OUNTERBORE 200355 HE-CB ---- G AUG VT-1 ELBOW-TO-PIPE UT MT 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; MINOR GRZND MARKS - ACCEPTABLE.

MT: NO RECORDABLE INDICATIONS ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY; ROOT 6( ID PIPE GEOMETRY - ACCEPTABLE.

52

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 797D S.National Board Number for Unit jNA ATTACHMENT I HIGH ENERGY COMPONENTS CONT.

D9. FEEDWATER LOOP A OUTSIDE CV DRAWZNGSr HE-3 Summary Exam Item r NDE Number Categ Number Component Component Type Exam 200440 HE-CB Z AUG VT-1 3995 VALVE-TO-PIPE RT MT 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT MINOR GRIND MARKS -ACCEPTABLE.

MT: NO RECORDABLE INDICATIONS -ACCEPTABLE'T: INSIGNIFICANT WELD 6( CASTING POROSITY( SLAG 6 MZNOR EROSION OF BACKING RING ACCEPTABLE D10 FEEDWATER LOOP B OUTSIDE CV DRAWINGS: HE-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 200540 HE-CB H2B AUG VT-1 FLANGE-TO-PIPE UT MT 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT'NDERCUT 1/32" ACCEPTABLE.

MT: NO RECORDABLE INDICATIONS - ACCEPTABLE. UT: NO RECORDABLE INDICATIONS 6 GEOMETRY; ROOT GEOMETRY ACCEPTABLE.

200560 HE-CB ---- M AUG VT-1 PIPE-TO-VALVE 3994 RT MT 93-VT: NO RECORDABLE INDICATIONS( CASTING P'S ON REDUCER ACCEPTABLE. MT: NO RECORDABLE INDZCATIONS ACCEPTABLE. RT: INSIGNIFICANT; BACKING RING WASH OUT, POROSITY 6 SLAG ACCEPTABLE.

53

RE E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 i

ATTACHMENT I HIGH ENERGY COMPONENTS CONT.

Dll. MAIN STEAM DRAWINGS: HE-7 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201050 HE-CS MS-47 (S3) AUG VT-3 RIGID HANGER (N IA MT 93-VT/MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

201260 HE-CS S13A AUG VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

201460 HE-CS ---- S23A AUG VT-3 RIGID HANGER 93-VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

D12. FEEDWATER LOOP A DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201660 HE-CS FWU-24 AUG VT-3 MECHANICAL SNUBBER 9 3 VT NO RECORDABLE IND ICATIONS S/N 1 006 1 9 TEMP 7 1 DEG F 9 SETTING 2 1 /8 ACCEPTABLE.

D13. FEEDWATER LOOP B DRAWINGS: HE-4 Summary Exam Item NDE Number Categ Number Component Component Type Exam 201900 HE-CS FWU-36 AUG VT-3 RIGID RESTRAINT 93-VT: NO RECORDABLE IND1CATIONS ACCEPTABLE.

54

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 HIGH ENERGY COMPONENTS CONT.

D14. MAIN FEEDWATER LINE DRAWINGS: HE-6 Summary Exam Item NDE Number Categ Number Component Component Type Exam 202140 HE-CS ---- FW-39 (S27) AUG VT-3 VARIABLE SPRING 93-VT: NO RECORDABLE INDICATIONS 6 REJECT; SPRING CAN (SIZE 16) NOT ONE STATED ON DRAWING (SIZE 17). NCR93-079 GENERATED. RESOLUTION; DESIGN ANALYSIS FOR EWR 4057-ME-1 RO (6 CATALOG INDICATES THAT THE SIZE 16 SPRING CAN IS ADEQUATE, USE-AS-IS PER ENGINEERING. DCR GENERATED. SETTING 3/4"= 6009 4'S, TEMP. 225 DEG. F. ACCEPTABLE.

E. LEAKAGE TESTING:

E1. LEAKAGE EXAMINATIONS CLASS 1 DRAWINGS: L-43 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 93-VT: NO RECORDABLE INDICATIONS 6< INSIGNIFICANT; ALL LEAKS ('N BORIC ACID RESIDUES WERE WORKED DURING PT-7. W/0 6 INSTRUCTIONS WERE CONTROLLED BY THE WORK PLANNING OFFICE. ALL LEAKS WERE RESOLVED BY THE COMPLETION OF PT-7, TEST ACCEPTABLE.

E2. LEAKAGE EXAMINATIONS CLASS 2,3 DRAWINGS:

Summary Exam Item NDE Number Categ Number Component Component Type Exam 411100 C-H IWC5221 MAINSTEAM INSIDE ASME VT-2 CONTAINMENT 93-VT: INSIGNIFICANT: (1) A S/G MANWAY COVER APPEARS TO BE LEAKING. RUST RESIDUE ON MIRROR INSULATION. BOLT 6 COVER TO BE INSPECTED DURING OUTAGE (IWA 5250), NO WR/TR GENERATED. (2) WATER ON TOP SIDE OF V-12368B, WR GENERATED'3) V 123708 CONNECTION JOINTS RUSTYS JOINT IS DRYS VERIFIED PLANT CONDITIONS WITH PLAN-A-LOG. TEST WAS SATISFACTORY.

55

R'. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 ~cul 1970 B.National Board Number for Unit ~NB ATTACHMENT I LEAKAGE TESTING CONT.

LEAKAGE EXAMINATIONS CLASS 2,3 (CONT.) DRAWINGS e N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 411300 D-B IWD5221 MAINSTEAM TO ASME VT-2 TDAFWP 93-.VT: NO RECORDABLE INDICATIONS (N INSIGNIFICANT TEST WAS ACCEPTABLE. MINOR PACKING LEAK ON V-3570, PIPE SHOP TIGHTENED - PACKING LEAK STOPPED. W/0 CLEARED ON 9202031 FOR V-3514, W/0 9221812 FOR V-3515, W/0 9340887 FOR V-3508 61 W/0 9340888 FOR V-3509 D-B IWD5221 AUXILIARY FEEDWATER

'11900 ASME VT-2 TURBINE DRIVEN 93-VT: NO RECORDABLE INDICATIONS - TEST WAS ACCEPTABLE. CLEARED W/0 932041 (SM 4951.1 REV. 0) V-4023.

412300 C-H IWC5221 STEAM GEN BLOWDOWN ASME VT-2 INSIDE CONTAINMENT 93-VT: INSIGNIFICANT: (1) V-5771 CAP DOWNSTREAM IS LEAKING, VALVE MAY BE LEAKING BY, VALVE - WHITIEY (SWAGELOK). (2) TUBING DOWNSTREAM OF V-5731 HAS NO COMPONENT SUPPORTS. WR/TR GENERATED FOR ITEMS 1 6 2. VERIFIED PLANT CONDITIONS VIA PLAN-A-LOG. NO UNACCEPTABLE CONDITIONS NOTED.

412600 C-H IWC5221 SAFETY INJECTION "B" ASME VT-2 PUMP IN/OUT CONTAINMENT 93-VT: NO RECORDABLE INDICATIONS-ACCEPTABLE. WORK ORDER WRITTEN QCR 93-0663.

INSIDE CONTAINMENT ALL ITEMS WERE FIXED. OUTSIDE CONTAINMENT, DRY BORON NOTED ON VALVE PACKINGS FOR V890B 6 V885B, INBOARD 6 OUTBOARD OF PUMP PACKING.

412800 C-H IWC5221 SAFETY INJECTION ASME VT-2 ACCUMULATOR 1 (A) 93-VT: INSIGNIFICANT: (1) VALVE 886A HAS BORIC ACID ON STEM (DRY). (2) FITTING TO PT-940 HAS DRY BORIC ACID AT THE JOINT. (3) VALVE 841 HAS BORIC ACID ON THE STEM. (4) VALVE 892A HAS BORIC ACID. WR/TR GENERATED FOR ALL ITEMS. NO UNACCEPTABLE CONDITIONS NOTED. PLANT CONDITIONS WERE VERIFIED AT PLAN-A-LOG.

56

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 ~oui 197D 6.National Board Number for Unit ~NA ATTACHMENT I LEAKAGE TESTING CONT.

LEAKAGE EXAMINATIONS CLASS 293 (CONT ) DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 413200 C-H IWC5221 RHR LOW PRESSURE ASME VT-2 "A" PUMP 93-VT: TEST SATISFACTORY. (1) V-851B HAS SMALL AMOUNT OF BORIC ACID ON PACKING FOLLOWER, (2) V-850, BODY TO BONNET LEAK. DRY BORIC ACID RESIDUE. PACKING GLAND SHOWS DRY BORIC ACID RESIDUE. (3) V-705C PACK GLAND HAS DRY BORIC ACID RESIDUE. (4) V-850B HAS DRY BORIC ACID AT THE BODY TO BONNET JOINT. WR/TC GENERATED FOR ITEMS 3 6 4.

413400 C-H IWC5221 RHR PUMP "A" ASME VT-2 IN/OUT CONT.

93 VT TEST SATI S FACTORY ~ ITEMS INS I DE EXAM SCOPE 9 V 709C/V 69 6A HAS MOIST BORIC ACID RESIDUE. V-2781 HAS DRY BORIC ACID RESIDUE. ITEMS OUTSIDE EXAM SCOPE: V-709D HAS MOIST BORIC ACID RESIDUE. V-2782 HAS DRY BORIC ACID RESIDUE. PIPING TO V-705B RUSTY. PAINT OR REPLACE W/SS. WR/TR GENERATED.

414300 D-A IWD5221 SERVICE WATER TO ASME VT-2 TDAFWP 93-VT: NO RECORDABLE INDICATIONS, TEST WAS ACCEPTABLE. W/0 9221426 CLEARED ON TDAFWP FOR MOV 4013. W/0 9221424 6 9221423 CLEARED ON MDAFWP FOR MOV 4027 & MOV 4028.

414700 C-H IWC5221 LETDOWN SYSTEM ASME VT-2 IN/OUT CONTAINMENT 93-VT: NO UNACCEPTABLE CONDITIONS WERE FOUND. NOTE: V-311C HAS BORIC ACID RESIDUE ON THE PACKINGf WR/TR GENERATED'7

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I F. SNUBBER PROGRAM COMPONENTS:

Fl. STEAM GENERATORS DRAWINGS: A-7F Summary Exam Item NDE Number Categ Number Component Component Type Exam 600080 SN-VT SGA-7 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 77 28073 Af TEMP 63 DEG F 6 SETTING 3 2 3/ 1 6

~ ~ VT NO RECORDABLE INDICATIONS G INSIGNIFICANT: HYDRAULIC FITTING LEAKING 1-3 DROPS OF FLUID PER HOURS T/C WRITTENf EXAM ACCEPTABLE'00090 SN-VT SGA-8 AUG VT-3 HYDRAULIC SNUBBER 93-S/N 77-28073-A,, TEMP. 63 DEG. F., SETTING 3'-1/4". VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

600120 SN-VT SGB-3 AUG VT-3 HYDRAULIC SNUBBER 93 S/N SGB 3 6 TEMP ~ 67 DEG ~ F 9 SETTING 3 3 5/ 1 6 VT INS IGNIFICANT LOCKNUTS 9

ON SNUBBER HAS LACK THREAD ENGAGEMENT (1-2 THREADS). USE-AS-IS PER LETTER FROM ENGINEERING. EXAM ACCEPTABLE.

600130 SN-VT SGB-4 AUG VT-3 HYDRAULIC SNUBBER 93-S/N SGB-4, TEMP ~ 67 DEG. F., SETTING 3'-3/8". VT: INSIGNIFICANT: LOCKNUTS ON SNUBBER HAS LACK THREAD ENGAGEMENT (1-2 THREADS). USE-AS-IS PER ENGINEERING. EXAM - ACCEPTABLE.

600131 SN-FT SGB-4 AUG FT HYDRAULIC SNUBBER 93-ANKER HOLTHS ID Ã AH 13 FAILED REPLACED WITH 'NEW ANKER HOLTH ID 4 AH 5,.

58

I' R. E. GINNA NUCLEAR POWER. PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 SNUBBER PROGRAM COMPONENTS CONT.

F2. TURBINE DRIVEN AUX. FW PUMP SUCTION DRAWINGS! C-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600200 SN-VT ---- AFU-03 AUG VT-3 MECHANICAL SNUBBER 93 S/N 20925 9 TEMP ~ 7 1 DEG ~ F~ 6 SETTING 2 9 PSA 1 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

F3. AUX., FW PUMPS DISCH INTERh1ED. BLDG. DRAWINGS: C-lE Summary Exam Item NDE Number Categ Number Component Component Type Exam 600220 SN-VT AFU-31 AUG VT-3 MECHANICAL SNUBBER 93 S/N 24452 f TEMP 69 DEG ~ Ff SETTING 2 f PSA 1 VTf NO RECORDABLE INDICATIONS ACCEPTABLE'00240 SN-VT AFU-34 AUG VT-3 MECHANICAL SNUBBER 93 S/N 16379 TEMP 69 DEG Ff SETTING 2 ~ 7/8 9 PSA 1 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

600260 SN-VT AFU-52 AUG VT-3 MECHANICAL SNUBBER 93 S/N 24453 f TEMP 82 DEG F f SETTING ~ 1 3/4 PSA 1 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

600280 SN-VT AFU-75 AUG VT-3 MECHANICAL SNUBBER 93 S/N 20924 f TEMP 70 DEG ~ F f SETTING 2 f PSA 1

~ ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

59

0 e

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 SNUBBER PROGRAM COMPONENTS CONT.

AUX. FW PUMPS DISCH INTERNED. BLDG. (CONT ~ ) DRAWINGS: C-1E Summary Exam Item NDE Number Categ Number Component Component Type Exam 600300 SN-VT ---- AFU-98 AUG VT-3 MECHANICAL SNUBBER 93-S/N 24454, TEMP. 275 DEG ~ Faf SETTING l-l/2ms PSA-1. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

600320 SN-VT AFU-101 AUG VT-3 MECHANICAL SNUBBER 93-S/N 15751, TEMP. 272 DEG. Fef SETTING 3-3/Bms PSA-3. VT;,NO RECORDABLE INDICATIONS - ACCEPTABLE.

600339 SN-VT ---- AFU-103 (EAST) AUG VT-3 MECHANICAL SNUBBER 93-S/N 18184, TEMP. 270 DEG. Fef SETTING 3", PSA-3. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

600340 SN-VT ---- AFU-103 (WEST) AUG VT-3 MECHANICAL SNUBBER 93 S/N 181856 TEMP 270 DEG F f SETTING 3 1/2 f PSA 3 VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

600360 SN-VT AFU-109 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 309869 TEMP 275 DEG F f SETTING 2

~ 1/8 GRINNELL 1 5 f 5/8 FULL ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

600380 SN-VT AFU-111 AUG VT-3 MECHANICAL SNUBBER 93-S/N 16377, TEMP. 270 DEG. F., SETTING 2-1/Bms PSA-l. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

60

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

AUX. FW PUMPS DISCH - INTERhlED. BLDG. (CONT.) . DRAWINGS: C-lE Summary Exam Item NDE Number Categ Number Component Component Type Exam 600400 SN-VT ---- AFU-123 AUG VT-3 MECHANICAL SNUBBER 93 S/N 16378 f TEMP 273 DEG F

~ ~ ~ f SETTING 1 5/8 f PSA 1 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

600420 SN-VT AFU-124 AUG VT-3 MECHANICAL SNUBBER 93 S/N 24451 f TEMP 271 DEG ~ F ~ f SETTING 2 f PSA 1 VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

F4. 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 93 S/N 10182 f TEMP 61 DEG F

~ ~ ~ f SETTING 2 1/2 f PSA 3 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

F5. AUX.COOL LINE 4S-AC6-152 DRAWINGS: B-29 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600530 SN-VT ---- CCU-43 AUG VT-3 MECHANICAL SNUBBER 93-S/ N 1 1462 f TEMP 61 DEG F f SETTING 1 1/4 f PSA 1 VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

61

'R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 SNUBBER PROGRAM COMPONENTS CONT.

F6. AUX.COOL SYS.FRM.PUMP COOL OUT.TO PEN126 DRAWINGS: C-34 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600610 SN-VT ---- CCU-57 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 8 1 94 5 TEMP 7 1 DEG F ~ 5 SETTING 2 3/8 PSA 3 ~ VT 5 NO RECORDABLE INDICATIONS - ACCEPTABLE.

~ ~ 5 600611 SN-FT ---- -

CCU-57 AUG FT MECHANICAL SNUBBER 93 PSA 3 5 S/N 1 8 1 94 REMOVED 5 TESTED 6 REI NSTALLED ACCEPTABLE ~

J F7. AUX.COOL LINE 4T-AC6-152 DRAWINGS: B-30 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600710 SN-VT ---- CCU-71 AUG VT-3 MECHANICAL SNUBBER 93 S/N 18193 TEMP 59 DEG F I SETTING ~ ~ 2 1/2 PSA 3 ~ VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

5 ~ 5 F8. 2-IN. LETDOWN LINE DRAWINGS: A-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600880 SN-VT CVU-26 AUG VT-3 MECHANICAL SNUBBER 93 VT; NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; S/N 208805 TEMP 60 DEG F

~ ~ 5 SETTING 2 5 PSA 15 NO ID TAG ACCEPTABLE.

62

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval Second Period f First Outage ( 1993)

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 7970 S.National Board Number for Unit ~HA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F9. 2-IN. CHARGING LINE DRAWINGS: A-30 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600900 SN-VT CVU-46 AUG VT-3 MECHANICAL SNUBBER 93 S/N 38555 f TEMP 70 DEG F

~ ~ SETTING 1 1/2 f PSA 1/4 VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

600901 SN-FT CVU-46 AUG FT MECHANICAL SNUBBER 93 PSA 1/4 f S/N 23517 f FAILED SNUBBER REPLACED WITH NEW PSA 1/4 f S/N 38555 ACCEPTABLE. REF. NCR93-081. TESTED WITH MARK HAZE 623A TESTER SHOWED ACCEPTABLE RESULTS FOR FAILED SNUBBER. SNUBBER TO BE RETURNED TO STOCK AFTER TESTING.

F10. 2-IN'LTERNATE CHARGING DRAWINGS: A-27 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600920 SN-VT CVU-49 AUG VT-3 MECHANICAL SNUBBER 93 S/N 9483 f TEMP ~ 60 DEG ~ F f SETTING 1 f PSA

~ 1/2 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

Fll. CVCS RELIEF LINE TO PRT DRAWINGS: B-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600940 SN-VT ---- CVU-80 AUG VT-3 MECHANICAL SNUBBER 93 REJECT REPLACED SNUBBER S/N 38556 9 TEMP 7 1 DEG ~ F ~ 9 SETTING 1 SHOULD BE S

1 15/16" PER ME-256. NCR93-138 GENERATED. RESOLUTION: SETTING WITHIN TOLERANCE-1 1/2". INCORRECT READING FROM MISINTERPRETATION OF ME-256, USE-AS-IS PER ENGINEERING ACCEPTABLE'3

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 NjA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

CVCS RELIEF LINE TO PRT (CONT.) DRAWINGS: B-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600941 SN-FT CVU-80 AUG FT MECHANICAL SNUBBER 93 PSA 1/4 5 S/N 23516 6 FAILED SNUBBER REPLACED WITH NEW PSA 1/4 6 S/N 38556 7

ACCEPTABLE. REF. NCR93-119. TESTED WITH MARK HAZE 623A MACHINE SHOWED ACCEPTABLE RESULTS FOR FAILED SNUBBER. SNUBBER TO BE RETURNED TO STOCK AFTER TESTING.

F12. RC PUMP 1B SEAL WATER DRAWINGS: B-33

, Summary Exam Item NDE Number Categ Number Component Component Type Exam 600960 SN-VT CVU-103 AUG VT-3 MECHANICAL SNUBBER 93 S/N 24450 5 TEMP 60 DEG F ~ 5 SETTING 2 1 /8 f PSA 1 ~ VT f NO RECORDABLE INDICATIONS ACCEPTABLE.

600980 SN-VT CVU-104 AUG VT-3 MECHANICAL SNUBBER 93-S/N 24449, TEMP. 60 DEG. F., SETTING 2", PSA-1. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F13. RC PUMP 1A SEAL WATER DRAWINGS: B-34 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601000 SN-VT CVU-186 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 654 1 f TEMP 64 DEG F f SETTING 1 3/4 f PSA 1 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

64

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 S.National Board Number for Unit jNA I

ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F14. CVCS LETDOWN LINE TO NON-REGEN HTX DRAWINGS: B-35 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601040 SN-VT CVU-345 AUG VT-3 MECHANICAL SNUBBER 93 S/N 949 1 f TEMP 180 DEG F f SETTING 1

~ 3/8 f PSA 1/2 ~ VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

601060 SN-VT ---- CVU-351 AUG VT-3 MECHANICAL SNUBBER 93 S/N 9472 f TEMP ~ 7 1 DEG ~ F ~ f SETTING 1 f PSA 1 /2 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE. ~

601061 SN-FT ---- CVU-351 AUG FT MECHANICAL SNUBBER SUCCESSIVE 93 PSA 1/2 6 S/N 282 1 f FAILED SNUBBER REPLACED WITH NEW PSA 1/2 f S/N 9472

~

ACCEPTABLE. REF. NCR93-080. TESTED WITH MARK HAZE 623A TESTER SHOWED ACCEPTABLE RESULTS FOR FAILED SNUBBER. SNUBBER TO BE RETURNED TO STOCK AFTER TESTING.

F15. CVCS LETDOWN LINE TO MIX BED DEMIN DRAWINGS: B-36 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601080 SN-VT ---- CVU-372 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9490, TEMP. 71 DEG. F., SETTING 1 1/4", PSA-1/2. VTf'O RECORDABLE INDICATIONS ACCEPTABLE.

601081 SN-FT CVU-372 AUG FT MECHANICAL SNUBBER SUCCESSIVE 93- PSA-1/2, S/N 9471, FAILED. SNUBBER REPLACED WITH NEW PSA-1/2, S/N 9490-ACCEPTABLE'EF. NCR93-078. TESTED WITH MARK HAZE 623A TESTER SHOWED ACCEPTABLE RESULTS FOR FAILED SNUBBER. SNUBBER TO BE RETURNED TO STOCK AFTER TESTING.

65 v

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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.cottaercial Service Date ~Jul 1970 6.National Board Number for Unit ~NB ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F16. FEEDWATER LOOP A DRAWINGS: B-12 Summary Exam Item NDE Number Categ Number Component Component 'Zype Exam 601100 SN-VT FWU-3 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 2500 10 1539 TEMP 66 DEG F f SETTING 4 f B P SIZE 10 VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

~ ~

601110 SN-VT ---- FWU-5 AUG VT-3 HYDRAULIC SNUBBER 93-S/N 2500-10-152, TEMP. 67 DEG. F., SETTING 2 3/4", B-P SIZE 10. VT'O RECORDABLE INDICATIONS ACCEPTABLE.

F17. FEEDWATER LOOP B DRAWINGS: B-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601120 SN-VT ---- FWU-8 AUG VT-3 MECHANICAL SNUBBER 93 S/N 8033 f TEMP 60 DEG F f SETTING 3

~ ~ 1/4 f PSA 10 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601130 SN-VT FWU-12 AUG VT-3 MECHANICAL SNUBBER 93 S/N '8034 f TEMP ~ 63 DEG ~ F ~ f SETTING 3 f PSA 10 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

66

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

1. Owner Rochester Gas S 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. O~ner Certificate of Authorization (If Req.) ~N A B.commercial service Date ~cul 197D 6.National Board Number for Unit ~NB ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F18. FEEDWATER LOOP A DRAWINGS: B-11 Summary Exam i.Item NDE Number Categ Number Component Component Type Exam 601140 SN-VT ---- FWU-15 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9358, TEMP. 270 DEG. F., SETTING 2 5/8", PSA-35. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

601150 SN-VT FWU-17 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9392, TEMP. 270 DEG. F., SETTING 5", PSA-35. VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: MOISTURE FROM OVERHEAD POSSIBLE CONDENSATION.

ACCEPTABLE.

601160 SN-VT FWU-18 AUG VT-3 MECHANICAL SNUBBER 93 S/N 7067 f TEMP 275 DEG F f SETTING 4 5/8 f PSA 35 VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

601170 SN-VT FWU-20 AUG VT-3 MECHANICAL SNUBBER 93 S/N 7049 9 TEMP 280 DEG F 6 SETTING 1 3/4 f PSA 35 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601180 SN-VT FWU-21 AUG VT"3 HYDRAULIC SNUBBER 93 S/N 2 500 20 38 9 TEMP 28 1 DEG F 9 SETTING 4

~ I BERGENSON S ZE 20 ~ VT 9 NO RECORDABLE INDICATIONS - ACCEPTABLE.

~ 6 67

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 S.National Board Number for Unit ~NB ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

FEEDWATER LOOP A (CONT.) DRAWINGS: B-11 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601190 SN-VT FWU-23 AUG VT-3 MECHANICAL SNUBBER 93 S/N 0368 f TEMP 280 DEG F f SETTING 2

~ 3/4 6 PSA 10 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601200 SN-VT FWU-24 AUG VT-3 MECHANICAL SNUBBER 93 S/N 10061 f TEMP 230 DEG F f SETTING 3 f PSA 10

~ ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601209 SN-VT ---- FWU-26 (EAST) AUG VT-3 MECHANICAL SNUBBER 93 S/N 18179 f TEMP 281 DEG F

~ ~ 9 SETTING 2 15/16 f PSA 3 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601210 SN-VT ---- FWU-26 (WEST) AUG VT-3 MECHANICAL SNUBBER 93-S/N 18180, TEMP. 281 DEG. F., SETTING 3", PSA-3. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F19. FEEDWATER LOOP B DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Nun&er Compoixe>at Coinponent Type Exam 601220 SN-VT ---- FWU-32 AUG VT-3 MECHANICAL SNUBBER 93 VT NO RECORDABLE INDICATIONS S/N 70539 TEMP ~ 282 DEG F ~ f SETTING 3 f PSA 35 ACCEPTABLE. INSIGNIFICANT'ABEL (NAME PLATE) DAMAGED ACCEPTABLE.

68

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 ~MA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

FEEDWATER LOOP B (CONT.) DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601230 SN-VT ---- FWU-38 AUG VT-3 MECHANICAL SNUBBER VT-3 93 S/N 9395 s TEMP 208 DEG F 6 SETTING 3 6 PSA 35 VT) NO RECORDABLE INDICATIONS

~ ~

ACCEPTABLE. SNUBBER REMOVED 6 REINSTALLED FOR MAINTENANCE ACTIVITY, S/N 93956 TEMP 330 DEG F 7 SETTING 2 7/8 6 PSA 35

~ ~

ACCEPTABLE'01240 SN-VT FWU-39 AUG VT-3 MECHANICAL SNUBBER 93 S/N 9354 TEMP 208 DEG F SETTING 3 3/4 PSA 35 VTB NO RECORDABLE INDICATIONS - ACCEPTABLE.

9 7 s 601250 SN-VT FWU-40 AUG VT-3 MECHANICAL SNUBBER 93 S/N 70667 TEMP 208 DEG F

~ ~ ~ 7 SETTING 3 1/2 s PSA 35 ~ VT NO RECORDABLE INDICATIONS 6( INSIGNIFICANT; 3RD NUT ON THE TOP PIN -IMPROPER THREAD ENGAGEMENT. DRAWING DOES NOT REQUIRE A 3RD NUT. USE-AS-IS PER ENGINEERING ACCEPTABLE.

601260 SN-VT FWU-42 AUG VT-3 MECHANICAL SNUBBER 93 S/N 8159 7 TEMP 208 DEG F 6 SETTING 3 5/16 s PSA 35 VTB NO RECORDABLE

~ ~ ~

INDICATIONS 6i INSIGNIFICANT: INSULATION ON V4012 IS IN CONTACT WITH SNUBBER ACCEPTABLE.

601270 SN-VT FWU-44 AUG VT-3 HYDRAULIC SNUBBER 93 S/N G 43864 02 207 TEMP 74 DEG F 9 SETTING 3 5/8

~ ~ VTs NO RECORDABLE INDICATIONS 6t INSIGNIFICANTS HYDRAULIC RESERVOIR MOUNTED UPSIDE DOWN ACCEPTABLE.

69

RE E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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.commercial Service Date ~Jul 1970 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

FEEDWATER LOOP B (CONT.) DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601280 SN-VT FWU-47 AUG VT-3 MECHANICAL SNUBBER 93-S/N 7474, TEMP. 45 DEG F., SETTING 4 ll/16, PSA-35. VT; NO RECORDABLE INDICATIONS 6 INSIGNIFICANTS'IGEON FECES 6 1" TEAR IN TOP OF BOOT ACCEPTABLE.

601290 SN-VT FWU-48 AUG VT-3 MECHANICAL SNUBBER 93 S/N 7475 f TEMP 45 DEG F f SETTING 4 1/8 f PSA 35 VTS NO RECORDABLE

~

INDICATIONS 6 INSIGNIFICANT'IGEON FECES - ACCEPTABLE.

~ ~

~

601300 SN-VT FWU-51 AUG VT-3 MECHANICAL SNUBBER 93 S/N 7483 f TEMP 45 DEG F f SETTING 4 1/2 f PSA 35 VTS NO RECORDABLE

~

INDICATIONS 6 INSZGNIFICANT; PIGEON FECES ACCEPTABLE.

601310 SN-VT ---- FWU-52 AUG VT-3 MECHANICAL SNUBBER 93-S/N 8607, TEMP. 45 DEG. F., VT: INSIGNIFICANT: PIGEON FECES. REJECT: SETTING 3.062" DOES NOT AGREE WITH 3 15/16". NCR93-100 GENERATED. RESOLUTION: PER BELL ENGINEERING DESIGN ANALYSIS 18001-05050035ROS COLD SETTING ACCEPTABLE USE-AS-IS PER ENGINEERING. ME256 WILL BE REVISED.

601320 SN-VT FWU-54 AUG VT-3 MECHANICAL SNUBBER 93-S/N 7482, TEMP. 45 DEG. F., SETTING 4", PSA-35. VT; NO RECORDABLE INDICATIONS' INSIGNIFICANTS PIGEON FECES 6 NO ID TAG ACCEPTABLE.

601330 SN-VT FWU-57 AUG VT-3 MECHANICAL SNUBBER 93-S/N 10064, TEMP. 45 DEG. F., SETTING 2 3/4", PSA-10. VTS'O RECORDABLE INDICATIONS 6 INSIGNIFICANT PIGEON FECES ACCEPTABLE.

70

pf R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. v F20. MAIN STEAM LOOP A DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601350 SN-VT ---- MSU-2 AUG VT-3 MECHANICAL SNUBBER 93 S/N 70485 TEMP 68 DEG ~ F ~ f SETTZNG 3 5/8 f PSA 35 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

601360 SN-VT MSU-3 AUG VT-3 MECHANICAL SNUBBER 93-S/N 7060, TEMP. 68 DEG. F., SETTING 3", PSA-35. VT; NO RECORDABLE ZNDICATIONS ACCEPTABLE.

F21. MAIN STEAM LOOP B DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601369 SN-VT ---- MSU-7 (TOP/WEST) AUG VT-3 MECHANICAL SNUBBER 93 S/N 7051 f TEMP 66 DEG F ~ f SETTING 2 1/2 f PSA 35 VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

~

601370 SN-VT ---- MSU-7 (BOTTOM/EAST) AUG VT-3 MECHANICAL SNUBBER 93-S/N 7047, TEMP. 66 DEG. F., SETTING 3", PSA-35. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

601380 SN-VT MSU-8 AUG VT-3 HYDRAULIC SNUBBER 93 S/N G20968 1 30f TEMP 60 DEG F f SETTING 3 3/4 f BERGEN 6 STROKE ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

71

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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. O~ner Certificate of Authorization (If Req.) ~N A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

MAIN STEAM LOOP B (CONT.) DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component 'omponent Type Exam 601390 SN-VT MSU-12 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9400, TEMP. 70 DEG. F., SETTING 3 5/16". VT; NO RECORDABLE INDICATIONS 6 INSIGNIFICANTS TORN BOOT ACCEPTABLE.

601391 SN-FT MSU-12 AUG FT MECHANICAL SNUBBER 93 PSA 3 5 6 /

S N 9400 REMOVED 6 TESTED (6 I RE NSTALLED ACCEPTABLE ~

601399 SN-VT '--- MSU-13 (EAST)

MECHANICAL SNUBBER AUG VT-3 93 S/N 1467 f TEMP 45 DEG F f SETTING 3 375

~ VTS NO RECORDABLE INDICATIONS INSIGNIFICANT; PIGEON FECES 6 NO ID TAG ACCEPTABLE.

601400 SN-VT ---- MSU-13 (WEST) AUG VT-3 MECHANICAL SNUBBER 93 VTf INSIGNIFICANT PIGEON FECES 6 NO ID TAG 6 S/N 1464 6 TEMP 45 DEG ~ F ~ ~

SETTING 1.0" SHOULD BE 3-5/16". REJECT PER ME-256. NCR93-099 GENERATED-PIGEON FECES REMOVED. REMEASUREMENT VERIFIED SETTING AT 3.187" USE-AS-IS PER ENGINEERING ACCEPTABLE.

601409 SN-VT ---- MSU-15 (NORTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 74766 TEMP ~ 71 DEG ~ F f SETTING 3 f PSA 35 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

r 601410 SN-VT ---- MSU-15 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 7477 f TEMP 71 DEG F f SETTING 3 1/4 f PSA 35 VT NO RECORDABLE

~

INDICATIONS Ec INSIGNIFICANTS TWISTED BOOT ACCEPTABLE.

72

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 SNUBBER PROGRAh'I COMPONENTS CONT.

MAIN STEAM LOOP B (CONT.) DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601411 SN-FT MSU-15 (NORTH) AUG FT MECHANICAL SNUBBER 93-PSA-35, S/N 7476. REMOVED, TESTED 6 REINSTALLED ACCEPTABLE.

601412 SN-FT MSU-15 (SOUTH) AUG FT MECHANICAL SNUBBER 93-PSA-35, S/N 7477. REMOVED, TESTED 6 REINSTALLED ACCEPTABLE.

601419 SN-VT ---- MSU-16 (NORTH) AUG VT-3 MECHANICAL SNUBBER 93-VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; PIGEON FECES ACCEPTABLE. S/N 7480., TEMP. 46 DEG. F., SETTING 2-5/8", PSA-35.

601420 SN-VT MSU-16 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93-VT; NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: PIGEON FECES ACCEPTABLE. S/N 7481f TEMP 46 DEG F ~ ~ 6 SETTING 3 3/16 f PSA 35 SN-VT ---- MSU-18 (NORTH) AUG

'01429 VT-3 MECHANICAL SNUBBER 93 S/N 7478 f TEMP 45 DEG F f SETTING 1 625 f PSA 35 VTf NO RECORDABLE

~ ~

INDICATIONS & INSIGNIFICANT; PIGEON FECES ACCEPTABLE.

601430 SN-VT ---- MSU-18 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93-S/N 74796 TEMP 45 DEG F f SETTING 2 375 f PSA 35 INDICATIONS 6 INSIGNIFICANT; PIGEON FECES - ACCEPTABLE.

'Tf NO RECORDABLE 73

X5-0 4

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 19VD 6.National Board Number for Unit ~N A ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT. v MAIN STEAM LOOP B (CONT.) DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601439 SN-VT MSU-19 (NORTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 9369 f TEMP 45 DEG F f SETTING 2 375 f PSA 35 VT NO RECORDABLE

~ ~

INDICATIONS 6 INSIGNIFICANTf PIGEON FECES 6 SERIAL NUMBER TAG STAMPED 51646 ACCEPTABLE.

601440 SN-VT MSU-19 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 9372 f TEMP 45 DEG F f SETTING 2 375 ~ PSA 35 ~ VTf NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: 'PIGEON FECES 6 SERIAL NUMBER TAG STAMPED 51646 ACCEPTABLE.

601450 SN-VT MSU-22 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9357, TEMP. 45 DEG F., SETTZNG 1.526", PSA-35. VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT; PIGEON FECES ACCEPTABLE.

601460 SN-VT MSU-25 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1465 f TEMP 45 DEG F f SETTING 1 375 9 PSA 100 VT

~ ~ NO RECORDABLE INDICATIONS 6 INSIGNIFICANTa PIGEON FECES ACCEPTABLE.

601469 SN-VT ---- MSU-26 (TOP) AUG VT-3 MECHANICAL SNUBBER 93 S/N 9355 f TEMP 71 DEG F ~ ~ 6 SETTING 4 7/8 6 PSA 35 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

e 0

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1970 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

MAIN STEAM LOOP B (CONT.) DRAWINGS: B-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601470 SN-VT ---- MSU-26 (BOTTOM) AUG VT-3 MECHANICAL SNUBBER 93 S/N 46869 TEMP 71 DEG F 9 SETTING 4 1/2 9 PSA 35 VT NO RECORDABLE INDICATIONS ACCEPTABLE.

601472 SN-FT ---- MSU-26 (BOTTOM) AUG FT MECHANICAL SNUBBER "'UCCESSIVE 93 PSA 359 S/N 4686 REMOVEDf TESTED 6 REINSTALLED ACCEPTABLE 601480 SN-VT MSU-27 AUG VT-3 MECHANICAL SNUBBER 93 S/N 9398 9 TEMP 45 DEG F f SETTING 1 37 5 9 PSA 3 5 VT NO RECORDABLE

~ ~

INDICATIONS 6 INSIGNIFICANT: PIGEON FECES ACCEPTABLE.

601490 SN-VT ---- MSU-29 AUG VT-3 MECHANICAL SNUBBER 93-S/N 1469, TEMP. 230 DEG. F., SETTING 4 1/4", PSA-100. VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

601500 SN-VT MSU-31 AUG VT-3 MECHANICAL SNUBBER 93-S/N 9356, TEMP. 230 DEG. F., SETTING 2 7/8", PSA-35. VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

601510 SN-VT MSU-32 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1093 f TEMP 380 DEG F

~ f SETTING 2 1/2 9 PSA 100 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

75

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Inter'val, Second Period, First Outage (1993)

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 197C S.national Board Number Sor Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F22. l4AIN STEAM LOOP A DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601520 SN-VT ---- MSU-38 AUG VT-3 MECHANICAL SNUBBER 93-S/N 1090, TEMP. 385 DEG. F., SETTING 1 9/16mB PSA-100. VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

601530 SN-VT MSU-39 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1087 5 TEMP 69 DEG F s SETTING 4 3/4 5 PSA 100 VT NO RECORDABLE

~ ~

INDICATIONS - ACCEPTABLE. NOTE: NO SUPPORT TAG, NO RIVETS ON SNUBBER TAGs

~

~

TAPED IN PLACE.

601531 SN-FT MSU-39 AUG FT MECHANICAL SNUBBER 93 PSA 1 00 5 S /N 1 087 REMOVED 5 TESTED & RE INSTALLED ACCEPTABLE ~

601540 SN-VT MSU-40 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 080 TEMP 275 DEG ~ F SETTING 4 3/4 PSA 1 00 VT NO RECORDABLE 6 ~ 7 s ~

INDICATIONS ACCEPTABLE.

601550 SN-VT MSU-44 AUG VT-3 MECHANICAL SNUBBER 9 3 S /N 1 4 68 s TEMP 2 7 5 DEG ~ F~ 6 SETTING 3 6 PSA 1 00 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

76

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 Sor Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.  !

F23. h1AIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601560 SN-VT ---- MSU-55 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 8 195 TEMP 38 1 DEG F

~ SETTING 1 9/ 1 6 PSA 3 VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

9 9 601570 SN-VT MSU-57 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 0 1 6 1 9 TEMP 70 DEG F ~ ~ 6 SETTING 3 1 /4 s PSA 3 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

601571 SN-FT ---- MSU-57 AUG FT MECHANICAL SNUBBER SUCCESSIVE 93 PSA 39 S/N 10161 REMOVEDs TESTED 6 REINSTALLED ACCEPTABLE ~

F24. hfAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601580 SN-VT ---- MSU-58 AUG VT-3 MECHANICAL SNUBBER 93 S/N 18187 9 TEMP 380 DEG ~ F 9 SETTING 2 9 PSA 3 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

601590 SN-VT MSU-60 AUG VT-3 MECHANICAL SNUBBER 93 S/N 10107 9 TEMP 70 DEG F ~ 9 SETTING 3 5/8 9 PSA 3 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

77

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

MAIN STEAM LOOP A ATMOSPHERIC VENT (CONT.) DRAWINGS: B-9A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601591 SN-FT MSU-60 AUG FT MECHANICAL SNUBBER SUCCESSIVE 93-PSA-3, S/N 10107 REMOVED, TESTED & REINSTALLED ACCEPTABLE.

F25. MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601600 SN-VT MSU-72 AUG VT-3 MECHANICAL SNUBBER 93-S/N 15767, TEMP. 281 DEG. F., SETTING 2 1/2", PSA-3. VT: NO RECORDABLE INDICATIONS - ACCEPTABLE.

1 601610 SN-VT MSU-74 AUG VT-3 MECHANICAL SNUBBER

/

93 S/N 1 0066 f TEMP 70 DEG F f SETTING 3 7 1 6 f PSA 1 0 ~ VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

~ ~

601611 SN-FT ---- MSU-74 AUG FT MECHANICAL SNUBBER SUCCESSIVE 93 PSA 10f S/N 10066 'EMOVEDf TESTED 6 REINSTALLED ACCEPTABLE'01620 SN-VT MSU-75 AUG VT-3 MECHANICAL SNUBBER 93 S/N 8030f TEMP ~ 69 DEG F f SETTING 3 1/2 f PSA 10 ~ VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

7&

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 1970 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT ~  !

MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE (CONT.) DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601621 SN-FT ---- MSU-75 AUG FT MECHANICAL SNUBBER 93 PSA 1 0 6 S/N 8030 ~ REMOVED 6 TESTED 6 REINSTALLED ACCEPTABLE ~

601630 SN-VT MSU-78 AUG VT-3 MECHANICAL SNUBBER 93 S/N 85769 TEMP 380 DEG F f SETTING 3

~ ~ 1/8 f PSA 10 ~ VT NO RECORDABLE INDICATIONS ACCEPTABLE.

601640 SN-VT ---- MSU-80 AUG VT-3 MECHANICAL SNUBBER 93 S/N 18181 TEMP 380 DEG F f SETTING 2 f PSA 3 VTl NO RECORDABLE ZNDICATZONS ACCEPTABLE.

601650 SN-VT MSU-82 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 5768 7 TEMP 380 DEG F

~ ~ ~ 6 SETTING 2 3/4 6 PSA 3 ~ VT 6 NO RECORDABLE INDICATIONS ACCEPTABLE.

601659 SN-VT ---- MSU-84 (EAST) AUG VT-3 MECHANICAL SNUBBER 93 S/N 10 108 f TEMP 69 DEG F 9 SETTI NG 3 1 / 1 6

~ ~ PSA 3 ~ VT ) NO RECORDABLE INDICATIONS ACCEPTABLE. NOTES NO TAG.

601660 SN-VT ---- MSU-84 (WEST) AUG VT-3 MECHANICAL SNUBBER 93 S/N 1014 1 f TEMP '9 DEG F f SETTING 3 f PSA 3 ACCEPTABLE. NOTES'O TAG.

~ ~ VTS NO RECORDABLE INDICATZONS 79

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

MAIN STEAM SUPPLY TO AUX FW PUMP TURBINE (CONT.) DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601661 SN-FT ---- MSU-84 (EAST) AUG FT MECHANICAL SNUBBER SUCCESSIVE 93 PSA 3 f S/N 10108 REMOVED S TESTED 6 REINSTALLED ACCEPTABLE ~

601662 SN-FT ---- MSU-84 (WEST) AUG FT MECHANICAL SNUBBER SUCCESSIVE 93-PSA-3, S/N 10141. REMOVED, TESTED 6 REINSTALLED ACCEPTABLE.

601670 SN-VT ---- MSU-85 AUG VT-3 MECHANICAL SNUBBER 93-S/N 10074, TEMP. 365 DEG. F., SETTING 3 3/8", PSA-10. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F26. 6-IN. SAFETY INJ. SYS (LOW HEAD) DRAWINGS: B-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601680 SN-VT ---- RHU-8 AUG VT-3 MECHANICAL SNUBBER 93-S/N 15755, TEMP. 60 DEG F., SETTING 2 5/8". PSA-3. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

80

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 S.commercial Service Date ~Jul 197D S.National Board Number for Unit ~NB ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F27. 10-IN. RESID HT REMOVAL (OUT) DRAWINGS: A-15 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601690 SN-VT RHU-30 AUG VT-3 MECHANICAL SNUBBER 93-S /N 7065 9 TEMP 58 DEG F 9 SETTING 1 9 PSA 35 ~ VT j NO RECORDABLE INDZCATIONS ACCEPTABLE.

601700 SN-VT RHU-33 AUG VT-3 MECHANICAL SNUBBER 93 S/N 7064 9 TEMP 67 DEG F 9 SETTING 3 f PSA 35 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

F28. RESIDUAL HEAT REMOVAL LINE 8B-AC-601 DRAWINGS: B-23 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601710 SN-VT ---- RHU-36 AUG VT-3 MECHANICAL SNUBBER v

93-S/N 15756, TEMP. 63 DEG F, SETTING 2 1/2", PSA-3. VTf NO RECORDABLE INDICATIONS & INSIGNIFICANTf TOP PIN IS THREADED ROD WITH DOUBLE NUT ON EACH SZDE ACCEPTABLE.

F29. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601720 SN-VT ---- RHU-51 AUG VT-3 MECHANICAL SNUBBER 93-VT-3; NO RECORDABLE INDICATIONS, S/N 15752, TEMP. 72 DEG. F., SETTING 2 1/2'9 PSA-3, - ACCEPTABLE.

81

0 1

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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.

RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG (CONT.) DRAWINGS: B-25 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601721 SN-FT ---- RHU-51 AUG FT MECHANICAL SNUBBER 93-PSA-3, S/N 15752. REMOVED, TESTED 65 REINSTALLED ACCEPTABLE.

601730 SN-VT RHU-53 AUG VT-3 MECHANICAL SNUBBER 93 S/N 15754 f TEMP 78 DEG F f SETTING 2 3/4 f PSA 3 VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

~ ~ ~

F30. RESIDUAL HEAT REMOVAL LZNE 6D-AC-601 DRAWINGS: B-26 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601740 SN-VT ---- RHU-61 AUG VT-3 MECHANICAL SNUBBER 93 S/N 15753 f TEMP 58 DEG F f SETTZNG 2 3/8 f PSA 3 ~ VTS NO RECORDABLE INDICATIONS - ACCEPTABLE.

F31. RESIDUAL HEAT REMOVAL LINE 10E-AC-601 DRAWINGS: B-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601749 SN-VT ---- RHU-63 (NORTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 163806 TEMP 63 DEG F f SETTING 2 7/8 f PSA 1 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

82

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

RESIDUAL HEAT REh)OVAL LINE 10E-AC-601 (CONT.) DRAWINGS: B-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601750 SN-VT ---- RHU-63 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 16375 f TEMP ~ 63 DEG F f SETTING 3 f PSA 1 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE. t F32. RESIDUAL HEAT REMOVAL LINE 10G-AC-601 DRAWINGS: B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601760 SN-VT RHU-69 AUG VT-3 MECHANICAL SNUBBER 93 S/N 8629 f TEMP 63 DEG F f SETTING 2 3/8 f PSA 10 VTS NO RECORDABLE INDICATIONS 6 INSIGNIFICANTS'IGHT RUST ON SNAP RING AND SNUBBER BODY ACCEPTABLE.

601769 SN-VT ---- RHU-71 (NORTH) AUG VT-3 MECHANICAL SNUBBER 93-S/N 11466, TEMP. 63 DEG. F., SETTING 2 1/2", PSA-1. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

601770 SN-VT ---- RHU-71 (SOUTH) AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 1465 5 TEMP 63 DEG F

~ ~ ~ 9 SETTING 2 1 /2 5 PSA 1 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

83

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 1

Interval, Second Period, First Outage (1993)

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. ) ~NA B.Commercial Service Date ~oui 197D S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F33. RHR PUMP A SUCTION LINE DRAWINGS! B-20A Summary Exam Item NDE Number Categ Number Component Component; Type Exam 601780 SN-VT ---- RHU-72 AUG VT-3 MECHANICAL SNUBBER 93 S/N 86069 TEMP 72 DEG F f SETTING 3

~ ~ 1/8 f PSA 10 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601781 SN-FT RHU-72 AUG FT MECHANICAL SNUBBER 93-PSA-10, S/N 8606. REMOVED, TESTED 6 REINSTALLED ACCEPTABLE.

1 F34. RESIDUAL HEAT REMOVAL LINE 10D-AC-601 DRAWINGS: B-20

,Summary Exam Item NDE Number Categ Number Component Component Type Exam 601790 SN-VT RHU-75 AUG VT-3 MECHANICAL SNUBBER 93 S/N 8632f TEMP 62 DEG F f SETTING 3 1/2 f PSA 10

~ 'TS NO RECORDABLE INDICATIONS 6f INSIGNIFICANTf'HIPPED PAINT THROUGHOUT SNUBBER. I'D. TAG WIRE BROKEN. T/C WRITTEN. UPPER PIN IS THREADED ROD 6 DOUBLE NUT ACCEPTABLE.

F35. RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Exam Item NDE Number Categ Number Component Component Type, Exam 601800 SN-VT ---- RHU-92 AUG VT-3 MECHANICAL SNUBBER VT-3 93-VT; NO RECORDABLE INDICATIONS 6 REJECT; SETTING ACCEPTABLE, FLOOR PLATE ASSEMBLY DEGRADEDS CORROSION 6 CHIPPED PAINTS NOT SERVICE INDUCED'R/WO GENERATED'OP 93206399 CLEANED 6l REPLACED PIN ~ S/N 163766 TEMP ~ 64 DEG ~ F ~ f SETTING 2 1/4", PSA-1. RE-EXAM: INSIGNIFICANT'ENT BASE EAR, SCALE, PIN THREADED ROD ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 (Zf Req.) ~N A B.commercial Service Date J~ul 197D S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F36. L.P. SAFETY INJECTION LINE FROM RWST DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601810 SN-VT ---- RHU-109 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 1463 5 TEMP 73 DEG F ~ ~ 5 SETTING 2 1/4 5 PSA 1 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601820 SN-VT RHU-110 AUG VT-3 MECHANICAL SNUBBER 93-S/N 163737 TEMP ~ 73 DEG ~ F ~ 5 SETTING 2 1/4 f PSA 1 ~ VTf NO RECORDABLE INDICATIONS ACCEPTABLE. ~

F37. SAFETY INJECTION PUMP A SUCTION LINE DRAWINGS: B-16B Summary Exam Number Categ 'tem Number Component Component Type NDE Exam 601830 SN-VT RHU-119 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 57 66 5 TEMP 1 1 8 DEG F ~ 7 SETTING 1 5/8 f PSA 3 ~ VT 5 NO RECORDABLE INDICATIONS ACCEPTABLE.

F38. SAFETY INJECTION LINE 8H-SI-151 DRAWINGS: B-19 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601840 SN-VT ---- RHU-123 AUG VT-3 MECHANICAL SNUBBER 93-S/N 15765, TEMP. 80 DEG. F., SETTING 2 1/2", PSA-3. VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

85

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F39. H.P. SAFETY INJECTION LINE TO LOOP A COLD LEG DRAWINGS: A-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601850 SN-VT ---- SIU-3 AUG VT-3 MECHANICAL SNUBBER 93 S/N 86 1 4 9 TEMP ~ 58 DEG F f SETTING 3"

~ ~ 1 /4 f PSA 1 0 ~ VT f NO RECORDABLE INDICATIONS ACCEPTABLE.

F40. H.P. SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601860 SN-VT SIU-47 AUG VT-3 MECHANICAL SNUBBER 93 S/N 15349 f TEMP 52 DEG F ~ f SETTING 3 f PSA 3 ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

F41. 10-IN. RESID HT REMOVAL (IN) DRAWINGS: A-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601870 SN-VT SIU-52 AUG VT-3 MECHANICAL SNUBBER 93 S/N 1 5348 f TEMP 52 DEG F 9 SETT1 NG 2 1 /2 f PSA 3

~ ~ ~ VTS NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE; NO TAG.

601871 SN-FT SIU-52 AUG FT MECHANICAL SNUBBER 93-PSA 3f S/N 15348 'EMOVEDS TESTED 6 REINSTALLED ACCEPTABLE.

k S6

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 6.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F42. SVC.WTR.-TO A & B DIESEL GEN.WTR.COOLERS DRAWINGS: C-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601890 SN-VT ---- SWU-254 AUG VT-3 MECHANICAL SNUBBER 93-S/N 12508, TEMP. 67 DEG. F., SETTING 1 1/4mf PSA-1/2. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F43. SERVICE WATER LINE SL-SW-125 DRAWINGS: B-50A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601900 SN-VT SWU-308 AUG VT-3 MECHANICAL SNUBBER 93 S/N 803 1 6 TEMP 70 DEG F ~ SETTING 2 7 /8 PSA 1 0 ~ VT NO RECORDABLE INDICATIONS - ACCEPTABLE.

6 6 6 601910 SN-VT SWU-309 AUG VT-3 MECHANICAL SNUBBER 93 S/N 10073 f TEMP 73 DEG F f SETTING 3

~ ~ 1/4 f PSA 10 ~ VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

F44. SVC.WTR.-INTMD.BLDG.16"HD.TO PEN 312-320 DRAWINGS: C-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 601920 SN-VT ---- SWU-370 AUG VT-3 MECHANICAL SNUBBER 93-S/N 114646 TEMP 70 DEG F f SETTING

~ 2 1/4 f PSA 1 VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

601921 SN-FT SWU-370 AUG FT MECHANICAL SNUBBER 93-PSA-l, S/N 11464. REMOVED, TESTED 6 REINSTALLED ACCEPTABLE.

a 87

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F45. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWINGS: C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601930 SN-VT AFU-205 (AFW-10) AUG VT-3 HYDRAULIC SNUBBER 93 S/N 154036 TEMP 68 DEG F 6 SETTING 3 1/16

~ ~ ~ 6 FLUID LEVEL 4/5 FULL VTS NO RECORDABLE INDICATIONS ACCEPTABLE.

601931 SN-FT ---- AFU-205 (AFW-10) AUG FT HYDRAULIC SNUBBER SUCCESSIVE 93 GRINNEL 1 56 S/N 12900f FAILED ~ SNUBBER REPLACED WITH NEW GRINNEL 1 ~ 5f S/N 15403 ACCEPTABLE'EF. NCR93-089, SNUBBER TO BE REBUILT 6 PLACED IN STOCK.

601940 SN-VT AFU-208 (AFW-13) AUG VT-3 HYDRAULIC SNUBBER 93 S/N 210106 TEMP 60 DEG F f SETTING 2 f GRINNEL SIZE 1 1/2 VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

F46. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS: 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 93 S/N 12905 f TEMP 7 1 DEG F

~ ~ f SETTING 2 3/4 f GRINELL SIZE 1 1/2 f 3/4 FULL ~ VTS NO RECORDABLE INDICATIONS G INSIGNIFICANTS'NUBBER PIN PIPE CLAMP END CENTER PUNCH MARK ON END OF PIN ACCEPTABLE.

601980 SN-VT ---- AFU-226 (AFW-27) AUG VT-3 HYDRAULIC SNUBBER 93 S/N 12901 9 TEMP 7 1 DEG F ~ 6 SETTING 3 9 GRINNEL SIZE 1 1/2 6 7/8 FULL ~ VTS NO

~

RECORDABLE INDICATIONS 6 INSIGNIFICANTS SNUBBER PIN (PIPE CLAMP END) ROUNDED OVER ACCEPTABLE.

88

RE E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 197D S.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COhlPONENTS CONT ~

STANDBY AUX FW THRU PEN 119 TO A S/G FWHD (CONT.) DRAWINGS: C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601990 SN-VT AFU-225 (AFW-29) AUG VT-3 HYDRAULIC SNUBBER 93 S/N 12906/ TEMP 71 DEG

~ F / SETTING 1 1/2

~ ~ GRINNELL SIZE 1 1/2 VT ~

INSIGNIFICANT: LOCKNUT NOT REQUIRED TO HAVE FULL THREAD ENGAGEMENT AS LONG AS IT IS TIGHT WITH PRIMARY NUT. PIVOT PIN ACCEPTABLE TO BE LOOSE IN BRACKET HOLE BUT TIGHT TO EACH OTHER/ REFT NCR91 166 ACCEPTABLE'02000 SN-VT AFU-227 (AFW-31) AUG VT-3 MECHANICAL SNUBBER 93-S/N 25594, TEMP. 71 DEG. Fe/ SETTING 4 1/4m, PSA-3. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F47. PRESS. RELIEF FM PRESS.TO RELIEF MANIFOLD DRAWINGS: S-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602010 SN-VT ---- N601 AUG VT"3 HYDRAULIC SNUBBER 93-S/N 6565, TEMP. 66 DEG. Fe/ SETTING 3 9/16N/ GRINNELL SIZE 2, FLUID LEVEL 60't FULL VT / NO RECORDABLE IND ICATIONS 6 INS IGNIFI CANT / 1 DROP OF OIL ON BOTTOM OF RESERVOIR - ACCEPTABLE.

~

602020 SN-VT N602 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 6568/ TEMP 66 DEG F / SETTING 2 3/8 / GRINNELL SIZE 2 / FLUID LEVEL 75't

~

FULL/ VT; NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE/ NO MANUFACTURERS TAG.

89

9 1990-1999 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Interval, Second Period, First Outage (1993)

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 197C 6.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

PRESS. RELIEF FM PRESS.TO RELIEF MANIFOLD (CONT.) DRAWINGS: S-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602030 SN-VT N604 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 6566 7 TEMP 66 DEG F

~ 7 SETTING 1 9/ 16 f GRINNELL SI ZE 2 f FLUID LEVEL 3/8 FULL. VT; NO RECORDABLE INDICATIONS ACCEPTABLE'OTE; NO MANUFACTURERS TAG.

602040 SN-VT ---- N605 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 6561 f TEMP 66 DEG F 7 SETTING 2 11/16 f GRINNELL SIZE 2f FLUID LEVEL 80%

~ ~ ~

FULL. VT; NO RECORDABLE INDICATIONS ACCEPTABLE. NO MANUFACTURERS TAG.

~

602050 SN-VT N607 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 6562 f TEMP 66 DEG F f SETTING 3 1 1/ 16 6 GRINNELL SI ZE 2 6 FLUID LEVEL 60%

FULL, VTf NO RECORDABLE INDICATIONS ACCEPTABLE. NOTE: NO MANUFACTURERS TAG.

602060 SN-VT ---- N608 AUG VT-3 HYDRAULIC SNUBBER 93-S/N 6563, TEMP. 66 DEG. F., SETTING 3 3/4", GRINNELL SIZE 2, FLUID LEVEL NO RECORDABLE INDICATIONS & INSIGNIFICANTf 1 DROP OF OIL ON BOTTOM 66'%ULLf VTf OF RESERVOIR. NOTE: NO MANUFACTURERS TAG ACCEPTABLE.

602070 SN-VT N615 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 6564 f TEMP 66 DEG F f SETTING 2 3/8

~ ~ GRINNELL SI ZE 2 f FLUID 60% FULL ~

VT; NO RECORDABLE INDICATIONS & INSIGNIFICANTf 1 DROP OF OIL ON BOTTOM OF RESERVOIR. NOTES'O MANUFACTURERS TAG. ACCEPTABLE.

90

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 SNUBBER PROGRAM COMPONENTS CONT.

PRESS. RELIEF FM PRESS.TO RELIEF hDQlIFOLD (CONT.) DRAWINGS: S-2 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602080 SN-VT ---- N616 AUG VT-3 HYDRAULIC'SNUBBER 93 S/N 6567 5 TEMP 66 DEG F f SETTING 2 1/2 5 GRINNELL SI ZE 2 6 FLUID LEVEL 75't

~ ~ ~

FULL. VT: NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: 1 DROP OF OIL ON BOTTOM OF RESERVOIR ACCEPTABLE. NOTE: NO MANUFACTURERS TAG.

F48. POWER PRESS. RELIEF LINE DRAWINGS: S-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602090 SN-VT PS-2 AUG VT-3 HYDRAULIC SNUBBER t

93-REJECT: LOOSE FASTENERS 6 FLUID LEVEL, NCR93-155 GENERATED. RESOLUTION: TWO EXPOSED THREADS ARE ACCEPTABLE PER ENGINEERING, USE-AS-IS. RE-EXAM AFTER CORRECTIVE ACTIONS S/N PD87239 12446 TEMP 62 DEG F 6 SETTING 4 1/8 ~ VTj NO

~

RECORDABLE INDICATIONS ACCEPTABLE.

602091 SN-FT ---- PS-2 AUG FT HYDRAULIC SNUBBER EXPANDED 93 NCR93 1 55 LOW FLUID LEVEL 1 GRINNEL 1 ~ 5 6 REMOVED f TESTED 6 REINSTALLED ACCEPTABLE.

602100 SN-VT PS-4 AUG VT-3 HYDRAULIC SNUBBER 93 S/N PD 86 144 1 1 52 6 TEMP 61 DEG F 6 SETTING 1 1/8 6 PAUL MONROE f FLUID LEVEL 50%. VTf NO RECORDABLE INDICATIONS ACCEPTABLE.

602101 SN-FT PS-4 AUG FT HYDRAULIC SNUBBER 93 - PMH-2103, S/N PD 86144-1152. REMOVED, TESTED 6 REINSTALLED - ACCEPTABLE.

91

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 B.National Board Number for Unit jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F49. 3-IN. PRESSURIZER RELIEF LINE DRAWINGS: A-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602110 SN-VT ---- PS-5 AUG VT-3 HYDRAULIC SNUBBER 93-REJECT: NO GREEN SHOWING, NCR93-085 GENERATED. MAINTENANCE PERFORMED FUNCTIONAL TESTf ADDED OILf VERIFIED SETTING ACCEPTABLE'EEXAMINE S/N PD87239 1246f TEMP 71 DEG F f SETTING 2

~ 5/8 f PAUL MONROE'Tf NO RECORDABLE INDICATIONS ACCEPTABLE.

602111 SN-FT ---- PS-5 AUG HYDRAULIC SNUBBER 93 NCR93 085 9 LOW FLUID LEVEL9 GRINNEL 1 ~ 5 9 S/N 87239 1246 ~ REMOVED 9 TESTED REINSTALLED ACCEPTABLE.

602120 SN-VT PS-6 AUG VT-3 HYDRAULIC SNUBBER 93 S/N PD87767 1239 f TEMP ~ 66 DEG ~ F f SETTING 3 3/4 9 PAUL MONROE ~ VT9 NO RECORDABLE INDICATIONS 6 INSIGNIFICANTf LOWER BASE PLATE SPACER MISSING. NOT REQUIRED PER DRAWING ACCEPTABLE.

602130 SN-VT PS-8 AUG VT-3 HYDRAULIC SNUBBER 93 S/N PD86144 1 159 f TEMP 66 DEG F f SETTING 2 3/4 f PAUL MONROE ~ VT NO RECORDABLE INDICATIONS 6 INSIGNIFICANT: CENTERING DEVICE FOR YOKE IN BASEPLATE ATTACHMENT MISSING ACCEPTABLE. EXPANDED VT-3 COMPONENT EXAM PER NCR93-086 FOR PS-9.

92

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 jNA ATTACHMENT I SNUBBER PROGRAM COMPONENTS CONT.

F50. POWER PRESS. RELIEF LINE DRAWINGS: S-1A Summary Exam Item NDE Number Categ Number Component Component Type Exam 602140 SN-VT ---- PS-9 AUG VT-3 HYDRAULIC SNUBBER 93-REJECT: LOOSE LOCK NUT ON UPPER SOUTH BOLT WITH,NO OTHER RECORDABLES, NCR93 086 GENERATED'E EXAM AFTER CORRECTIVE ACTIONS UPPER LOCK NUT TIGHTS S/N PD86144 1154f TEMP 66 DEG F f SETTING 3 1/4

~ ~ (REJECT WAS DETERMINED TO BE SERVICE INDUCED.) ACCEPTABLE.

PS-10 AUG VT-3 HYDRAULIC SNUBBER 93 S/N PD86 1 44 1 1 57 f TEMP 66 DEG F f SETTING 3 3/4

~ ~ PAUL MONROE EXPANDED VT 3 COMPONENT EXAM PER NCR93-086 FOR PS-9. VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

602160 SN-VT PS-11 AUG VT-3 HYDRAULIC SNUBBER 93 VTf NO RECORDABLE INDICATIONS 6 INS IGNIFICANTf S/N 6562 f TEMP 66 DEG ~ F~ f SETTING 2 1 /4 f FLU I D LEVEL 50't f NO MANUFACTURER TAG ACCEPTABLE ~

F51. CVCS RCP B LEAKOFF RET. DRAWINGS: S-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602200 SN-VT CVU-131 AUG VT-3 MECHANICAL SNUBBER 93 S/N 25432 f TEMP 60 DEG F f SETTING 2 1/2 f PSA 3

~ ~ VTf NO RECORDABLE INDICATIONS - ACCEPTABLE.

602300 SN-VT CVU-550 AUG VT-3 MECHANICAL SNUBBER 93 S /N 1 8 1 90 f TEMP 60 DEG F f SETTING 2 1 /4 f PSA 3 ~ VT f NO RECORDABLE INDICATIONS ACCEPTABLE.

93

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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.mmarcial Service Date J~ul 1570 S.National Board Number for Unit ~NA ATTACHMENT I SNUBBER PROGRAM COhlPONENTS CONT.

F52. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD DRAWINGS: C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602400 SN-VT ---- AFU-209 AUG VT-3 HYDRAULIC SNUBBER 93-SNUBBER REPLACED UNDER W/0 9320686. S/N 12904, TEMP. 63 DEG. F., SETTING 2 1/4", FLUID LEVEL 50%. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

F53. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD DRAWINGS: C-20 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602500 SN-VT AFU-229 AUG VT-3 HYDRAULIC SNUBBER 93 S/N 12903 f TEMP 7 1 DEG F f SETTING 2 1/4 f GRINNELL SI ZE 1 1/2 f FLUID 3/4

~

FULL VT 5 NO RECORDABLE INDICATIONS 6 INS IGNI FICANT5 P IN ON CLAMP END IS ROUNDED OVER - ACCEPTABLE.

~

G. STEAM GENERATOR EDDY CURRENT EXAhlINATIONS:

Gl. STEAM GENERATOR A DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 800000 B-Q ~ B16.20 OPEN GENERATOR TUBES ASME ET PREVIOUS IDENTIFIED ET DEGRADATION > 20%

93-PREVIOUS INDICATIONS >' 20%, WERE EXAMINED TO THE EXTENT OF DEGRADATION AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS'4

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage'1993)

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 STEAM GENERATOR EDDY CURRENT EXAMINATIONS CONT.

STEAM GENERATOR A (CONT.) DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 800150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20% ROTATING RANDOM ET SAMPLE 93-20% RANDOM SAMPLE OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED FULL LENGTH (F/L).

SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

800200 SG-ET ---- OPEN GENERATOR TUBES OE ET 100% OF ALL UNSLEEVED ET TUBES 93-100% OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED TO THE FIRST SUPPORT PLATE ON THE HOT LEG SIDE AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS'00350 B-Q B16.20 SLEEVED GENERATOR ASME ET TUBESf 20'%OTATING ET RANDOM SAMPLE OF EACH ET TYPE SLEEVE ET 93-20'%ANDOM SAMPLE OF EACH TYPE OF SLEEVED GENERATOR TUBES WERE EXAMINED FROM THE SLEEVE END AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

G2. STEAM GENERATOR B DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 801000 B-Q B16.20 OPEN GENERATOR TUBES ASME ET PREVIOUS IDENTIFIED ET DEGRADATION > 20%

93-PREVIOUS INDICAT1ONS >= 20% WERE EXAMINED TO THE EXTENT OF DEGRADATION AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

95

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

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 J~ul 1970 6.National Board Number for Unit jNA ATTACHMENT I STEAM GENERATOR EDDY CURRENT EXAMINATIONS CONT.

STEAM GENERATOR B (CONT.) DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 801150 B-Q B16.20 OPEN GENERATOR TUBES ASME ET 20% ROTATING RANDOM ET SAMPLE 93-20'%ANDOM SAMPLE OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED FULL LENGTH (F/L).

SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

801200 SG-ET ---- OPEN GENERATOR TUBES OE 100% OF ALL UNSLEEVED TUBES 93-100% OF ALL OPEN UNSLEEVED TUBES WERE EXAMINED TO THE FIRST SUPPORT PLATE ON THE HOT LEG SIDE AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

801350 B-Q B16.20 SLEEVED GENERATOR ASME ET TUBES, 20% ROTATING ET RANDOM SAMPLE OF ET EACH TYPE SLEEVE ET 93-20% RANDOM SAMPLE OF EACH TYPE OF SLEEVED GENERATOR TUBES WERE EXAMINED FROM SLEEVE END TO SLEEVE END AS A MINIMUM. SEE THE 1993 EDDY CURRENT REPORT FOR DETAILS.

96

I' FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1.Owner Rochester Gas fd Electric Cor . Date 7 June 1993 89 East Ave. Rochester NY 14649 Sheet 1 of 34

2. Plant R.E. Ginna Nuclear Power Plant Unit 1503 Lake Road Ontario NY 14519 Address Repair Organization P.O. No., Job No., etc.
3. Work Performed by Type Code Symbol Stamp N A Name Authorization No. N A

~

Expiration Date N A Address

4. Identification of System
5. (a) Applicable Consirnodon Code ~19~ Edison,~

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Addenda, 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 or (Yes Component Manufacturer Serial No. No. Identification Build Replacement or No)

7. Description of Work
8. Tests Conducted:(') Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure psi Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(') See "ATTACHMENTII sr (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N. Y. 10017 1

0 FORM NIS-2 (Back) 9.Remarks Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp Certificate of A thori ation No. NA Expiration Date NA Si ned 1 F.A. Kle acki ISI En ineer Date 7 June 1993 Owner or Owne 's Designee, Title CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by HSBI&l Co.

of Hartford CT. have inspected the components described in this Owner's Report during the period ~ 2. to , and state that to the best of my knowledge and belief, the Owner has pe ormed examinations and taken corrective measures described in this Owner's Report in accordance with the inspection plan and as required by the ASME Code,Section XI.

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

Commissions Inspector's Signature National Board, State, Province, and Endorsements Date F  ! qg 9W

(*) See "ATTACHMENTII"

(**) Repair, Replacement or Modification as identified within ATTACHMENT II'

Ro Eo GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPAIR REPLACEMENT and MODIFICATION PROGRAM The Repair, Replacement and Modification (RR&M) Program, as identified within the "Appendix B" Program'f the Ginna Station Quality Assurance Manual, identifies component jurisdiction and associated requirements. Applicable Repair, Replacement or Modification activities have been performed in accordance with ASME Section XI Code, 1986 edition, no addenda.

When an item under the rules and requirements of the "Appendix B" Program is found deficient, an Engineering "use-as-is" evaluation may result. This determination is indicated within the ISI Program Summary, "Attachment I", for the applicable component within this report. If the deficiency results in a Code Repair, Replacement or Modification; the deficiency will be classified as one of three category types. These category types shall consist of a "Code Service Induced Rejectable Indication", a "Code Rejectable Indication" and a "Corrective Action Activity".

A "Code Service Induced Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be "Service Induced". "Service Induced" indications, stemming from Inservice Inspection Examinations 'ISI), shall require additional expanded examinations. The associated expanded examinations shall be performed in accordance to the requirements of the ASME Section XI Code.

A "Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not "Service Induced". This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

'0

1. Owner: Rochester Gas 5 Electric Cor . 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 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. Atlantic Valve Turnpike Industrial Park P.O. Box 774 Westfield, Mass. 01086
6. Babcock & Wilcox Lynchburg, Virginia

0 R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas & Electric Cor . 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 Modifications: 1986 No Addenda ATTACHMENT II The following information will report applicable Repairs, Replacements or Modifications performed at R. E. Ginna Nuclear Power Plant during this reporting period as required by ASME Section XI Code.

A CODE REPAIRS:

ASME Class: 3 ~S stem: Service Water GORR Nc.: 93-T-013 Construction Code:

Work Performed B :

ASME 3

Section III, 1986 Edition.

Name of Com onent: MOV-4664; Valve Disc Guide Repair.

Work Descri tion Remarks: A Repair activity was initiated to replace the welds associated with the valve disc guide on MOV-4664. This activity was controlled by WO number 9221521 and SM 92-002.5; Upon completion of the repair activity, Construction Code VT and PT NDE was performed and acceptable. Upon reinstallation, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

Re E ~ GINNA NUCLEAR POWER PLANT I,

Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993) 1 Ownerc Rochester Gas & Electric Cor . 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 CODE REPAIRS Cont.

2- ASME Class: 1 ~S stem: Reactor Coolant Sys. GORR No.: 93-E-006 "Line: N/A Construction Code: ASME Section III, 1986 Edition.

Work Performed B : 4 Name of Com onent: Steam Generator "A" (EMSO1A) Tubes, Welded Sleeves.

Work Descri tion Remarks: During the Eddy Current. Examination of Steam .Generator "A & B", a total of 51 tubes containing defects were identified and determined to be candidates for CE (27") welded sleeves. The 51 identified tubes were all located in Steam Generator "Aue The location of these defective tubes are identified within the Eddy Current "1993 Summary 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, UT Examinations were performed on the Upper Sleeve Weld while VT Examinations were performed on the Lower Sleeve Weld. Baseline Eddy Current Examinations were performed and accepted on the welded CE Sleeves.

3. ASME Class: 1 ~S stem: Reactor Coolant Sys. GORR No.: 93-E-007 Line: N/A Construction Code: ASME Section III, 1986 Edition.

Work Performed B : 4 Name of Com onent: Steam Generator "A & B (EMS01AI EMSOlB)

Tubes, Welded Plugs.

Work Descri tion Remarks: During the Eddy Current Examination of Steam Generator "A & B", a total of 20 tubes containing defects were identified and determined to be candidates for CE welded plugs. A total of two (2) welded CE Plugs were installed in the "A" Steam Generator. A total of eighteen (18) welded CE Plugs were installed in the "B" Steam Generator. The location of these defective tubes are identified within the Eddy Current "1993 Summary 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.

Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 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 CODE REPAIRS Cont.

4 ~ ASME Class: 1 ~S stem: Reactor Coolant Sys. GORR No.: 93-E-008 Line: N/A Construction Code: ASME Section III, 1986 Edition.

Work Performed B : 6 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", a total of 216 tubes containing defects were identified and determined to be candidates for B&W bimetallic explosive sleeves or plugs. A total of sixty-two (62) B&W explosive sleeves and one (1) B&W explosive plug were installed in the "A" Steam Generator. A total of 153 B&W explosive sleeves were installed in the "B" Steam Generator.

The location of these defective tubes are identified within the Eddy Current "1993 Summary Examination Report for Steam Generators". This activity was controlled by Ginna Station Maintenance Procedures M43.16 & M43.43.3, and B&W document 51-1212535-01. Upon completion of the installation activity, Eddy Current examinations were performed and acceptable on the sleeves. No Eddy Current. examination was performed on the Plug. Eddy Current Sleeve Examinations are also utilized to verify proper weld location and provides comparison to,ensure weld soundness.

5. ASME Class:N/A-High Energy stem: Feedwates

~S GORR No.:93-M-001 Construction Code: B31.1, 1967 Edition.

Work Performed B : 1 Name of Com onent: 14 x 12 Feedwater Reducer Weld Overlay.

Work Descri tion Remarks: During an erosion/corrosion minwall examination it was discovered that the wall thickness of the reducer was .461am The results were submitted for review and evaluation. A determination was made to perform an engineered weld overlay on the area of approximately 1/8us This "Repair" activity was controlled by WO number 9320663 and RRER 93-0007.

Upon completion of the repair activity, both MT and UT Thickness (erosion/corrosion) Examinations were performed and acceptable.

7

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 5 Electric Cor . 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 CODE REPAIRS Cont.
6. ASME Class: 1 ~S stem: Charging GORR No.: 93-M-002 Construction Code: B31.1, 1956 Edition.

Work Performed B : 1 Name of Com onent: V-383A; Valve Body Indication Repair.

Work Descri tion Remarks: During an ISI examination, 2 linear indications were discovered within the base material of the valve body. Metallurgical examination revealed that the indications were manufacturing defects and not service induced. An NCR was generated for evaluation and disposition.

A Code "Repair" cycle by metal removal was initiated. This repair activity was controlled by NCR 93-102 and WO number 9320457. Upon completion of the repair cycle, UT thickness and a PT baseline examination was performed and acceptable as documented within the WO and NDE summary exam number 053200.

7 ~ ASME Class: 3 ~S stem: Service Water GORR Nc.: 93-M-003 Construction Code: B31.1, 1983 Edition.

Work Performed B : 3 Name of Com onent: MOV-4615, Valve Stem Repair.

Work Descri tion Remarks: During a Maintenance activity, was discovered that the valve stem had scratches needing it corrective action. A Code "Repair" cycle by metal removal was initiated. This repair activity was controlled by WO number 9221494 and SM 92-002.7. Upon repair completion and reassembly of the valve, an Inservice Test and associated VT-2 examination was performed and acceptable as documented within the WO.

R e E ~ OINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas & 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 Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II B REPLACEMENTS AND MODIFICATIONS:

1~ ASME Class: 2 ~S stem: Feedwater GORR No.: 92-E-039 Construction Code:

Work Performed B :

ASME 1

Section III, 1986 Edition Name of Com onent: FWU-11, Variable Spring Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to change out two 7/8u diameter bolts.

The replacement consisted of threaded rods and nuts. This action was required since the original bolting had insufficient thread engagement by three (3') threads. The replacement activity was controlled by NCR92-142. The materials utilized were obtained under PO GPN 720601 & GPN 7456. Upon installation, a baseline VT-3 examination was performed and accepted as documented within NDE summary number 92098100.

2. ASME Class: 3 ~S stem: Service Water GORR Nc.: 93-T-001 Construction Code: B31.1, 1955 Edition, Gilbert Spec. SP-5291.

Work Performed B : 1 Name of Com onent: V-4601, Crane Valve, Model CV06001-8-12 Work Descri tion Remarks: A corrective action Replacement activity was initiated to change out the Disc, Disc Arm (hanger bracket) and Lockwashers which included lockwire per TSR 91-149. The replacement activity was controlled by WO number 9140634. Items utilized for this activity were obtained under PO's NQ 12344 AJD, NQ 12396 AJD and NQ 12985 AJD. Upon installation, an Inservice Test was performed and accompanying VT-2 Examination acceptable as documented within the Work Order.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas E Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS'ont.
3. ASME Class: 3 ~S stem: Diesel Air Start GORR No.: 93-T-002 Construction Code: Gilbert BOM EI-l, Spec. SP-5291 Work Performed B : 1 Name of Com onent: V-5975 Replacement Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 5975 due to leaking.

This activity was controlled by WO numbers 9200850 & 9220137.

The Valve utilized for this activity was obtained from Lunkenheimer (2140) under PO number NEG 46959 84 3. Upon reassembly, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within Work Order Number 9220137.

4 ~ ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-003 Line: N/A Construction Code: Gilbert SP-5291/M-11.10.2 Work Performed B : 1 Name of Com onent:Worthington SW Pump PSW01A, Model 20H500W-2.

Work Descri tion Remarks: A preventative maintenance "Like-for Like" Replacement activity was initiated to change out the Pump Bowl assembly with a rebuilt assembly from stock. This replacement activity was controlled by WO number 9140583.

Items utilized for this activity conformed to'othington Drawing DEN 19353. Upon installation, a Functional Test and accompanying VT-2 Examination was performed in accordance with PT 2.7 at normal operating pressure and acceptable as documented within the Work Order and M-11.10.

10

R. E GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner! Rochester Gas 5 Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
5. ASME Class: 3 ~S stem: Service Water GORR Nc.: 93-T-004 14B-SWO-125-1 14C-SWO-125-1 Construction Code: B31.1, 1955 Edition Work Performed B : 1 Name of Com onent: Studs/Nuts on the A, B, C Service Water Pumps Expansion Joints, SSW01, SSW02, SSW03.

Relief Re uest Used: RR g 14 Work Descri tion Remarks: A preventative maintenance "Like-for Like" Replacement activity was initiated to change out Studs/

Nuts associated with the A, B, & C Service Water Pumps Expansion Joints (SSWOl, SSW02, SSW03). This replacement activity was controlled by WO numbers 9220869, 9220870 &

9220871. Items utilized for this activity were obtained from Energy Steel under PO number NQ 12234 AJD. Upon installation, an Inservice Test was performed and accompanying VT-2 Examination was acceptable as documented within the Work Orders.

6. ASME Class: 2 ~Sstem: Mainsteam GORR No.: 93-T-005 Construction Code: B31.1, 1977 Edition Work Performed B : 1 Name of Com onent: AOV-3411 Internals.

Work Descri tion Remarks: A preventative maintenance "Like-for-Like" Replacement activity was initiated to change out AOV-3411 internals due to leakage at the seat. This replacement activity was controlled by WO number 9201430.

Items utilized for this activity was obtained under PO number NQ 11415 BJD, Heat g 94504-6. Upon installation, an Inservice Test and accompanying VT-2 Examination was performed and acceptable as documented within the Work Order.

R. E ~ OINNA NUCLEAR POWER PLANT Inservice InsPection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas E Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Oinna 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 e

REPLACEMENTS AND MODIFICATIONS: Cont.

7 ~ ASME Class: 2 ~S stem: Charging/CVCS GORR No.: 93-T-006 Line: NA Construction Code: B31.1, 1955 Edition & Augmented PT Exam per ASME Section VIII.

Work Performed B : 1 Name of Com onent: Charging Pump "C" (PCH01C) Block & Old Weld Drain Pan, & all Discharge/Suction Manifold Studs. Model T-125, SN 5813.

Code Cases Used: N-416 Work Descri tion Remarks: A Maintenance Replacement activity was initiated on the Charging Pump "C" Block & Weld Drain Pan, and all Discharge/Suction Manifold Studs. This activity was controlled by WO number 9201722. Items utilized for this activity conformed to Ajax Drawing Number SK8540, & items were obtained from Cooper Energy Services under PO number NEG 29113

83. Construction Code Surface examinations were performed and acceptable. Upon completion of the replacement activity, a Functional Test and accompanying VT-2 Examination was performed & acceptable as documented within PT-. 31 and the Work Order.

12

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993) 1 ~ Owner: Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649 2 ~ Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 ~ Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.

8. ASME Class: 3 ~S stem: Service Mater GORR Nc.: 93-T-007 Line: N/A Construction Code:

III, 1

1. Underwater Support Nut ASME Section 1986 Edition.
2. Bowl Assembly Gilbert SP-5291; BOM MD-l, Spec. R0-2204.
3. Pipe Column Nut Gilbert BOM MD-l, Spec. RO-2204 & ASME Section III, 1986 Edition.
4. Pipe Column Bolt Gilbert BOM MD-1, Spec. R0-2204, SAE J404g & ANSI B18.18.2M
5. Pump Bowl Bolt Gilbert BOM MD-1, Spec. RO-2204 & ASME Section III, 1986 Edition.
6. Flange Bolts/Nuts B31.1, 1973 Edition; EWR 2512 Stress & ASME Section III, 1986 Edition.

Work Performed B  : 1 Name of Com onent: Service Water Pump "D"(PSWO1D) Components;

1. 1" Underwater Support Nut. 2. Bowl Assembly Spare Swap Out.
3. Pipe Column Nuts 8. 4. Pipe Column Bolts 15.
5. Pump Bowl Bolts 36. 6. Discharge Flange Nut & Bolt.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to Swap Out the existing Pump Bowl Assembly on the Service Water Pump "D" and replace original spare. A 1" Underwater Support Nut was replaced. The it with an nut used was obtained from Nova Machine, Lot g 32568030, Heat 79181 under PO Number NQ 11469 BJD. Eight (8) 7/8-9 Nuts were also replaced on the Pipe Column. The nuts used were obtained from Nova Machine, Heat g 43236 under PO Number 12702 AJD. Fifteen (15) 7/8-9x4" Bolts were replaced on the Pipe Column. The items utilized for this replacement were obtained from Premier Fastener under PO Number NQ 10069 BJD. Thirty-six (36) Pump Bowl Bolts (3/4-10 x 2") were replaced. The bolts used were obtained from Nova Machine under PO Number NQ 12702 AJD, Heat, g 4-9943 FA. One Nut and Bolt was replaced on the Discharge Flange. These items were obtained from Nova Machine under PO Number NQ 12396 AJD. These replacement activities were controlled by TSR 91-546 and WO numbers 9221819, 9221152

& 9320328. Upon completion of the replacement activity, a Flow Test and accompanying VT-2 Examination was performed &

accepted as documented within the Work Orders, M11.10 and PT-2.7.

13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.

9 ~ ASME Class: 3 ~Sstem: Diesel Gen. Lube Oil GORR No.: 93-T-008 Line: N/A Construction Code: Alco Diesel, Model 16-251-F Specifications.

Work Performed B : 1 Name of Com onent: V-5987 & 5979 Disc Replacements.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the Discs'in Valves 5987 &

5979 which contains the Lube Oil Temperature Control VILV Thermostats on the Alco Diesel Generators, Model 16-251-F.

This activity was controlled by WO number 9240996. The for this activity were obtained under PO number NQ Discs'tilized 12970 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

10. ASME Class: 3 ~S stem: Auxiliary Feedwater GORR No.: 93-T-009 Construction Code: B31.1, 1973 Edition & ASME Section Work Performed B  :

III, 1986 Edition for Welding & NDE.

1 Name of Com onent: Piping & Coupling by Valve 4023.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: A Maintenance Replacement activity was initiated to replace eroded section of piping and 1 coupling downstream of the Turbine Driven Auxiliary Feedwater Pump Recirculation Valve. This activity was controlled by WO number 9320243, and NCR's93-044 & 93-107. Items utilized for this activity were obtained from Tiose'ipe, Energy Steel, McJunkin and Haverstick under PO numbers VG 93015 BUG, NQ 12460 AJD, N ASC25888 1 & NEG 84464; Construction Code VT and PT NDE was performed to the requirements of Relief Request g 23 and acceptable. Upon completion of the replacement activity, a Functional Test. and accompanying VT-2 Examination was performed & acceptable as documented within PT-16Q-T and the Work Order.

14

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 8 Electric Cor . 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 REPLACEMENTS AND MODIFICATIONS: Cont.
11. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-010 Construction Code: B31.1, 1967 Edition & ASME Section Work Performed B :

III, 3

1986 Edition for Welding & NDE.

Name of Com onent: Valve 4611, Crane 150¹ Gate, 47 1/2XU Relief Re uest Used: RR ¹ 23 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4611. This activity was controlled by WO number 9122438, and TSR 92-002. Items utilized for this activity were obtained from Crane under PO number NQ 12921 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request ¹ 23 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

12. ASME Class: 3 ~Sstemi Service Water GORR No.: 93-T-011 Construction Code: B31.1, 1967 Edition & ASME Section Work Performed B :

III, 3

1986 Edition for Welding & NDE.

Name of Com onent: Valve 4738, Crane 150¹ Gate, 47 1/2XU Relief Re uest Used: RR ¹ 23 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4738. This activity was controlled by WO number 9221514, TSR 92-002 & SM-92-002.7.

Items utilized for this activity were obtained from Crane under PO number CP 42408 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request ¹ 23 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

15

Rs E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas 8 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: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.

13, ~ ASME Class: 1 ~S stem: RCS Pressurizer GORR No.: 93-T-012 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 1 Name of Com onent: Pressurizer Manway Bolts (TRC01)

Work Descri tion Remarks: A Replacement activity was initiated to replace 9 Pressurizer Manway Bolts. This acti.vity was controlled by Maintenance Procedure M-47.2 . Items used for this, activity are identified within the BOM, f22, per drawing 681J253 and obtained under PO number NEG 26848 (Heat g 15652).

Both VT-1 (ISI Preservice) and MT (Augmented IEB 82-02) examinations were performed and acceptable. Owner Elected UT examinations were also performed and acceptable. Upon completion of the replacement activity, a System Leakage Test and accompanying VT-2 Examination was performed & acceptable as documented within ISI Summary Examination number 93411000.

14. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-013 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B  : 3 Name of Com onent: MOV-4664; Stem, Disc & Body/Bonnet Bolting.

Work Descri tion Remarks: A Replacement activity was initiated on MOV-4664 to replace the Stem, Disc & Body/Bonnet Bolting.

This activity was controlled by WO number 9221521, TSR 90-004 and SM 92-002.5. The items utilized for this activity were obtained under PO numbers NQ 11984 BJD (Nuts & Studs), NQ 13252 AJD (Stem) & NQ 11984 BJD (Disc). Upon completion of the replacement activity, a VT-2 Inservice Test was performed and acceptable as documented within the Work Order.

16

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 8 Electric Cor . 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 REPLACEMENTS AND MODIFICATIONS: Cont.
15. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-015 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4625; Body/Bonnet Studs & Nuts.

Work Descri tion Remarks: A Replacement activity was initiated to replace the Body/Bonnet Studs & Nuts associated with V-4625. This activity was controlled by WO number 9221486. The items utilized for this activity were obtained under PO number NQ 13264 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

16. ASME Class: 3 ~S stem: Service Water. GORR No.: 93-T-016 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4626; Crane Gate Valve.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace Valve 4626. This activity was controlled by WO number 9221487, and SM 92-002.5. The items utilized for this activity were obtained from Crane under PO number NEG 29595 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request g 23 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Qiana Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 Applicable Edition of Section XI Utilized for Repiirs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
17. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-017 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4756; Plug (Wedge).

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the Plug (Wedge) in Valve 4756. This activity was controlled by WO number 9221537, NCR 93-09 and SM 92-002.6. The items utilized for this activity were obtained under PO number CP 45659 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as

.documented within the Work Order.

18. ASME Class: 3 ~Sstem: Comp. Cool. Water GORR No.: 93-T-018

"/"

Construction Code: ASME Section VIII, 1965 Edition.

Work Performed B : 1 Name of Com onent: "A" & !,'Bu CCW Heat, Exchanger Nuts/Bolts (EAC01A, EACOlB)

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace "B"

associated Nuts/Bolts on the "A" and CCW Heat Exchangers. This activity was controlled by WO numbers 9320141 and 9320142. The Nuts/Bolts utilized for this activity were obtained from Allied Nut & Bolt under PO number NQ 13264 AJD; Bolt Heat g 8078593, Nut Heat g E04277.

Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

18

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. 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 REPLACEMENTS AND MODIFICATIONS: Cont.

19. ASME Class: 1 ~S stem: CVCS Charging , GORR No.: 93-T-019 Construction Code: B31.1, 1967 Edition:

1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: AOV-294; Body/Bonnet, Gland Bolting, and Stem/Plug.

Work Descri tion Remarks: A Replacement activity was initiated to replace the Body/Bonnet, Gland Bolting & Stem/Plug associated with AOV 294. This activity was controlled by WO number 9221466, TSR 91-140 and SM 92.002.1. The items utilized for this activity were obtained under PO numbers NEG 42949 84 3 and NQ 12870 AJD. Upon completion of the replacement activity, a VT-2 Inservice Test was performed and acceptable as documented within the Work Order.

20. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-020 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4669; Gate Valve.

Relief Re uest Used: RR ¹ 23 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4669. This activity was controlled by WO number 9221508, TSR 92-002 and SM 92-002.7. The items utilized for this activity were obtained under PO number NQ 12921 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request ¹ 23 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

19

0 h

Re E ~ GINNA NUCLEAR POWER PLANT Inservice InsPection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

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 REPLACEMENTS AND MODIFICATOR'ONS: Cont.

21. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-021 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B  : 3 Name of Com onent: V-4760; Gate Valve.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4760. This activity was controlled by WO number 9320528, and TSR 92-002. The items utilized for this activity were obtained under PO number NQ 12921 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request g 23 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

22. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-022 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4739; Gate Valve.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4739. This activity was controlled by WO number 9320527, and TSR 92-002. The items utilized for this activity were obtained under PO number UG 92031 B-4G. Construction Code VT and PT NDE was performed to the requirements of Relief Request. g 23 and acceptable Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

20

R. E. "GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. 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 Modificationss 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
23. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-023 Construction Code: B31.1, 1983 Edition; 1986 Edition.

ASME Section III, Work Performed B  : 3 Name of Com onent: V-4618 Gate Valve; Stem & Plug (Disc).

Work Descri tion Remarks: A "Like for Like" Replacement activity was initiated to replace the Stem & Plug (Disc) for the Crane Gate Valve, Model L150 on Valve 4618. This activity was controlled by WO number 9221487, and SM 92-002.7. The items utilized for this activity were obtained from Crane under PO number CP 45659 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

24. ASME Class: 3 ~s stem: Service Water GQRR No.: 93-T-024 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4668B Gate Valve; Body/Bonnet, Bolting &

Plug (Disc) .

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the Body/Bonnet Bolting &

Plug (Disc) for the Velan Gate Valve in accordance with the component requirements contained within Drawing 83309 on Valve 4668B. This activity was controlled by WO number 9221534, and SM 92-002.7. The items utilized for this activity were obtained from Velan under PO number NQ 12976 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

21

0 Re Ee GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS'ont.
25. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-025 Construction Code: B31.1, 1986 1967 Edition; Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4640 Gate Valve; Body/Bonnet Bolting &

Plug (Disc).

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the Body/Bonnet Bolting &

Plug (Disc) for the Crane Gate Valve, Model L155 on Valve 4640. This activity was controlled by WO number 9221491, and SM 92-002.7. The items utilized for this activity were obtained from Crane under PO numbers NQ 13266 AJD (Disc) and NQ 13264 AJD, NQ 13391 AJD (Body/Bonnet Bolting). Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

26. ASME Class: 3 ~Sstem: Service Water GORR No.: 93-T-026 Construction Code: B31.1, 1967 Edition; 1986 Edition.

ASME Section III, Work Performed B : 3 Name of Com onent: V-4779 Gate Valve; Body/Bonnet Bolting.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the Body/Bonnet Bolting on Valve 4779. This activity was controlled by WO number 9221504, and SM 92-002.7. The items utilized for this activity were obtained under PO numbers NQ 12688 AJD, NQ 13391 AJD and NQ 13391 AJD. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

22

Re Ee GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 1999 Znterval, Second Period, First Outage (1993)

1. Owner< Rochester Gas 5 Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant! R.E.. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS: Cont.
27. ASME Class: 2 ~S stem: Main Steam GORR No.: 93-T-027 Construction Code: B31.1, 1955 Edition; Gilbert SP-5291, Work Performed B :

ASME 1

Section III, 1986 Edition.

Name of Com onent: V-3509; Inlet Flange Bolting/Nuts & Disc.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace four (4) Inlet Flange Bolts, two (2) Inlet Flange Nuts and the Valve Disc on Valve 3509.

This activity was controlled by WO number 9340888. The items utilized for this activity were obtained as follows: Studs, Nova Machine under PO Number NQ 10991 BRD; Nuts, Texas Bolt Company under PO numbers NEG 18607; Disc, Crosby Valve under PO number NEG 24469 82 9. Upon completion of the replacement activity, a Functional Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

28. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-028 Y

Construction Code: B31.1, 1986 Edition & ASME Section Work Performed B  :

III, 1986 3

Edition (Installation & NDE).

Name of Com onent: V-4663 Replacement.

Relief Re uest Used: RR g 24 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace Valve 4663. This activity was controlled by WO number 9221539, and TSEE 93-519. The items utilized for this activity were obtained under PO number NQ 12921 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request g 24 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

23

R. E ~ GINNA NUCLEAR POWER PLANT Inservice InsPection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 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,'eplacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS. Cont.
29. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-029 Construction Code: B31.1, & ASME (Installation Section

& NDE).

III, 1986 Edition Work Performed B : 3 Name of Com onent: MOV-4013.

Relief Re uest Used: RR ¹ 24 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace MOV-4013. This activity was controlled by WO number 9221426, and TSEE 93-521. The items utilized for this activity were obtained under PO number NQ 13571 AJD. Construction Code VT and PT NDE was performed to the requirements of Relief Request ¹ 24 and acceptable . Upon

.completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

30. ASME Class: 3 ~S stem: Service Water 'ORR No.: 93-T-030 Construction Code: B31.1, & ASME (Installation Section

& NDE).

III, 1986 Edition Work Performed B  : 3 Name of Com onent: MOV-4027.

Relief Re uest Used: RR ¹ 24 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace MOV-4027. This activity was controlled by WO number 9221424, and TSEE 93-521. The items utilized for this activity were obtained under PO number NQ 13571 AJD. Construction Code VT and PT NDE was performed to

. the requirements of Relief Request ¹ 24 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

R. E ~ GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 1999 Znterval, Second Period, First Outage (1993)

1. Owner: Rochester Gas 5 Electric Co . 89E. Ave. Rochester N.Y. 14649 2~ Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONSs Cont.
31. ASME Class: 3 ~Sstem: Service Water GORR No.: 93-T-031 Construction Code: B31.1, & ASME (Installation Section

& NDE).

III, 1986 Edition Work Performed B : 3 Name of Com onent: MOV-4028.

Relief Re uest Used: RR g 24 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace MOV-4028. This activity was controlled by WO number 9221423, and TSEE 93-521. The items utilized for this activity were obtained under PO number NQ 13571 GLD. Construction Code VT and PT NDE was performed to the requirements of Relief Request g 24 and acceptable . Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

32. ASME Class: 2 ~S stem: SG Blowdown GORR No.: 93-T-032 2E-BD-600-1A Construction Code:

Work Performed B  :

ASME Section 1 & 5 III, 1986 Edition.

Name of Com onent: AOV-5737 & 5738, Stem Replacement.

Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to replace the Masoneilian Stems on the Blowdown Isolation Valves 5737 & 5738. This activity was controlled by WO number 9300432. The stems utilized for this activity were obtained from Nova Machine under PO number NQ 13590 AJD, Heat g 98254. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

25

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990 - 1999 Znterval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 5 Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT ZZ REPLACEMENTS AND MODIFICATIONS: Cont.
33. ASME Class: 2 ~S stem: CVCS-Letdown GORR No.: 93-T-035 Construction Code: ASME Section III, 1965 Westinghouse Spec. G676257.

Edition per Work Performed B : 1 Name of Com onent: RV-209; Crosby Relief Valve, Model 51007.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace Crosby Relief Valve RV-209.

This activity was controlled by WO number 9300592. The items utilized for this activity were obtained under PO number NEG 16227, H 51007. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable as documented within the Work Order.

34. ASME Class: 2 ~S stem: Main Steam GORR No.: 93-T-036 Construction Code: B31.1 1974 1973 Edition Edition.

& ASME Section III, Work Performed B : 1 Name of Com onent: MSU-12 Support: Pin Replacement/

Modification Work Descri tion Remarks: A Replacement activity was initiated to replace a pin on a Pacific Scientific, Model PSA-35 S/N 9400, Mechanical Snubber on MSU-12 Support. The pin was also Modified by placing a center drill and tap hole for ease of removal in the future. This activity was controlled by WO number 9240443. The pin that was utilized for this activity was obtained from Basic Engineers under PO number NEG 11351, Heat g 42347. Upon completion of the replacement activity, a preservice VT-3 Examination was performed & acceptable as documented within the Work Order.

26

II 4

Re E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 5 Electric Co . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 Applicable Edition of Section XI Utilized for Repairs, Replacements or

~

Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS Cont.

35. ASME Class:1/2 ~S stem: CVCS-Charging/Letdown GORR No.:93-T-037 2E-CH-601 2H-CH-601 2A-CH4-151 Construction Code: B31.1, 1973 1974 Edition.

Edition; ASME Section III, Work Performed B : 1 Name of Com onents:

  • Class 1, CVU-46 Mechanical Snubber Support, Pacific Scientific Model PSA 1/4, S/N 38555.
  • Class 2, CVU-80 Mechanical Snubber Support, Pacific Scientific Model PSA 1/4, S/N 38556.
  • Class 2, CVU-351 Mechanical Snubber Support., Pacific Scientific Model PSA 1/2, S/N 9472.
  • Class 2, CVU-372 Mechanical Snubber Support, Pacific Scientific Model PSA 1/2, S/N 9490.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace the existing Mechanical Snubber component supports with ones that are identified above. The replacement activities were controlled by WO numbers 9340875, 9340689, 9340686 and 9320470; and NCR numbers93-081, 93-119,93-080 and 93-078. The items utilized for these activities were obtained from stock. Upon completion of the replacement activities, preservice VT-3 Examinations were performed & accepted as documented within the Work Orders.

27

R, E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
36. ASME Class: 2 ~S stem: Standby Aux.Feedwater GORR No.: 93-T-038 Construction Code: B31.1, 1974 1973 Edition; Edition.

ASME Section III, Work Performed B  : 1 Name of Com onent: Hydraulic Snubber AFU-205 Support, ITT Grinnell, Size 1 1/2", S/N 15403.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace an existing Hydraulic Snubber support with one identified above. The replacement activity was controlled by WO number 9340685 and NCR number 93-089. The item utilized for this activity was obtained from stock. Upon completion of the replacement activity, a preservice VT-3 Examination was performed & accepted as documented within the Work Order.

37. ASME Class: 2 ~S stem: Standby Aux.Feedwater GORR No.: 93-T-039 Construction Code: B31.1, 1974 1973 Edition; Edition.

ASME Section III, Work Performed B  : 1 Name of Com onent: Hydraulic Snubber AFU-209 Support, ITT Grinnell, Size 1 1/2", S/N 12904.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace an existing Hydraulic Snubber support with one identified above due to leaking oil.

The replacement activity was controlled by WO number 9320686.

The item utilized for this activity was obtained from stock.

Upon completion of the replacement activity, a preservice VT-3 Examination was performed & accepted as documented within the Work Order.

28

CI Re Ee GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas 8 Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant! R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ik ATTACHMENT Z Z REPLACEMENTS AND MODIFICATIONS: Cont.
38. ASME Class: 2 ~S stem: Steam Generator "B" GORR No.: 93-T-040

"/"

Construction Code: Gilbert Spec. 5378 & 5291.

Work Performed B : 1 Name of Com onent: Hydraulic Snubber SGB-4 Support, Anker Holth AH-5.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace an existing Hydraulic Snubber support with one identified above. The replacement activity was controlled by WO number 9341087 and NCR Number 93-148. The item utilized for this activity was obtained from stock. Upon completion of the replacement activity, a preservice VT-3 Examination was performed & accepted as documented within the Work Order.

39. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-041

/

Construction Code:

1. Bowl Assembly Gilbert SP-5291; BOM MD-1, Spec. R0-2204.
2. Pump Bowl Bolting Gilbert BOM MD-1, Spec. RO-2204 & ASME Section III, 1986 Work Performed B  : 1 Edition.

Name of Com onent: Service Water Pump "A", PSWOlA.

1. Pump Bowl Assembly Swap Out.
2. Pump Bowl Bolting Replacement.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to Swap Out"A"the existing Pump Bowl Assembly on the Service Water Pump and replace original spare. This replacement activity was controlled by WO it with an number 9320651. Also, an "Approved Equivalent" replacement activity was initiated on eight (8) Pump Bowl Bolts (3/4"-10 x 2"). This replacement activity was controlled by WO number 9221833 and TSEE 91-546. The bolts utilized for this activity was obtained from Nova Machine under PO Number NQ 12702 AJD, Heat g 4-9943FA. Upon completion of the replacement activity, a Flow Test and accompanying VT-2 Examination was performed &

accepted as documented within the Work Order and PT-2.7.1 29

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
40. ASME Class: 3 ~S stem: Service Water GORR No.: 93-T-042 Construction Code: ASME Section Work Performed B : 1 III, 1980/86 Edition.

Name of Com onent: V-4668F; Bonnet/Body Nuts & Studs.

Work Descri tion Remarks: A "Like-for-Like" Replacement activity was initiated to replace 16 Nuts & 8 Studs associated with Valve 4668F Bonnet to Body connection. The replacement activity was controlled by WO number 9102122. Items utilized for this activity were obtained from Allied Nut & Bolt under PO Number NQ 13264 AJD for Heat Numbers 8866807 (Studs) and B81716 (Nuts). Upon completion of the replacement activity, an Inservice Test, and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

41. ASME Class: 2 stem: Service Water GORR No.: 93-E-002

"/

~S Construction Code: B31.1, 1967 Edition.

Work Performed B : 1 Name of Com onent: 3" Header Pipe of the Containment Recirculating Fan "C" Cooling Coil (ACA01C) Mechanical Plug.

Code Cases Used: N-416 Work Descri tion Remarks: An "Approved Equivalent" Replacement activity was initiated to install a Vibra-Proof Mechanical Plug into a decayed 5/8" Copper Tube within the 3" Header Pipe of the Containment Recirculating Fan "C" Cooling Coil. This activity is considered a replacement activity as allowed by B31.1, Part 4 under "Sleeve Coupled and Other Proprietary Joints". This activity was controlled by NCR 92-394 and WO Number 9201949. The item utilized for the replacement activity was obtained under PO Number NQ 11633 BJD. A visual verification of the installation was performed to ensure proper assembly. Upon completion of the replacement activity, a Leak Test was, performed & acceptable as documented within the Work Order & GORR Report.

30

R. E ~ GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649 2 ~ Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519 3 ~ Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
42. ASME Class: 2 ~S stem: 'Instrument Air GORR No.: 93-E-003 Construction Code: ASME Section Work Performed B : 2 III, 1986 Edition.

Name of Com onent: Instrument Air Containment Isolation Check, Valve 5393 & Associated Piping per EWR 5150.

Code Cases Used: N-416 Work Descri tion Remarks: A "Modification" Replacement activity was initiated under EWR 5150 that replaced Valve 5393 and associated piping. This activity was controlled under SM 5150.1 and 5150.2. The replaced valve was a BNL Screwed End Check N9212003-1 that was obtained under PO Number NQ 13506-B-DH. A Construction Code VT Examination was performed on the brazed connections and acceptable. Upon completion of the replacement activity and reassembly, a System Functional Test and associated VT-2 Examination was performed & acceptable.

43 ASME Class: 3 ~S stem: Aux. Feedsatex GORR No.: 93-E-004 Construction Code: ASME Section Work Performed B : 2 III, 1986 Edition.

Name of Com onent: Turbine Driven Auxiliary Feedwater Pump Recirculation Check Valve 4023 per EWR 4951.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: A "Modification" Replacement activity was initiated under EWR 4951 that replaced Valve 4023 and one joint (pipe to 5 x 1 1/2 reducer). This activity was controlled under SM 4951.1 . The replaced valve was a Kerotest 31612GS that was obtained under PO Number NQ 13413-B-DH. Construction Code VT and PT NDE was performed to the requirements of Relief Request g 23 and acceptable. Also, on the one reducer joint, an RT exam was performed and acceptable. Upon completion of the replacement activity, a Functional Test and accompanying VT-2 Examination was performed & acceptable.

31

Re E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas E Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XZ Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
44. ASME Class: 3 ~S stem: Service Water GORR No.: 93-E-005 Construction Code: ASME Section Work Performed B : 2 III, 1986 Edition.

Name of Com onent: Service Water Butterfly Valves 4609 &

4780 per EWR 5098.

Work Descri tion Remarks: A "Modification" Replacement activity was initiated under EWR 5098 that replaced existing Butterfly Valves 4609 & 4780 with new stainless steel wafer Butterfly Valves. A new pup piece between the valves was fabricated utilizing slip on flanges. This activity was controlled under SM 5098.2 . The replaced valves were obtained from XOMOX ( 8" 'Fig. 801 HPBV) under PO Number NQ 12565-B-DH per drawing N91139NZX3326. Construction Code VT and PT NDE was performed and acceptable. Upon completion of the replacement activity, an Inservice Test and accompanying VT-2 Examination was performed & acceptable.

45. ASME Class: 3 ~S stem: Service Water GORR No.: 93-E-008 Construction Code: ASME Section Work Performed B : 2 III, 1986 Edition.

Name of Com onent: Service Water Butterfly Valves 4613 per EWR 5098.

Relief Re uest Used: RR g 23 Work Descri tion Remarks: A "Modification" Replacement activity was initiated under EWR 5098 to replace the existing Butterfly Valve 4613 with a new Butterfly Valve. This activity was controlled under SM 5098.1 . The replaced valve was obtained from XOMOX (10" Fig. 801 HPBV) under PO Number NQ 12565-B-DH per drawing N91140NZX3326. Construction Code VT, PT and RT NDE was performed and acceptable. Upon completion of the replacement activity, a Functional Test, and accompanying VT-2 Examination was performed & acceptable in accordance with Relief Request Number 23.

32

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

l. Owner: Rochester Gas 5 Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
46. ASME Class: 2 ~S stem: Service Water GORR No.: 93-E-010 93-E-011 Line: N/A Construction Code:
l. ASME Section VIII, V,
2. ASME Section III, III; 1986 1986 Edition.

Editions.

Work Performed B : 2 Name of Com onent: EWR 5275.

1. Containment Recirculation Fan Cooler Cooling Coils, 12 Components (ACA01A, ACAOlE, ACA01F, ACAOlB, ACA01G, ACA01HI ACA01CI ACAOlJg ACA01Kg ACA01DI ACAOlLI&'ACA01M)
2. Installation of applicable 8", 4" & 3" Carbon Steel Piping.

Code Cases Used: N-416 Work Descri tion Remarks: A "Modification" Replacement activity was initiated under EWR 5275 to replace the 12 Containment Recirculation Fan Cooler Cooling Coils and associated 8", 4" & 3" piping to suit the needed configuration. This activity was controlled under SM 5150.1 and 5150.2. The replaced Cooling Coils were obtained from Marlo Coil; Model g's 12Q20-120-5608T-25.3-H-3.0-L & 12Q20-120-5608T-25.3-H-3.0-R under PO Number NQ 13295-A-JD.

Applicable Construction Code piping examinations of VT, MT, and RT were performed and acceptable. The Cooling Coils had a Construction Hydrostatic Test to 225 psig. and was acceptable.

Upon completion of the installation of the replacement activity, a System Functional Test and associated VT-2 Examination was performed & acceptable.

33

R. E ~ GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, First Outage (1993)

1. Owner: Rochester Gas & Electric Cor . 89E. Ave. Rochester N.Y. 14649
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications: 1986 No Addenda ATTACHMENT II REPLACEMENTS AND MODIFICATIONS: Cont.
47. ASME Class: 3 ~S stem: Service Water GORR Nc.: 93-M-003 Construction Code: B31.1, 1983 Edition.

Work Performed B : 3 Name of Com onent: MOV-4615, Disc 6 Body/Bonnet Bolting.

Work Descri tion Remarks: During a Maintenance activity, a Replacement activity was initiated to replace the Crane Disc and Body/Bonnet Bolting associated with MOV-4615. This activity was controlled by WO number 9221494 and SM 92-002.7.

The items utilized for this activity were obtained from Crane for a Chapman L155 under PO number NQ 12688 AJD. Upon completion of the replacement activity and reassembly, an Inservice Test and accompanying VT-2 Examination was performed

& acceptable as documented within the Work Order.

34

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III EROSION/CORROSION (MINWALL) PROGRAM

SUMMARY

This section provides Erosion/Corrosion examination details and information corresponding to items inspected prior to or during the 1993 Ginna Outage.

A total of 192 items were examined prior to or during the 1993 Outage. The breakdown of this total number is as follows:

Component Type Total Number Pipes 84 Elbows 41 Reducers 36 Tees 21 Caps Tanks 2 Nozzles 2 Heater Shells 2 Total 192 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. SYSTEM M-1 A/8 FW Pump Discharge to 5 A/8 Heaters M-78 Condensate Pump 6 Heater Drain Tank Discharge to Feedwater Suction.

M-11A MSR 1A 6 18 2nd Pass Drain M-118 MSR 2A 6 28 2nd Pass Drain M-12A MSR 1A 6 18 2nd Pass to 5A Heater 6 Condenser

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stems of Examined Com onents: Cont.

DWG.

NO SYSTEM M-12B MSR 2A & 2B 2nd Pass to 5B Heater & Condenser M-15B MSR 1B 4th Pass to 5A Heater

.M-17A MSR 2A 4th Pass to 5B Heater M-17B MSR 2B 4th Pass to 5B Heater M-18 MSR 2A & 2B 4th Pass to Condenser M-21 Steam Extraction to Preseparator Tank B & 4B

'.P.H.

M-22 Steam Extraction to Preseparator Tank A & 4A L.P.H.

M-3l MSR 1A & 1B to Heater Drain Tank & Condenser M-32 MSR 2A & 2B to Heater Drain Tank M-41A 5A H.P. Heater Drain to 4A L.P. Heater M-4 1B 5B Heater Drain to 4B Heater M-45 Preseparator A/B to Heater Drain Tank & Condenser M-46B Preseparator A/B to Heater Drain Tank M-48 Auxiliary FW Pump A to Discharge Lines M-49 Auxiliary FW Pump B to Discharge Lines M-50 M.D. Aux. FW Pumps to T.D. F.W. Pumps Crossover M-71 Mainsteam from S/G 1A (Intermediate Building)

M-72 Mainsteam to Turbine (Turbine Building)

M-75 Steam Extraction to 5A & 5B Heaters M-81 Feedwater Discharge (Turbine Building)

M-82 Feedwater Discharge (Intermediate Building)

M-88D S/G Blowdown to Flash Tank (Turbine Building)

M-89A S/G 1A Blowdown Line (Inside Containment)

M-89B S/G 1B Blowdown Line (Inside Containment)

M-89C S/G 1B Blowdown Line (IC) to PEN. 322 M-90 Feedwater Clean Up (CV-18)

M-91 Feedwater Clean Up (CV-19)

M-92 Main Feedwater Pump Recirc.

M-93 Feedwater By-Pass Line M-98 S/G Blowdown Tank to Condenser

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stems of Examined Com onents: Cont.

DWG.

NO. SYSTEM M-99 Turbine Gland Steam from Generator & Governor Ends to Gland Steam Condenser M-100 Turbine Gland Steam Mainsteam to Turbine Generator & Governor Ends.

M-101 Turbine Gland Steam Condenser to Main Condenser A M-102 FW Heater Vents (Extraction Steam) from Heater Drain Tank to Extraction Steam Heater 4 M-103 Feedwater Heater Drain System from H.D. Pumps Discharge to H.D. Tank M-104 Condensate L.P. FW Heaters from L.P. FW Heaters 3 to L.P. FW Heaters 4 S stem Com onent Results:

The following break down by system provides general results on the component types that were examined.

DWG.

No. ~setem M-1 A/B F.W PUMP DISCHARGE TO 5 A/B HEATERS Components Examined: Results:  % of Nominal 2 Pipe(s) 2 >88~m M-7B CONDENSATE PUMP & HEATER DRAIN TANK DISCHARGE TO FEEDWATER SUCTION Components Examined: Results: s of Nominal 1 Pipe(s) 4 >88%

2 Reducer(s) 1 Tee(s)

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG ~

No. ~em tern M-11A MSR 1A & 1B 2ND PASS DRAIN Components Examined: Results: . of Nominal 1 Elbow(s) 4 >8 8~e 1 Nozzle(s) 1 Pipe(s) 1 Reducer(s)

M-11B MSR 2A & 2B 2ND PASS DRAIN 'I Components Examined: Results:  % of Nominal 2 Elbow(s) 7 >884 1 Nozzle(s) 3 Pipe(s) 1 Reducer(s)

M-12A MSR 1A & 1B 2ND PASS TO SA HEATER & CONDENSER Components Examined: Results: . of Nominal 2 Pipe(s) 2 >88~o M-12B MSR 2A & 2B 2ND PASS TO 5B HEATER & CONDENSER Components Examined: Results:  % of Nominal 1 Pipe(s) 2 >88%

1 Reducer(s)

M-15B MSR 1B 4TH PASS TO 5A HEATER Components Examined: Results:  : of Nominal 1 Cap(s) 1 >88%

1 Reducer(s) 1 88-82~e M-17A MSR 2A 4TH PASS TO 5B HEATER Components Examined: Results:  % of Nominal 3 Reducer(s) 1 >88~o 1 88 82o 1 70-65~m

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~set em M-17B MSR 2B 4TH PASS TO 5B HEATER Components Examined: Results:  % of Nominal 1 Pipe(s) 2 >889' 3 Reducer(s) <65'o M-18 MSR 2A & 2B 4TH PASS TO CONDENSER Components Examined: Results:  % of Nominal 2 Pipe(s) 3 >88%,

2 Reducer(s) 1 76-704 3 Tee(s)

M-21 STEAM EXTRACTION TO PRESEP. TANK B & 4B LP. HEATER Components Examined: Results: o of Nominal 4 Elbow(s) 8 >88%

5 Pipe(s) 1 70-65~o M-22 STEAM EXTRACTION TO PRESEP. TANK A & 4A LP. HEATER Components Examined: Results: '. of, Nominal 2 Elbow(s) 3 >88%

5 Pipe(s) 1 88-82~o 1 82-76~o 1 76-70%

1 70-65~o M-31 MSR 1A & 1B TO HEATER DRAIN TANK & CONDENSER Components Examined: Results:  % of Nominal 1 Elbow(s) 5 >88%

3 Pipe(s) 1 88 82+o 3 Reducer(s) 1 76 70~o

4 0

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~sstem M-32 MSR 2A & 2B TO HEATER DRAIN TANK Components Examined: Results:  % of Nominal 2 Pipe(s) 2 >88~0 3 Reducer(s) 1 88 8 2+o 1 82 7 6+o 1 76-70~m M-41A . 5A HP HEATER DRAIN TO 4A LP HEATER Components Examined: Results:  % of Nominal 2 Pipe(s) 2 >88~o M-41B SB HEATER DRAIN TO 4B HEATER Components Examined: Results: . of Nominal 3 Elbow(s) 6 >88~m 2 Pipe(s) 1 76-70~o 1 Reducer(s) 1 Tee (s)

M-45 PRESEPARATOR A/B TO HEATER DRAIN TANK AND CONDENSER Components Examined: Results: o of Nominal 1 Pipe(s) 1 >88~m M-46B PRESEPARATOR A/B TO HEATER DRAIN TANK Components Examined: Results:  % of Nominal 3 Pipe(s) 2 >88~m 2 Reducer(s) 1 88 82~o 2 Tee(s) 1 82-76~m 2 70-65>

1 (654

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG ~

No. ~sstem M-48 AUX F.W. PUMP A TO DISCHARGE LINES Components Examined: Results:  % of Nominal 4 Elbow(s) 6 >88~o 3 Pipe(s) 1 88 8 2~o M-49 AUX F.W. PUMP B TO DISCHARGE LINES Components Examined: Results: s of Nominal 2 Elbow(s) 9 >88~o 5 Pipe(s) 2 Reducer (s)

M-50 M.D. AUG F.W. PUMPS TO T.D. F.W. PUMPS CROSSOVER Components Examined: Results: % of Nominal 2 Elbow(s) 4 ~ >88~o 3 Pipe(s) 1, <65~e M-71 MAINSTEAM FROM S/G 1A (INTERMEDIATE BLDG)

Components Examined: Results:  % of Nominal 1 Elbow(s) 1 >88~o M-72 MAINSTEAM TO TURBINE (TURBINE BLDG)

Components Examined: Results:  : of Nominal 1 Elbow (s) 2 >88%

1 Pipe(s)

M-75 STEAM EXTRACTION TO 5A & SB HEATERS Components Examined: Results:  % of Nominal 4 Pipe(s) 2 >88%

1 Tee(s) 1 88-82~e 2 <65<m

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~Set em M-81 FEEDWATER DISCHARGE (TURBINE BLDG)

Components Examined: Results: . of Nominal 1 Elbow(s) 6 >88<m 2 Pipe(s) 1 70-65'o 4 Reducer(s) 1 (65~o 1 Tee(s)

M-82 FEEDWATER DISCHARGE (INTERMEDIATE BLDG)

Components Examined: Results: : of Nominal 1 Pipe(s) 1 >88~

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

Components Examined: Results: % of Nominal 1 Elbow(s) 2 >884 2 Pipe(s) 2 88-82~m 1 Reducer(s) 1 82-76<m 1 Tee(s)

M-89A S.G. 1A BLOWDOWN LINE (INSIDE CONT.)

Components Examined: Results: . of Nominal 3 Pipe(s) 4 >88Se 1 Tee(s)

M-89B S.G. 1B BLOWDOWN LINE (INSIDE CONT.)

Components Examined: Results:  % of Nominal 4 Pipe(s) 7 >889' Tee(s)

M-89C S.G 1B BLOWDOWN LINE (IC) TO PEN. 322 Components Examined: Results:  % of Nominal 1 Elbow(s) 1 >88%

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~Sstem M-90 FEEDWATER CLEAN UP (CV-18)

Components Examined: Results:  % of Nominal 1 Pipe(s) 1 >884 1 Reducer(s) 1 76-70>o M-91 FEEDWATER CLEAN UP (CV-19)

Components Examined: Results:  % of Nominal 1 Elbow(s) 1 70-65~m 1 Pipe(s) 1 <65'o M-92 MAIN FEEDWATER PUMP RECIRC Components Examined: Results:  % of Nominal 3 Elbow(s) 10 >88 ~e 4 Pipe(s) 1 Reducer(s) 2 Tee(s)

M-93 FEEDWATER BY-PASS LINE Components Examined: Results: : of Nominal 2 Elbow(s) 4 >88%

2 Pipe(s)

M-98 SG BLOWDOWN TANK TO CONDENSER Components Examined: Results:  % of Nominal 1 Elbow(s) 1 >88%

1 Pipe(s) 1 88 82~o M-99 TURBINE GLAND STEAM FORM GEN & GOV ENDS TO GLAND STEAM CONDENSER Components Examined: Results:  % of Nominal 1 Pipe(s) 1 >88~m 1 Reducer(s) 1 82 76~o

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~setem M-100 TURBINE GLAND STEAM MAINSTEAM TO TURBINE GEN. 6 GOV.'NDS Components Examined: Results: . of Nominal 1 Elbow(s) 2 >88~o 1 Reducer(s) 1 88 82~o 1 Tee(s)

M-101 TURBINE GLAND STEAM CONDENSER TO MAIN CONDENSER A Components Examined: Results: : of Nominal 1 Pipe(s) 2 >88~o 1 Reducer(s)

M-102 F.W. HEATER VENTS (EZTRACTION STEAM) FROM HEATER DRAIN TANK TO EXTRACTION STEAM HTR 4 Components Examined: Results: ~o of Nominal 4 Elbow(s) 10 >88%

6 Pipe(s) 1 <65-:

1 Tee(s)

M-103 FEEDWATER HEATER DRAIN SYSTEM FROM H.D. PUMPS DISCH.

TO H.D. TANK Components Examined: Results: '. of Nominal 1 Cap(s) 5 >88~m 2 Pipe(s) 1 88 82~o 1 Reducer(s) 2 Tee(s)

M-104 CONDENSATE L.P. F.W. HEATERS FROM L.P. F.W. HTR'S 3 TO L P F.W. HTR'S 4 Components Examined: Results:  % of Nominal 3 Elbow(s) 6 >88~m 2 Pipe(s) 1 Tee (s) 10

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III S stem Com onent Results: Cont.

DWG.

No. ~Sstem NA Miscellaneous Examinations Components Examined: Results:  % of Nominal 2 Tanks 6 2 Tank caps Heater shells

>889'om 2

onent Result Details:

The following list provides component result details of examinations by drawing number. The "Component Type" code specified in the list below equates to the following:

C = Cap E = Elbow N = Nozzle P = Pipe T = Tee R = Reducer/Expander Drawin No. M-1 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 200035 03A P 0.938 0. 656 0.880 >88 UT 200110 11 P 0.938 0. 656 0.902. >88 UT Drawin No. M-7B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent, NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 208360 36 R 0.375 0.365 .263/.256 0.361 >88 UT 208380 38 R 0.365 0.406 .256/.263 0.358 >88 UT 208570 57 T 0.375 0.263 0.509 >88 UT 208580 58 P 0.375 0.263 0.374 >88 UT

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report, 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-11K Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 215010 1 N 0.500 0. 350 0.545 >88 UT 215015 1A R 0.500 0.432 .350/.302 0.472 >88 UT 215020 '

E 0.432 0.302 0.388 >88 UT 215030 3 P 0.432 0.302 0.432 >88 UT Drawin No. M-11B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 216352 114A N 0.500 0.350 0.505 >88 UT 216357 114B R 0.500 0.432 .350/.302 0.501 >88 UT 216360 114 P 0.432 0.302 0.426 >88 UT 216370 115 E 0.432 0.302 0.402 >88 UT 216375 115A P 0.432 0.302 0.421 >88 UT 216380 116 E 0.432 0.302 0.408 >88 216390 117 P 0.432 0.302 0.401 >88 UT 12

H R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-12A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 222920 90 P 0.593 0. 415 0.565 >88 UT 222930 91 P 1.031 0.722 0.998 >88 UT Drawin No. M-12B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 222470 45 R 0.432 0.300 .302/.210 0.310 >88 UT 222675 65A P 0.500 0.415 0.524 >88 UT Drawin No. M-15B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 227060 58 C 0.938 0 '57 0.943 >88 UT 227377 89B R 0.218 0.179 .104/.081 0.183 83.9 RT Drawin No. M-17A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 230365 36A R 0.300 0.179  ? /.095 0.120 67.0 RT 230382 38A R 0.179 0.218 .081/.104 0.182 83.5 RT 230387 38B R 0.218 0.337 .153/.236 0.224 >88 UT 13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-17B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 231375 87A 0.300 0.179 /.095 0.111 62.0 RT

'T R  ?

231390 89 P 0.337 0. 236 0. 315 >88 231392 89A R 0.179 0.218 .081/.093 0.166 RT 231397 89B R 0.218 0.337 .153/.236 0.221 >88 UT Drawin No. M-18 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 232192 19A R 0.300 0.179  ? /.095 0.194 RT 232197 19B P 0. 179 0. 095 0.162 90.5 RT 232300 30 T 0.500 0.337 .350/.236 0.323 >88 UT 232452 45A R 0.300 0.179  ? /.095 0.178 RT 232457 45B P 0. 179 0.095 0.135 75.4 RT 232560 56 T 0.500 0.337 .350/.236 0.313 >88 UT 232570 57 T 0.500 0.337 .350/.236 NE UT 14

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Inter'val, Second Period, First Outage (1993)

ATTACHMENT III Com onent, Result Details: Cont.

Drawin No. M-21 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 301250 23 P 0.375 0.328 0.364 >88 UT 301260 24 E 0.375 0.328 0.381 >88 UT 301270 25 P 0.375 0.328 0.349 >88 UT 301280 26 E 0.375 0.328 0.353 >88 UT 301290 27 P 0.375 0.328 0.362 >88 UT 301300 28 E 0.375 0.328 0.368 >88 UT 301310 29 P 0.375 0.328 0.377 >88 UT 301345 32A P 0.375 0.263 0.355 >88 UT 301370 35 E 0. 375 0.263 0.245 70-65 UT Drawin No. M-22 Summary Comp. Comp ~ Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 302020 29 P 0 ~ 375 0.328 0.380 >88 UT 302030 30 E 0.375 0.328 0.384 >88 UT 302040 31 P 0.375 0.328 0.353 >88 UT 302050 32 E 0.375 0.263 0.312 88-82 UT 302060 32A P 0.375 0.263 0.259 70-65 UT 15

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-22 Cont.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 302065 32B P 0.375 0.263 0.303 82-76 UT 302170 42 P 0.375 0.263 0.270 76-70 UT Drawin No. M-31 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 260005 1A R 0.500 0.432 .350/.302 0.487 >88 UT 260010 1 P 0.432 0.302 0.410 >88 UT 260025 2A E 0.432 0.302 0.411 >88 UT 260200 20 P 0.432 0.302 0.406 >88 UT 260240 24 R 0.500 0.432 .350/.302 0.358 76-70 UT 260247 24C P 0.432 0.302 0.397 >88 UT 260315 31A R 0.432 0.300 .302/.210 0.265 88-82 UT Drawin No. M-32 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 261005 1A R 0.500 0.432 .350/.302 0.427 88-82 UT 261010 1 P 0.432 0.302 0.411 >88 UT 16

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-32 Cont.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 261255 26A R 0.500 0.432 .350/.302 0.367 76-70 UT 261260 26 P 0.432 0.302 0.413 >88 UT 261435 43A R 0.432 0.300 .302/.210 0.354 82-76 UT Drawin No. M-41A Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 290010 1 P 0.432 0.302 0.403 >88 UT 290260 26 P 0.593 0.415 0.583 >88 UT Drawin No. M-41B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 291090 48 T 0.432 0.302 0.465 >88 UT 291100 49 P 0.432 0. 302 0.413 >88 UT 291270 66 P 0.432 0.302 0.420 >88 UT 291275 66A E 0.432 0.302 0.326 76-70 UT 291280 67 E 0.432 0.302 0.422 >88 UT 291290 68 E 0.432 0.302 0.418 >88 UT 291325 71A R 0.432 0.593 .302/.415 0.509 >88 UT 17

4 0

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-45 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 298690 69 P 0.432 0.302 0.419 >88 UT Drawin No. M-46B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 328090 9 T 0.432 0. 302 0.294 70-65 UT 328110 11 P 0.432 0.302 0.336 82-76 UT 328640 64 T 0.432 0.302 0.297 70-65 UT 328660 66 P 0.432 0.302 0.264 <65 UT 328665 66A R 0.432 0.337 .302/.236 0.369 88-82 UT 328675 67A R 0.337 0.432 .236/.302 0.366 >88 UT 328680 68 P 0.432 0.302 0.419 >88 UT Drawin No. M-48 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 320490 49 E 0. 179 0. 157 0.228 >88 RT 320500 50 E 0. 179 0. 157 0.253 >88 RT 320510 51 P 0. 179 0. 157 0.170 >88 RT 18

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-48 Cont.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 320521 52A P 0.179 0.157 0.157 >88 RT 320530 53 E 0 '79 0.157 0.272 >88 RT 320550 55 E 0.218 0.191 0.286 >88 RT 320560 56 P 0.218 0.191 0.183 83.9 RT Drawin No. M-49 1

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 323512 51A P 0.179 0.157 0.175 >88 RT 323520 52 E 0.179 0. 157 0.267 >88 RT 323561 56A R 0.218 0.200 .191/.175 0.298 >88 RT 323562 56B P 0.200 0. 175 0.193 >88 RT 323571 57A P 0.200 0. 175 0.195 >88 RT 323572 57B R 0.200 0.218 .175/.191 0.296 >88 RT 323573 57C P 0.218 0. 191 0. 197 >88 RT 323580 58 E 0.218 0. 191 0.290 >88 RT 323590 59 P 0.218 0. 191 0.192 >88 RT 19

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-50 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 330010 1 P 0. 179 0.157 0. 164 >88 RT 330060 6 P 0. 179 0.157 0.158 >88 RT 330320 32 P 0. 218 0.191 0.203 >88 RT 330330 33 E 0. 218 0.191 0.362 >88 RT 330340 34 E 0.218 0.191 0.110 50.5 RT Drawin No. M-71 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 371010 1 E 1.250 1.143 1.284 >88 UT Drawin No. M-72 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 372160 16 P 1. 000 0. 914 1.052 >88 UT 372170 17 E 1. 000 0. 914 1.159 >88 UT 20

R. E. GINNA NUCLEAR POHER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-75 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 303040 4 T 0. 375 0.263 0.205 <65 UT 303055 5A P 0.375 0.263 0.321 88-82 UT 303065 6A P 0.375 0.263 0.190 <65 UT 303150 15 P 0.375 0.263 0.380 UT

>88'.414 303290 29 P 0.375 0.263 >88 UT Drawin No. M-81 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 390010 1 T 1.281 1.010 1.302 >88 UT 390020 2 R 1.281 0.938 1.010/.708 0.943 >88 UT 390035 3A P 0.938 0.609 0.865 >88 UT 390040 4 R 0.938 0.843 .706/.644 0.853 >88 UT 390060 6 R 0.843 0.937 .708/.646 0.555 70-65 UT 390065 6A P 0.937 0.708 0.891 >88 UT 390210 21 R 0.843 0.937 .708/.646 0.455 <65 UT 390230 23 E 0.938 0.713 0.902 >88 UT 21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-82 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 392050 5 P 0.938 0. 633 0.911 >88 UT Drawin No.'M-84 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 393140 14 P 0.938 0. 607 NE UT 393150 15 R 1 '56 0.937 .986/.802 NE UT 393160 16 E 0.938 0.893 NE UT Drawin No. M-88D Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 385392 39B P 0.337 0.170 0.300 >88 UT 385730 73 E 0.300 0.210 0.253 88-82 UT 385745 74A R 0.300 0.337 .210/.236 0.311 >88 UT 385750 75 P 0.337 0.236 0.291 88-82 UT 385800 80 T 0.500 0.337 .350/.236 0.394 82-76 UT 22

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-89K Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 387070 7 P 0.218 0.110 0.210 >88 RT 387110 11 P 0.218 0.180 0.207 >88 RT 387120 12 T 0.218 0.190 0.279 RT

>88'.204 387150 15 P 0.218 0.170 >88 RT Drawin No. M-89B Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 388020 2 P 0.218 0. 138 0.218 >88 RT 388030 3 T 0.218 0.161 0.252 >88 RT 388040 4 P 0.218 0.142 0.215 >88 RT 388050 5 T 0.218 0.128 0.240 . >88 RT 388060 6 P 0.218 0.120 0.209 >88 RT 388070 7 T 0.218 0.135 0.280 >88 RT 388080 8 P 0.218 0.185 0.217 >88 RT 23

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-89C Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 388320 32 E 0. 218 0. 128 0.215 >88 RT Drawin No. M-90 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 300450 44 R 0.432 0.337 .302/.236 0.386 >88 UT 300460 45 P 0.337 0.236 0.237 76-70 UT Drawin No. M-91 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 300840 38 E 0.432 0.302 0.289 70-65 UT 300850 39 P 0.432 0.302 0.269 (65 UT Drawin No. M-92 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 281060 6 E 0.500 0.337 .350/.236 0.626 >88 UT 281090 9 P 0.337 0.236 0.327 >88 UT 281200 20B E 0.500 0.337 .350/.236 0.444 >88 UT

0 1I

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-92 Cont.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 281210 21 P 0.337 0. 236 0. 304 >88 UT 281250 25 P 0.337 0.236 0.319 >88 UT 281530 53 R 0.688 0.500 .482/.350 0.763 >88 UT 281540 54 T 0.500 0.337 .350/.236 0.517 >88 UT 281560 56 E 0.594 0.415 0.552 >88 UT 281570 57 P 0.594 0.415 0.536 >88 UT 281580 58 T 1.031 0.594 .656/415 0.855 >88 UT Drawin No. M-93 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 394100 11 E 0.337 0.236 0.319 >88 UT 394110 12 P 0 '37 0.236 0.322 >88 UT 394260 27 E 0.337 0.236 0.301 >88 UT 394270 28 P 0.337 0.236 0.325 >88 UT 25

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-98 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 398170 17 E 0.337 0.236 0.280 88-82 UT 398180 18 P 0.337 0.236 0.307 >88 UT Drawin No. M-99 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 374790 79 R 0.406 0.365 .284/.256 0.318 82-76 UT 374800 80 P 0.365 0.256 0.359 >88 UT Drawin No. M-100 Summary Comp. Comp.. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 375040 4 R 0.203 0.280 .142/.196 0.197 >88 UT 375050 5 E 0.280 0 ~ 196 0.245 88-82 UT 375070 7 T 0.280 0. 196 0.259 >88 UT 375080 8 P 0.280 0. 196 NE UT 26

R. E. -GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont,.

Drawin No. M-101 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 376440 44 R 0.322 0.280 .226/.196 0.302 >88 UT 376450 45 P 0.280 0.196 0.260 >88 UT Drawin No. M-102 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable .Readin Nominal T 324010 1 P 0.237 0.166 0.077 <65 UT 324020 2 E 0.237 0.166 0.237 >88 UT 324030 3 P 0.237 0.166 0.221 >88 UT 324050 5 P 0.237 0. 166 0.238 >88 UT 324060 6 E 0.237 0.166 0.212 >88 UT 324160 16 E 0.237 0.166 0.219 >88 UT 324170 17 P 0.237 0.166 0.239 >88 UT 324180 18 T 0.237 0.154 .166/.108 0.233 >88 UT 324190 19 P 0.237 0.166 0.227 >88 UT 324270 27 E 0.237 0.166 0.207 >88 UT 324280 28 P 0.237 0.166 0.228 >88 UT 27

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. M-103 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 325130 13 T 0.337 0.300 .236/.210 0.257 88-82 UT 325230 23 P 0.237 0.166 0.219 >88 UT 325310 R 0.337 0.432 .236/.302 0.299 >88 UT 31'25320 32 T 0.432 0.302 0.518 >88 UT 325330 33 C 0.432 0.302 0.467 >88 UT 325340 34 P 0.432 0.302 0.433 >88 UT Drawin No. M-104 Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 326060 6 E 0.375 0.263 0.361 >88 UT 326070 7 P 0.375 0.263 0.356 >88 UT 326140 14 T 0.375 0.375 .263/.263 0.521 >88 UT 326150 15 E 0.375 0.263 0.365 >88 UT 326160 16 P 0.375 0.263 0.362 >88 UT 326165 16A E 0.375 0.263 0.353 >88 UT 28

R. ED GINNA NUCLEAR POWER PLANT Inservice Inspection Report, 1990-1999 Interval, Second Period, First Outage (1993)

ATTACHMENT III Com onent Result Details: Cont.

Drawin No. NA Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal T 400094 B P 0.500 0.438 0.501 >88 UT 400095 B C 0.500 0.438 0.505 >88 UT 400096 A P 0.500 0.438 0.441 >88 UT 400097 A C 0.500 0.438 0.505 >88 UT 400098 5A 0.,875 0.613 0.892 >88 UT 400099 5B 0.875 0.613 0.866 >88 UT 29

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