ML051930115

Transmittal of Inservice Inspection Report for the Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI and First Interval (1997-2008), Second Period, Third Outage (2005) - Iwe/Iwl

ML051930115
Person / Time
Site:	Ginna
Issue date:	07/01/2005
From:	Korsnick M Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051930115 (128)

Text

Maria Korsnick Vice President Constellation Energy I

R.E. Ginna Nuclear Power Plant 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick 6constellation.com July 1, 2005 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

SUBJECT:

Document Control Desk R.E. Ginna Nuclear Power Plant Docket No. 50-244 Transmittal of Inservice Inspection Report for the Fourth Interval (2000-2009).

Second Period, Second Outalwe (2005) - IST and First Interval (1997-2008),

Second Period, Third Outaeu (2005) - IX'E/IIWL Enclosed is a copy of the Ginna Station Inservice Inspection Report for the refueling outage conducted in 2005. This report is submitted as specified by Ginna Station Nuclear Directive ND-IIT (Inservice Inspection and Testing) and ASME Code section XI.

There are no new commitments being made in this submittal. Should you have questions regarding the information in this submittal, please contact George Wrobel at (585) 771-3535 or george.w robel(constellation.com.

Ve tly yours, 1 }

Mary G. orsnick Attachments:

(1) Inservice Inspection Report for the Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI and First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL cc:

S. J. Collins, NRC P. D. Milano, NRC Resident Inspector, NRC 100 F3LK,~

'- q-

0

R.E. Ginna Nuclear Power Plant, LLC R.E. Ginna Nuclear Power'Plant Nuclear Regulatory Commission 2005 Outage, Inservice Inspection Program Report

R. E. Ginna Nuclear Power Plant, LLC 1503 Lake Road, Ontario, NY 14519 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE FOURTH INTERVAL (2000-2009), SECOND PERIOD, SECOND OUTAGE (2005) -ISI AND FIRST INTERVAL (1997-2008), SECOND PERIOD, THIRD OUTAGE (2005) -

IWE/IWL AT R. E. GINNA NUCLEAR POWER PLANT Revision 0 June 29, 2005

R. E. GINNA NUCLEAR POWER PLANT NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOURTH INTERVAL (2000-2009), SECOND PERIOD, SECOND OUTAGE (2005) - ISI AND FIRST INTERVAL (1997-2008), SECOND PERIOD, THIRD OUTAGE (2005) -

IWE/IWL OWNERS DATA SHEET Date: 29 June, 2005 Owner:

R. E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519 Plant Location and Unit No.:

Commercial Operating Date:

R. E. Ginna Nuclear Power Plant Unit One 1503 Lake Road Ontario, New York 14519 July 1, 1970 Applicable Code:

ASME Section XI, 1995 Edition, 1996 Addenda (ISI)

ASME Section XI, 1992 Edition, 1992 Addenda (IWE/IWL)

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL TABLE OF CONTENTS Introduction and Synopsis Summary of Work Accomplished Class I Components Class 2 Components Class 3 Components High Energy Components

-Design/Consequential Break Weld Examinations & Component Support Examinations Steam Generator Eddy Current Examinations System Pressure Testing

-Leakage Testing Expanded Examinations Repair and Replacement Program Snubber Program

-Visual Examinations / Functional Testing Seismic Support Program Containment IWE/IWL Program Erosion/Corrosion (Minwall) Program Attachments:

Attachment IA ISI Program Examination Results Attachment IB Containment IWE - IWL Program Examination Results Attachment IC IWE Appendix J Testing Results 1 ASME Section XI - Repair & Replacement Program Report Attachment III Steam Generator Eddy Current Program - Final Report Attachment IV Erosion/Corrosion (Minwall) Program Examination Results i.

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005)- IWEIIWL INTRODUCTION AND SYNOPSIS:

Inservice Inspection (ISI) activities for the 2005 Outage were performed on items within Class 1, 2, 3, MC, CC, High Energy Piping & Components, Seismic Supports and Snubbers. ISI examinations for the outage were concluded on April 11, 2005. Examination methods included Visual and General Visual (VT), Liquid Penetrant (PT), Magnetic Particle (MT), Ultrasonic (UT), Eddy Current (ET) and Radiography (RT). Functional Testing (FT) and System Pressure Tests were also performed as well as Erosion/Corrosion examinations during this time.

Personnel involved in Outage activities included Ginna Station NDE Group, IHI SouthWest Technologies Inc., Westinghouse, Anatec International, Quality Inspection Services Inc.,

Whiting Services Inc. Ginna Station Quality Control, Ginna Station Performance Monitoring and Calvert Cliffs Personnel. Additional Support Personnel utilized included individuals from the following departments: Ginna Station Insulators, Maintenance, Electricians, Pipe Fitters, Radiation Protection, Turbine Maintenance, and Ginna Station System Engineering.

ASME SECTION XI

SUMMARY

OF WORK ACCOMPLISHED:

Upon conclusion of the 2005 Outage, 51.3% of ISI examinations for the Fourth Interval ISI Program have been completed. Also, 61.5% of ISI examinations for the First Interval ISI Containment (IWE/IWL) Program have been completed.

CLASS I COMPONENTS:

A total of 72 components were examined. The examinations for these components consisted of 22 VT's, 47 PT's, I RT and 14 UT's. A total of 84 examinations were performed on Class I Components.

Two Class I components were examined, rejected and required grind repairs to be performed.

These rejects were classified as original fabrication defects. One item was a Pressurizer Nozzle to Safe End Weld, ISI Summary Number 1004350, weld SLNSE which experienced delayed hot cracking and was subsequently repaired by grinding. The other item was a 10" Residual Heat Removal Weld, ISI Summary Number 1029100, weld ASW-I which had 3 porosity indications and was repaired by grinding.

A detailed listing of all Class I ISI Component Examinations is documented within Attachment IA of the 2005 Outage 90 Day Report.

CLASS 2 COMPONENTS:

A total of 63 components were examined. The examinations for these components consisted of 36 VT's, 8 PT's, 4 MT's, 3 RT's, and 5 UT's. A total of 56 examinations were performed on Class 2 Components.

I

R E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEAIWL Four Class 2 components were examined and rejected. The first item was on a 6" Mainsteam line, Pipe to Valve 3504 Weld, ISI Summary Number I 090300, weld L2-BC-1A. This weld had original fabrication slag that was removed and weld repaired. The second item was on an 8" Residual Heat Removal line, Component Support RHU41, Variable Spring, ISI Summary Number 1142210. This Component Support Spring Can Setting was off and needed readjustment and was considered service induced. The third item was on the Residual Heat Removal Heat Exchanger "A", Outlet Reinforcing Plate Weld, ISI Summary Number 1169090, weld ORPRHE-IA. This weld had original fabrication porosity that was removed by grinding.

The fourth item was on the Residual Heat Removal Heat Exchanger "B", Inlet Reinforcing Plate Weld, ISI Summary Number 1169270, weld IRPRHE-1B. This weld had original fabrication porosity that was removed by grinding.

A detailed listing of all Class 2 ISI Component Examinations is documented within Attachment IA of the 2005 Outage 90 Day Report.

CLASS 3 COMPONENTS:

A total of 11 component supports were examined utilizing the VT (visual) examination method.

A detailed listing of all Class 3 ISI Component Examinations is documented within Attachment IA of the 2005 Outage 90 Day Report. These examinations are identified with a 1500,000 series ISI Summary Number.

HIGH ENERGY COMPONENTS:

Fourteen (14) components associated with the High Energy Program were examined during the 2005 Outage. Examinations for these items were performed on welds, component supports and associated integral attachments. A total of 37 examinations were performed. The examinations for these components consisted of 14 VT's, 11 MT's, 1 PT, 7 RT's and 4 UT's.

A detailed listing of all High Energy Component Examinations is documented wvithin Attachment IA of the 2005 Outage 90 Day Report. These examinations are identified with a I200,000 series ISI Summary Number.

STEAM GENERATOR TUBING:

ASME and Owner Elected Examinations were performed on tubes in the "A" and "B" Steam Generators (S/G) during the 2005 Outage.

The following examinations were performed on both "A" and "B" Steam Generators:

50% Full Length Bobbin Coil Examination 20% Row I & 2 tight radius U-bend MRPC 20% TTS H/L transition MRPC Visual Examination of Tube Plugs MRPC of Outer radius Tube to Tube proximity tubes Diagnostic MRPC examinations TTS Fosar & inner bundle visual sampling Upper bundle inspection in "A" S/G only 2

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1 997-2008), Second Period, Third Outage (2005) - IWE/IWL During the 2005 Ginna Refueling outage a foreign object was detected in the "B" S/G cold leg, a small wire was removed from the "A" S/G hot leg, and a possible loose part "PLP" eddy current signal was also detected in the "A" S/G. Each location was reviewed and Westinghouse was requested to perform an analysis of each location.

The "B" S/G had an indication of a possible loose part which was detected with the bobbin coil in the "B" S/G cold leg. The tube locations exhibiting the "PLP" indications were row 50 column 114, and row 48 column 1 14 and were located on the periphery. There was no detectable degradation with either tube or surrounding tubes with the bobbin coil. The axial location of the foreign material was approximately 20.5" above the top of tube sheet (TTS). The "B" SIG was drained for a secondary side visual exam with a remote video probe. The inspection confirmed the presence of a piece of foreign material wedged in between tubes row 50 column 114, and row 48 column 114. The location of the object is within the shroud and tube bundle annulus region, below the first lattice grid, and within the two periphery tubes.

The two tubes mentioned above were examined from the tubesheet to the first lattice grid with MRPC which encompassed the foreign object location axially, as well as a bounding program which encompassed the adjacent tubes. No detectable degradation was found on any tube locations. The 35 kHz pancake and pluspoint coils were also reviewed for foreign material response from all bounding tubes. Only row 50 column 114, and row 48 column 114 exhibited foreign material responses.

These tubes were last inspected during the 1999 RFO with no evidence of foreign material during that inspection.

Repeated attempts were made for retrieval with manual grippers of varying sizes. The attempts were not successful due to the foreign material being firmly fixed within the tube bundle location. The grippers were grappled on the material repeatedly, with no material budging or movement. This provided the feedback that this material was extremely fixed at this location, and normal mechanical means was not going to be successful for foreign object removal.

Based on close visual inspection, the foreign material is estimated to be approximately 1/4" X 1/2" and.030" -.040" thick. The exact dimension cannot be determined, as it is wedged between two tubes and curled over. The material has been fixed for some time based on the amount of localized deposition that has settled on and adjacent to the object. There were also no signs of flow streaming, or tube fretting. There were no visible signs of foreign material corrosion or foreign material degradation. Based on the objects size and location it is unlikely that the material would break up and cause damage to other tube locations.

A conclusive quantitative means of estimating foreign material to tube wear potential could not be estimated. So a conservative approach of installing four (4) 86" length tube stabilizers at the area of interest on the cold leg, and removing all affected tubes from service with mechanical plugs on both the hot leg and cold leg locations was performed. This included the two tubes in contact with the foreign material, and in addition two bounding tubes. The listing of tube locations is as follows:

3

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005)- IWE/IWL Row Column 50 114 48 114 47 115 49 113 During the "A" S/G examination a "PLP" was detected during a TTS inner bundle visual examination. The location row 37 column 67 is approximately 60 rows in from the periphery.

The small wire was removed and physically measured to have dimensions of.75" in length and

.011" in diameter. This area was bounded with a TTS MRPC examination with no degradation.

During the review of this small wire, it was concluded that if similar wires were potentially left in the steam generators, they would not result in significant tube wear. Wires of this size have insufficient mass to cause impact damage and generally break into smaller pieces before they can cause significant wear on a tube. Fluid velocities of this magnitude, in combination with the small flow area of the wire, typically result in long wear times. In addition, tube vibration in this region of the tube bundle is minimal, which will further reduce the wear rate. To develop a more quantitative estimate of potential tube wear, Westinghouse reviewed calculations from other plants and associated wear rates for similar size loose parts from these other plants while making adjustments for higher fluid velocities and a tighter tube bundle pitch in the Ginna specific S/G conditions. It was possible to estimate a potential wear rate, and under the worst-case conditions it was estimated that it would take at least seven years for a 2-inch long wire to wear a tube to the plugging limit of 40% through-wall. Note that the above estimate is conservative in that it assumes the wire will not wear and the tube will. If it is assumed that the wire wears at the same rate of the tube (the more probable scenario), the wire will simply fall apart before it can wear a tube to the plugging limit. Based on this evaluation, it was concluded that wires similar to the one removed from "A" S/G will not cause significant tube wear in the Ginna S/Gs.

Also during the "A" S/G examination a "PLP" was detected with the bobbin coil located at row 94 column 54 and row 93 column 55 at an elevation of 9" above TTS. This location is approximately 8 rows in from the periphery. This area was bounded with a TTS MRPC examination with no degradation. It was concluded that the loose part at 9" above TTS in S/G "A" does not require plugging or stabilizing. This conclusion is based on previous inspections that showed the potential loose part did not cause wear on the affected tubes. Tube row 94 column 54 has been operating for at least 6 years with a PLP identified and no degradation.

Similarly, tube row 93 column 55 has been operating for at least 3 years with a PLP identified and no degradation. These previous inspections had categorized the "PLP" signal as a deposit.

Since there has been no change in the eddy current signal in that time, it is concluded that the PLP is not capable of causing significant tube damage. This process for dispositioning PLPs based on past history has been used at several plants. Since the eddy current signal had not changed and they caused no tube wear, the tubes were left inservice.

Steam Generator Eddy Current Examinations are summarized in Attachment IA. These examination summaries are identified with an 1800,000 series ISI Summary Number. Steam Generator Eddy Current Examination Final Report is contained within Attachment III.

4

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - IS]

First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL SYSTEM PRESSURE TESTS:

Leakage TestinM:

A total of twenty (20) Leakage Examinations were performed. Leakage tests performed included one ( I ) Class 1, Reactor Coolant System (PT-7) examination, eleven ( 11 ) Class 2 system examinations and eight ( 8 ) Class 3 system examinations. A detailed listing of all ISI Class 1, 2 and 3 System Leakage Tests are documented within Attachment IA of the 2005 Outage 90 Day Report. These examinations are identified with an I400,000 series ISI Summary Number.

EXPANDED EXAMINATIONS:

T~wo (2) components were classified as a "Service Induced Rejects". The following list identifies the components that had Code expanded examinations performed.

RHU-1 14 (Guide-loose sway strut nuts)

RHU-41 (Spring Can-setting out of specification)

REPAIR & REPLACEMENT PROGRAM:

A total of 66 ASME Section XI Code Repair and Replacement activities were performed during this cycle as documented within Attachment II of the 2005 Outage 90-Day Report.

SNUBBER PROGRAM:

Visual Examinations:

A total of 22 Snubber component supports were Visually (VT) examined. These Augmented examinations were performed to satisfy Ginna Station Snubber Program commitment.

One, Class Q, Hydraulic Snubber Component Support PS-2, was visually examined and rejected due to low fluid level. The Snubber was Functionally Tested and found operable.

Functional Testing:

A total of 18 snubbers were Functionally Tested (FT) during the 2005 outage. From the eighteen snubbers that were tested, 14 were mechanical snubbers and 4 were hydraulic snubbers.

One Mainsteam Mechanical Snubber, MSU-7 West, was Functionally Tested and Failed. The Snubber was replaced. Due to the failure of Mechanical Snubber MSU-7 West, an expansion was performed. The expansion consisted of two Mechanical Snubbers, MSU-25 and MSU-1 6 South. Both were Functionally Tested and found operable.

5

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL Snubber Functional Tests (FT) were performed on the following:

Mechanical Snubbers:

AFU-52 CVU-351 FWU-54 MSU-7 (Top/West)

MSU-7 (Bottom/East) MSU-16(South)

MSU-25 MSU-27 MSU-38 MSU-74 MSU-82 RHU-36 SIU-52 SWU-309 Hvdraulic Snubbers:

FWU-3 N608 PS-2 SGA-7 A detailed listing of all Snubber Program Examinations is documented within Attachment IA of the 2005 Outage 90 Day Report. These examinations are identified with an 1600,000 series ISI Summary Number.

SEISMIC SUPPORT PROGRAM:

Five (5) Seismic Supports were inspected this outage utilizing the visual (VT) examination technique.

A detailed listing of all Seismic Support Component Examinations are documented within Attachment IA of the 2005 Outage 90 Day Report. These examinations are identified with an 1700,000 series ISI Summary Number.

CONTAINMENT IWE/IWL PROGRAM:

The Containment IWE/IWL Program consist of the metallic liner (IWE) and concrete (IWL) relating to the Containment structure, including tendons (IWL). During the 2005 Outage, a total of 206 items were examined. These items consisted of 9 Appendix J Tests, 18 IWL Concrete examinations, 25 IWE Liner examinations, 160 Tendon Grease Cap examinations and 2 examinations on an area of the metallic liner prior to and after the application of paint/coating.

Other Tendon Examinations for the Second Period Containment Program (IWL) was not performed during the 2005 Outage but shall be completed on or before December 31, 2005. The results of these inspections will be included within the 2006 Outage 90-Day Report.

A detailed listing of all Containment IWE/IWL Program Examinations is documented within Attachment IB and Attachment IC of the 2005 Outage 90 Day Report. These examinations are identified with an I900,000 series ISI Summary Number.

6

R. E. Ginna Nuclear Power Plant Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL EROSION/CORROSION MINWALL PROGRAM:

A total of 390 components were examined and mostly performed online. Of this total, 216 components were examined utilizing the Radiographic method and 174 components utilized the Ultrasonic method. The breakdown of this total by component type is as follows:

Type Large Bore Components Small Bore Components Miscellaneous Components Service Water Components Total Number 162 139 31 58 A detailed listing of all Erosion/Corrosion Minwall Program Examinations is documented within Attachment IV of the 2005 Outage 90 Day Report.

The statements made within this Report and associated Attachments are correct and the examinations as well as corrective measures taken conform to the Rules of the ASME Code,Section XI.

Prepared By:

Reviewed By:

Approved By:

L 6/

X-Frank A. Klepacki Date Paul A. Lewis Date ector, Laboratory Inspection Services RPeter Bamford Date f Interim Director, Reliability Engineering Certificate of Inservice Inspection 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspections and the State or Province of N/A and employed by ABS of Houston TX 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:

'J. Longe~berger-ANII Date 7

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT I NIS-1 Sub-Attachments:

1A ISI Program Examination Results 1B Containment IWE -

IWL Program Examination Results IC IWE Appendix J Testing Results

APPENDIX II-MANDATORY Attachment IA - 21 Pages 1B - 17 Pages Form NIS-1 Page 1 of 2 Attachment I C - 2 Pages FORM%1 NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTION As required by the Provisions of the ASME Code Rules

1. Owner R. E. Ginna Nuclear Power Plant, LLC, 1503 Lake Road. Ontario, NY 14519 (Name and Address of Owner)

2. Plant R. E. Ginna Nuclear Power Plant. 1503 1Lake Road, Ontario. New York 14519 (Name and Address of Plant)

3. Plant 1

4. Owner Certificate of Authorization (if required)

NIA

5. Commercial Service Date 07/01/1970

6. National Board Number for Unit N/A 7.Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance Or Installer Serial No.

Province No.

Board No.

(*)

(*)

(*)

(*)

(*)

(*) See "Attachment lA, 1B & IC" For Applicable Information Note: Supplemental sheets in form of list, sketches, or drawings may be used, provided (I) size is 81/2 in. x I I in., (2) Information in items I 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.

This Form (E00029) may be obtained from the ASME Order Dept, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

1995 with 1996 Addenda SECTION XI - DIVISION 1 1992 with 1992 Addenda SECTION XI - DIVISION I Page 2 of 2 FOR% NIS-1 (Back)

8. Examination Dates 10/1701003 to 4/11/21)00

9. Inspection Period Identification:

Second Period (2005 Outane) / Second Period (2005 Outace)

10. Inspection Interval Identification: Fourth Interval (2000 to 2009)

/ First Interval (1997 to 2008)

11. Applicable Edition of Section XI 1995 Edition 1992 Edition Addenda 1996 (Class 1, 2 & 3 IST)

Addenda 1992 UWEVE & Ml.

12. Date/Revision of Inspection Plan: 2005 Outage Inspection Plan

13. Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See "Attachment IA. I

& 1 C" for Applicahle Information

14. Abstract of Results of Examinations and Tests. See -Attachment IA, I B & IC" for Applicahle Information.

15. Abstract of Corrective Measures. See 'Attachment IA. 1lB & IC" for Applicahle Information.

Wve certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by ASNIE Code.Section XI, and c) corrective measures taken conform to the rules of the ASIME Code,Section XI.

Cerificate ofAuthorization No. (if applicable)

N/A Expiration Date N/A Signed R. F. Ginna Nuclear Power Plant,.I.C. Bv:

Bi.

9.

Date 17.1une 2005 Owner Frank A. Klepacki {- ISI Engineer CERTIFICATE OF INSERVICE INSPECTION

1. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of N/A and employed by ABS of Itouston. TX have inspected the components described in this Owner's Report during the period 10/172(003 to 4/11/2005.

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, Concerning the examinations 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 N1110195 ACr-T Inspect s Signature National Board, State. Province, And Endorsements Date

/7 2005

(.

(

Owner:

Plant:

Plant Unit:

Affachment 1A - ISI Report - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 1

Page of 1 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Catecaory Item Procedure Method/Sheet/Results System ISO #

Class 1 1000701 RPV INTERIOR VESSEL INTERIOR B-N-1 B13.10 VT-110 VT 05GV362 Accept RPV A-1 Comments:

05-VT: Partial Exam-Thermal Couple conduit cut during 03 RFO, Upper internal Pick to Upper cavity stand, verify no Fuel Assemblies attached, Upper Internal Package insp.

on Stand, Upper Fuel Pins & Slip Pins insp. as Upper Internal Package was returned to Vessel. In-Vessel Insp. deferred to 06 RFO-Accept.

1004350 SLN SE NOZZLE-TO-SAFE END (SURGE LINE)

B-F B5.40 PT-1 06 PT 05GP020 Reject PZR A-4 PT-1 06 PT 05GP045 Accept PZR A-4 Comments:

05 - PT: Reject: Existing indications benign/grew or new indications developed. AR # 2005-1405 generated. Repair by blending performed -see RRM Summary # R05037.

Post Repair: PT: Numerous rounded indications left -all code acceptable. Owner Elected Exam.

1004600 RC-2501-ASW-IA NOZZLE-TO-SAFE END (RELIEF LINE)

B-F B5.40 PT-106 PT 05GP014 Accept PZR A-4 Comments:

05 - PT: No Recordable Indications -Accept. Owner Elected Exam.

1004800 RC-1000-MSW-1 SAFE END-TO-NOZZLE (SPRAY LINE)

B-F Comments:

05 - PT:-2 rounded indications 1/16" & 3/16" - Accept. Seen in previous exam. Owner Elected Exam B5.40 PT-106 PT 05GP016 Accept PZR A-4 1005000 RC-273-l NOZZLE-TO-SAFE END (SAFETY #1)

B-F B5.40 PT-1 06 PT 05GPO 1I Accept PZR A-4 Comments:

05 - PT: Linear indications @ 1 718", 2 1/2" & 7 1/4" - No change since previous exam - Accept. Two (2) new indications noted in safe end base material - Acceptable. Owner Elected Exam.

1005200 RC-273-S NOZZLE-TO-SAFE END (SAFETY #2)

B-F B5.40 PT-1 06 PT 05GP015 Accept PZR A-4 Comments:

05 - PT: Rounded indication - 1/8" dia. - No change from previous exam - Accept. Owner Elected Exam.

1007430 IMN-BR INLET MANWAY NUTS (20)

Comments:

05-VT: No Recordable Indications - Acceptable 1007435 IMS-BR INLET MANWAY STUDS (20)

Comments:

05-VT: No Recordable Indications - Acceptable B-G-2 B7.30 VT-108 B-G-2 B7.30 VT-1 08 VT 05GV342 Accept SG VT 05GV343 Accept SG A-5 A-5 1011000 PL-FW-II/1OA-RCO-2501-A 10" BRANCH WELD B-J B9.31 UT-208 UT 05GU031 Accept UT-208 UT 05GUO21 Accept UT-208 UT 05GU020 Accept PT-106 PT 05GP040 Accept Comments:

05 - PT: No Recordable Indications - Accept. UT: Base Metal Lamination - No Recordable Indications - Accept. UT: PDI - No Indications - Accept.

RC A-3-1A RC A-3-1A RC A-3-1A RC A-3-1A 1012100 PL-FW-VI PUMP(RCP-A)-TO-PIPE B-J B9.11 UT-208 UT 05GUi16 Accept RC A-3-1C PT-106 PT 05GP028 Accept RC A-3-1 C Comments:

05-PT: No Recordable Indications - Accept. UT: PDI, Utilized 1995 Lamination Scan & Coverage Plot. Single-sided access, far side of weld not examined, 64% of weld was covered -Accept. No RL wave scan performed-Reschedule 2006.

(

(

(

Affachment AA - ISI Report - 2005 Outage Page of 2 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Reg.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheetlResults System ISO#

1013500 PL-FW-XV ELBOW-TO-PUMP(RCP-B)

B-J B9.11 UT-204 UT 05GUOII Accept RC A-3-2B PT-106 PT 05GP012 Accept RC A-3-2B Comments:

05-PT: No Recordable Indications - Accept. UT: No Recordable Indications - Accept. Utilized 1995 Lamination Scan and Coverage Plot.

1015400 BSW-1 PIPE-TO-ELBOW B-J B9.21 UT-208 UT 05GU025 Accept PZR A-10 UT-208 UT 05GU022 Accept PZR A-10 PT-106 PT 05GP021 Accept PZR A-10 Comments:

05 - PT: No Recordable Indications - Accept. UT: Base Metal Lamination - No Recordable Indications - Accept. UT: PDI - No Indications - Accept. Small Bore Life Extension Program 1019800 A

NOZZLE-TO-PIPE B-J B9.21 PT-106 PT 05GP043 Accept PZR A-10 UT-208 UT 05GU019 Accept PZR A-10 Comments:

05 - PT: NRI - Accept. UT: PDI - No Indications - Accept. Scanned across weld for 100% coverage. Base Metal Lamination/Profile performed in 1985. Small Bore Life Extension Program.

1021100 DSW-3 PIPE-TO-ELBOW B-J B9.21 UT-208 UT 05GU027 Accept PZR A-10 UT-208 UT 05GU028 Accept PZR A-10 Comments:

05-UT: Base Metal Lamination-No Recordable Indications-Accept. UT: PDI - No Indications - Accept. Coverage Plot performed 2005. Small Bore Life Extension Program 1022700 CVU-67 RIGID RESTRAINT F-A F1.10A VT-106 VT 05GV318 Accept CVCS-CHfA-11 Comments:

05-VT: No Recordable Indications - Acceptable. ID tag missing.

1022800 CVU-68 RIGID RESTRAINT F-A F1.10B VT-106 VT 05GV317 Accept CVCS-CHfA-11 Comments:

05-VT: No Recordable Indications - Acceptable 1023300 CVU-70 RIGID RESTRAINT F-A F1.1iOB VT-106 VT 05GV320 Accept CVCS-CHF A-11 Comments:

05-VT: No Recordable Indications - Acceptable 1024000 14 PIPE-TO-COUPLING B-J B9.40 PT-106 PT 05GP026 Accept CVCS-CHfA-11 Comments:

05 - PT: No Recordable Indications - Accept 1025300 21 ELBOW-TO-PIPE B-J B9.40 PT-106 PT 05GP022 Accept CVCS-CHf A-11 Comments:

05 - PT: No Recordable Indications - Accept.

1025400 22 PIPE-TO-VALVE(297)

B-J B9.40 PT-1 06 PT 05GP056 Accept CVCS-CHf A-11 Comments:

05 - PT: Rounded indication - 1/32" - Accept.

1026000 27 PIPE-TO-REDUCER B-J B9.40 PT-106 PT 05GP013 Accept PZR A-1I RT-104 RT 05GRTOOI Accept PZR A-1I Comments:

05 - PT: No Recordable Indications - Accept. RT: Tungsten, IUC - Accept. Exam forThermal Stratification.

(C A - ISI Report - 2005 Outage Page of 3 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Req.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheetlResults System ISO#

1026600 C

REDUCER-TO-VALVE(515)

B-J B9.21 PT-106 PT 05GP036 Accept PZR A-12 Comments:

05 - PT: No Recordable Indications - Accept 1028200 Q

REDUCER-TO-ELBOW B-J B9.11 PT-106 PT 05GPOIO Accept PZR A-13 UT-208 UT 05GU007 Accept PZR A-1 3 Comments:

05 - PT: No Recordable Indications - Accept. UT: PDI - No Indications - Accept. Base Metal Lamination performed in 1995.

1029100 ASW-1 PIPE-TO-ELBOW B-J B9.11 PT-106 PT 05GP033 Reject RHR A-14 PT-106 PT 05GP038 Accept RHR A-14 UT-208 UT 05GU013 Accept RHR A-14 Comments:

05-PT: Rej-3 Rounded Indications-not service induced-AR# 2005-1451 generated. Metal removal repair-1995 lam scan used for UT thickness. Post repair UT thickness &

PT-see Sum # R05040. PT: No Recordable Indications-Accept. UT: PDI - No Indications - Accept. Used 1995 lam scan with new Coverage Plot 1033800 FSW-1 PIPE-TO-ELBOW B-J B9.11 PT-106 PT 05GP049 Accept HPSI A-16 UT-208 UT 05GU023 Accept HPSI A-16 Comments:

05 - PT: No Recordable Indications - Accept. UT: PDI - No Indication -Accept. UT: Base Metal Lamination performed in 1987.

1034300 H

PIPE-TO-VALVE(867A)

B-J B9.11 UT-208 UT 05GU026 Accept HPSI A-16 Comments:

05-UT: PDI, Utilized 1993 Lamination Scan & Coverage Plot. 50% coverage obtained due single-sided access. Shear wave scanning performed on near-side of weld - No Indications -Accept. RL wave scan performed incorrectly - Reschedule 2006.

1038100 F

ELBOW-TO-PIPE B-J B9.11 PT-106 PT 05GP009 Accept RC A-14 UT-208 UT 05GUO06 Accept RC A-14 UT-208 UT 05GU033 Accept RC A-14 Comments:

05-PT: No Recordable Indications - Accept. UT: Base Metal Lamination-No Recordable Indications-Accept. UT: PDI - No Indications -Accept. Utilized coverage plot performed in 1994.

1038700 FSW-19 TEE-TO-REDUCER B-J B9.40 PT-1 06 PT 05GP050 Accept HPSI A-19 Comments:

05 - PT: No Recordable Indications - Accept.

1041700 GSW-15 ELBOW-TO-PIPE B-J B9.40 PT-106 PT 05GP025 Accept HPSI A-21 Comments:

05 - PT: No Recordable Indications - Accept.

1042200 GSW-20 2" PIPE-TO-BRANCH CONNECTION B-J B9.40 PT-1 06 PT 05GP048 Accept RC A-21 Comments:

05 - PT: No Recordable Indications - Accept 1044900 20 PIPE-TO-ELBOW B-J B9.40 PT-106 PT 05GP041 Accept CVCS-LTCA-23 Comments:

05 - PT: No Recordable Indications - Accept.

1045425 CVU-33 GUIDE F-A F1.10B VT-106 VT 05GV245 Accept CVCS-LTCA-23 Comments:

05-VT: No Recordable Indications - Accept.

(

(

Owner:

Plant:

Plant Unit:

Attachment AA - ISI Report - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 1

Page of 4 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comr ID Comn Desc.

Cateaorv Item Procedure MethodlSheet/Results System ISO #

1046800 Comments:

1046820 Comments:

1048202 Comments:

1049750 Comments:

1049765 Comments:

1050730 Comments:

1050740 Comments:

1050745 Comments:

1050750 Comments:

1050800 Comments:

1050885 Comments:

1050888 Comments:

1051400 Comments:

CVU-29 (IA)

INTEGRAL ATTACHMENT B-K 05-PT: No Recordable Indications - Acceptable CVU-29 RIGID RESTRAINT (IA)

F-A 05-VT: No Recordable Indications - Acceptable 2

PIPE-TO-TEE B-J 05 - PT: No Recordable Indications - Accept 20 ELBOW-TO-PIPE B-J 05 - PT: No Recordable Indications - Accept 19 PIPE-TO-ELBOW B-J 05 - PT: No Recordable Indications - Accept. Limitation - pipe support - > 90%.

21 B VALVE(9314)-TO-PIPE B-J 05 - PT: No Recordable Indications - Accept.

CVU-6 VARIABLE SPRING F-A 05-VT: Required cold setting per ME 303 Rev 5 is 85# - Actual 80#. No Recordable Indications -

21 C TEE-TO-REDUCER B-J 05 - PT: No Recordable Indications - Accept.

22 PIPE-TO-VALVE(295)

B-J 05 - PT: No Recordable Indications - Accept.

23 VALVE(295)-TO-PIPE B-J 05 - PT: No Recordable Indications - Accept 23A PIPE-TO-COUPLING B-J 05-PT: No Recordable Indications - Accept 23B COUPLING-TO-PIPE B-J 05 - PT: No Recordable Indications - Accept.

20 VALVE(392B)-TO-PIPE B-J 05 - PT: No Recordable Indications - Accept. Limitations - Due to support, >90% obtained.

B10.20 F1.10B B9.40 B9.40 B9.40 B9.40 F1.10C Acceptable.

B9.40 B9.40 B9.40 B9.40 B9.40 B9.40 PT-1 06 VT-106 PT-1 06 PT-106 PT-106 PT-1 06 VT-1 06 PT-1 06 PT-106 PT-106 PT-106 PT-106 PT-106 PT 05GP044 Accept VT 05GV313 PT 05GP042 PT 05GP023 PT 05GP024 PT 05GP054 VT 05GV308 PT 05GP052 PT 05GP057 PT 05GP027 PT 05GP003 PT 05GP058 PT 05GP047 Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept CVCS-LTC A-23 CVCS-LTC A-23 CVCS-LTC A-24 CVCS-CHf A-31 CVCS-CHF A-31 CVCS-CHF A-25 CVCS-CHf A-25 CVCS-CHF A-25 CVCS-CHF A-25 RC A-25 RC A-25 RC A-25 CVCS-CHF A-26

(

(

Page of 5 - 21 A - ISI Report - 2005 Outage Owner:

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

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Reg.):

Commercial Service Date:

N/A 7/1/1970 Plant Unit:

I National Board N Category Item Procedu Summary # Comp ID Comp Desc.

1052500 Comments:

1052700 Comments:

1053300 Comments:

1054930 Comments:

1054960 Comments:

1054980 Comments:

1054990 Comments:

1055100 Comments:

1055300 Comments:

1057100 Comments:

1057150 Comments:

1057310 Comments:

30 ELBOW-TO-PIPE B-J B9.40 05 - PT: No Recordable Indications - Accept.

32 PIPE-TO-COUPLING B-J B9.40 05-PT: No Recordable Indications - Acceptable 38 VALVE(383A)-TO-PIPE B-J B9.40 05 - High Radiation - Contact ALARA. Exam forThermal Stratification. Cal Block used 2-SOCKET-71A REG. PT obtained.

9B VALVE(931 5)-TO-TEE B-J B9.40 05 - PT: No Recordable Indications - Accept.

9D TEE-TO-REDUCING INSERT B-J B9.40 05 - PT: No Recordable Indications - Accept 9E TEE-TO-PIPE B-J B9.40 05 - PT: No Recordable Indications - Accept 9F PIPE-TO-TEE B-J B9.40 05 - PT: No Recordable Indications - Accept.

11 VALVE(393)-TO-PIPE B-J B9.40 05 - Exam forThermal Stratification, Cal Block used 2-SOCKET-71A REG. PT & UT: No Recordable Indications 12 PIPE-TO-NOZZLE B-J B9.40 05 - PT: No Recordable Indications - Accept.

EBA-1 EYEBAR F-A F1.40 05-VT: No Recordable Indications - Acceptable.

EBA-2 EYEBAR F-A F1.40 05-VT: No Recordable Indications - Acceptable.

LEG E SUPPORT COMPONENTS F-A F1.40 05-VT: No Recordable Indications - Acceptable PT-1 06 PT-1 06 UT-202 PT-1 06

& UT: No PT-106 PT-1 06 PT-1 06 PT-106 PT-1 06 UT-202

- Accept.

PT-1 06 VT-1 06 VT-106 VT-1 06 umber for Unit:

N/A re Method/Sheet/Results System ISO #

PT 05GP046 Accept CVCS-CHF A-26 PT 05GP035 Accept CVCS-CHF A-26 UT 05GU018 Accept RC A-26 PT 05GP037 Accept RC A-26 Recordable Indications -Accept. >90% coverage PT 05GP032 Accept CVCS-CHF A-27 PT 05GPO31 Accept CVCS-CHF A-27 PT 05GP030 Accept CVCS-CHF A-27 PT 05GP055 Accept CVCS-CHF A-27 PT 05GP029 Accept RC A-27 UT 05GU024 Accept RC A-27

>90% coverage obtained.

PT 05GP039 Accept RC A-27 VT 05GV360 Accept RC A-7 VT 05GV361 Accept RC A-7 VT 05GV364 Accept RC A-6

=

(.

(

Page of 6 - 21 A - ISI Reiort - 2005 Outage Owner:

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

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

1 Owner Certificate of Authorization (If Req.):

Commercial Service Date:

National Board Number for Unit:

N/A 7/1/1970 N/A Summar 1057320 Commen ty#

its:

Comp ID Comp Desc.

LEG F SUPPORT COMPONENTS 05-VT: No Recordable Indications - Acceptable Category Item F-A F1.40 Procedure MethodlSheetlResults VT-106 VT 05GV365 Accept

= System ISO #

RC A-6

=

1057330 LEG G SUPPORT COMPONENTS Comments:

05-VT: No Recordable Indications - Acceptable F-A F1.40 VT-106 VT 05GV366 Accept RC A-6 1057410 RCP-B WELD A PUMP CASING WELD B-L-1 B12.10 VT-103 VT 05GV283 Accept Comments:

05-VT: Insignificant indications - pits from casting intermittent 360 degress around - grinding marks - no change from previous inspection - Acceptable 1057420 RCP-B WELD B PUMP CASING WELD B-L-1 B12.10 VT-103 VT 05GV284 Accept Comments:

05-VT: Insignificant indications - pits from casting intermittent 360 degress around - grinding marks - no change from previous inspection - Acceptable RC A-7 RC A-7 1057430 RCP-B WELD C PUMP CASING WELD B-L-1 B12.10 VT-103 VT 05GV285 Accept RC A-7 Comments:

'05-VT: Insignificant indications - pits from casting intermittent 360 degress around - grinding marks - gouge 1/2" x 1/32" deep x 1/16" wide @ 11 1/2" - no change from previous inspection - Acceptable 1057910 RCP-B SUPPORT #1 (IA)

INTEGRAL ATTACHMENT B-K B10.30 PT-106 PT 05GP019 Accept RC A-7 Comments:

05 - PT: indications similar to those seen in previous exams were observed. Limitation from 41" to 53" due to component configuration - Accept. Owner Elected Exam.

1057920 RCP-B SUPPORT #2 (IA)

INTEGRAL ATTACHMENT B-K 810.30 PT-106 PT 05GP018 Accept RC A-7 Comments:

05 - PT: Indications similar to those seen in previous exams were observed. Limitation from 41" to 53" due to component configuration - Accept. Owner Elected Exam.

1057930 RCP-B SUPPORT #3 (IA)

INTEGRAL ATTACHMENT B-K 810.30 PT-106 PT 05GP017 Accept RC A-7 Comments:

05 - PT: Indications similar to those seen in previous exams were observed. Limitation from 41" to 53" due to component configuration - Accept. Owner Elected Exam.

1058000 EBB-1 EYEBAR Comments:

05-VT: No Recordable Indications - Acceptable.

F-A F1.40 VT-106 F1.40 VT-106 VT 05GV311 Accept RC VT 05GV312 Accept RC A-7 A-7 1058050 EBB-2 EYEBAR Comments:

05-VT: No Recordable Indications - Acceptable.

F-A 1058130 LEG L SUPPORT COMPONENTS F-A F1.40 VT-106 VT 05GV277 Accept RC VT-106 VT 05GV386 Accept RC Comments:

05-VT: Corrosion noted on Hex Nuts and Inner Radius of Casting, No cross sectional loss or wastage. New Gussets. No Recordable Indications - Acceptable 1058140 LEG M SUPPORT COMPONENTS F-A F1.40 VT-106 VT 05GV385 Accept RC VT-106 VT 05GV278 Accept RC Comments:

05-VT: Corrosion noted on Hex Nuts and Inner Radius of Casting, No cross sectional loss or wastage. New Gussets, No Recordable Indications - Acceptable A-6 A-6 A-6 A-6

Affachment 1A - ISI Report - 2005 Outage Page of 7 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Reg.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetlResults System ISO #

1058150 LEG N SUPPORT COMPONENTS F-A F1.40 VT-106 VT 05GV279 Accept RC A-6 VT-1 06 VT 05GV387 Accept RC A-6 Comments:

05-VT: Corrosion noted on Hex Nuts and Inner Radius of Casting, No cross sectional loss or wastage. New Gussets, No Recordable Indications -Acceptable.

1411000 PT-7 LEAKAGE TEST OF REACTOR COOLANT SYSTEM B-P B15.XX VT-109 VT 05GV420 Accept RC L-1 Comments:

05-VT-2: Performed on Class I piping & components during PT-7. Generated AR #2005-1820 for Valve packing leak & AR# 2005-1819 for Swageloc fitting above Valve 11588. Also utilized Mainentance list for Valves requiring 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time per Code Case 416-2. - Acceptable 1600080 SGA-7 HYDRAULIC SNUBBER SN-VT VT VT-107 VT 05GV286 Accept SG A-7F VT-1 06 VT 05GV341 Accept SG A-7F Comments:

05-VT: Pre-Functional - Snubber SIN AH5, Required cold setting 38 1/8", actual 38", no ID tag, remote dual resevoir was 90% full - Accept. VT: Post-Functional - Snubber SIN AH16, Required cold setting 38 1/8", actual 38 1/8" - No Recordable Indications - Accept.

1600081 SGA-7 HYDRAULIC SNUBBER SN-FT FT FT VT 05GV454 Accept SG A-7F Comments:

05-FT: Functionally Tested Snubber-S/N AH-5 Results are Sat. Re-installed Snubber-SIN AH-16.

1601870 SIU-52 MECHANICAL SNUBBER SN-VT VT VT-1 07 VT 05GV304 Accept RHR A-14 VT-106 VT 05GV375 Accept RHR A-14 Comments:

05-VT: Pre-functional, Snubber S/N 15348, Required cold setting per IP IIT 5 rev. 4 is 2 1/2", Actual is 2 1/2"- Accept. Post-Functional, Snubber SIN 15348, Required cold setting per IP IIT 5 rev. 4 is 2 1/2", Actual is 2 5/8" - No Recordable Indications -Acceptable.

1601871 SIU-52 MECHANICAL SNUBBER SN-FT FT FT VT 05GV446 Accept RHR A-14 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-SIN 15348.

1802730 DIAGNOSTIC EXAM SAMPLING HS AREAS - SIG A B-Q B16.20 ET-109 ET 05ETOOS Accept SG Comments:

05-ET: Approx. 20% open tubes examined fm hot leg tubesheet +/-3" fm secondary face. Approx. 20% row 1 &2 u-bends examined. Approx 20% hot leg dents/dings >2.0 volts examined. Approx 20% manufactured buff marks MBM >5.0 volts on hot leg examined. Also, additional bobbin coil indications examined -Accept 1802800 OPEN GENERATOR TUBES BOBBIN COIL -50% FL - SIG A B-Q B16.20 ET-109 ET 05ET004 Accept SG Comments:

05-ET: S/G-"A". Approx 50% of all open tubes examined from tube end to tube end. Also, all peripheral tubes inspected - Accept.

1802850 TUBE-TUBE PROXIMITY OUTER RAD. U-BEND - SIG A B-Q B16.20 ET-109 ET 05ET006 Accept SG Comments:

05-ET: SIG-'A". 13 known outer peripheral tubes with detectable out of design tolerance for tube to tube proximity were examined - Accept. Evaluated every 18 months.

1802900 EXISTING PLUGS EXISTING PLUGS - SIG A SG-VT VT VT-1 03 VT 05GV451 Accept SG Comments:

05-VT: SIG - "A", row 52, tube 14, inlet & outlet tube ends was inspected. No Recordable Indications - Acceptable.

1803730 DIAGNOSTIC EXAM SAMPLING HS AREAS - S/G B B-Q B16.20 ET-109 ET 05ET002 Accept SG Comments:

05-ET: Approx. 20% open tubes examined fm hot leg tubesheet +/-3" fm secondary face. Approx. 20% row 1&2 u-bends examined. Approx 20% hot leg dents/dings >2.0 volts examined. Approx 20% manufactured buff marks MBM >5.0 volts on hot leg examined. Also, additional bobbin coil indications examined -Accept 1803800 OPEN GENERATOR TUBES BOBBIN COIL - 50% FL - SIG B B-Q B16.20 ET-109 ET 05ETOOI Accept SG Comments:

05-ET: S/G-"B". Approx 50% of all open tubes examined from tube end to tube end. Also, all peripheral tubes inspected - Accept.

(

(

(: A - ISI Report - 2005 Outage Page of 8 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Reg.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheet/Results System ISO #

1803850 TUBE-TUBE PROXIMITY OUTER RAD. U-BEND - S/G B B-Q B16.20 ET-109 ET 05ET003 Accept SG Comments:

05-ET: S/G-'B". 12 known outer peripheral tubes with detectable out of design tolerance for tube to tube proximity were examined - Accept. Evaluated every 18 months.

1803900 EXISTING PLUGS EXISTING PLUGS - S/G B SG-VT VT VT-1 03 VT 05GV450 Accept SG Comments:

05-VT: SIG - "B", row 67, tube 17, inlet & outlet tube ends was inspected. No Recordable Indications - Acceptable.

Class 2 1022200 CVU-63 GUIDE F1.20B VT-106 VT 05GV379 Accept CVCS-CHEA-11 Comments:

05-VT: No Recordable Indications -Acceptable 1050966 CVU-59 RIGID RESTRAINT F1.20A VT-106 VT 05GV391 Accept CVCS-CHIA-29 Comments:

05-VT: Trace of dry boric acid was noted on baseplate & floor - Acceptable 1077400 CVU410 RIGID RESTRAINT (IA)

F-A F1.20A VT-106 VT 05GV232 Accept CVCS-CHF B-6 Comments:

05-VT: Component is different from drawing. Item 1 is 4" Sch 40 pipe X 3 1/2" Ig, Item 3 is 2-3/8" jam nuts, Item 4 is 2-3/8" washers, Item 6 is 10" X 6" X 7/16" stainless plate, Item 8 is 9 1/2" X 5 1/2" X 7/16" plate, Item 11 is 2 spacer nuts. DCR generated to reflect as built -Acceptable 1077500 CVU-411 RIGID RESTRAINT (IA)

F-A F1.20B VT-106 VT 05GV233 Accept CVCS-CHFB-6 Comments:

05-VT: Component is different from drawing. Item 3 is 2, 1/2" jam nuts. Item 7 is 11 " X 5" X 7/16" stainless plate. Item 9 is 10" X 4" X 7/16" plate. Item 1 is 4" sch 40 pipe X 3" Ig. Iten 4 is 2, 1/2" std washer. Item 12 is 2 spacer nuts. Item 13 is 4" sch 40 pipe X 1 1/2" Ig. DCR generated to reflect as built -Accept.

1077600 CVU-412 RIGID RESTRAINT (IA)

F-A F1.20A VT-106 VT 05GV234 Accept CVCS-CHF B-6 Comments:

05-VT-3: Support Items not conforming to drawing. Support Abandomed in place per EWR-2512, remove from ISI Program.

1077700 CVU-413 RIGID RESTRAINT (IA)

F-A F1.20B VT-106 VT 05GV235 Accept CVCS-CHf B-6 Comments:

05-VT: Component is different from drawing. Item I is 4" sch 40 pipe X 3 1/2". Item 12 is 4" sch 40 pipe X 1 1/2" Ig. Item 4 is 2, 1/2" std washer. Item 3 is 2, 1/2" jam nut. Item 7 is 11" X 5" X 7/16" stainless plate. Item 9 is 10" X 4" X 7/16" plate. Item 13 is 2, spacer nuts. DCR generated to reflect as built -Acceptable 1077800 CVU-414 RIGID RESTRAINT (IA)

F-A F1.20A VT-106 VT 05GV236 Accept CVCS-CHF B-6 Comments:

05-VT-3: Support Items not conforming to drawing. Support Abandomed in place per EWR-2512, remove from ISI Program.

1077900 CVU-415 RIGID RESTRAINT (IA)

F-A F1.20A VT-106 VT 05GV237 Accept CVCS-CHI B-6 Comments:

05-VT: Component different from drawing. Item 1 -4" sch 40 pipe is 4 1/4" long. Item 3 is 2-3/8" std nut. Item 8 is 9 1/2" X 5 1/2" X 7/16" plate. Item 10 is 1 spacer nut. Item 6 is 10" X 6" X 7/16" plate. DCR generated to reflect as built - Accept.

1078950 RHR PUMP A SUPPORT #3 SPLIT LINE SUPPORT(#3)

F-A F1.40 VT-106 VT 05GV241 Accept RHR B-28 Comments:

05-VT: Boric Acid noted on Support Base - addresssed by Boric Acid Program via AR 2005-0587 & Sum N05380, also light rust noted on bolts. After BA removal - entire support Base was found Acceptable 1083850 G2-BC-2-B FLANGE(3507)-TO-PIPE C-F-2 C5.51 MT-105 MT 05GM007 Accept MS B-9A RT-104 RT 05GRT004 Accept MS B-9A Comments:

05 - MT: No Recordable Indications -Accept. RT: Insignificant - Porosity - Accept.

I C A - ISI Report - 2005 Outage Owner:

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

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

1 Page of 9 - 21 Owner Certificate of Authorization (If Req.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary#

Comp ID Comp Desc.

Category Item Procedure Method/SheetiResults System ISO #

1087400 MSU-21 GUIDE F-A F1.20A VT-106 VT 05GV230 Accept MS B-1OA Comments:

05-VT: Coating burned off at contact with Pipe, Bird Feces, No change since last inspection - Ref. AR#2000-1545 - Acceptable.

1087500 MSU-23 VARIABLE SPRING F-A F1.20C VT-106 Comments:

05-VT: No Recordable Indications - Required Spring Can setting per ME-303 is 9879#, Actual is 9871# - Acceptable.

VT 05GV231 Accept MS B-1 OA 1090300 L2-BC-1-A PIPE-TO-VALVE(3504)

C-F-2 C5.51 RT-104 RT 05GRT011 Accept MS MT-1 05 MT 05GM024 Accept MS RT-104 RT 05GRT002 Reject MS MT-105 MT 05GM010 Accept MS Comments:

05-MT: No Recordable Indications - Accept. RT: Rej: Indications were noted on previous exams but not to the extent of being rejectable - Origional Fabrication -

service induced. AR# 2005-1430 generated. Repair performed. MT: No Recordable Indications - Accept. RT: Porosity and slag noted - Accept.

1090820 MSU-55 MECHANICAL SNUBBER F-A F1.20C VT-106 VT 05GV363 Accept MS Comments:

05-VT-3: Snubber S/N 18195, required setting perIP IIT5rev4 is 3 3/16" Actual is 2 13/16"- No Recordable Indications-Acceptable B-10 B-10 B-1 0 B-10 Slag - not B-10 1091250 FWU-14 RIGID RESTRAINT Comments:

05-VT: No Recordable Indications - Acceptable.

F-A F1.20A VT-106 VT 05GV390 Accept FW B-1I 1093700 DD5 PIPE-TO-ELBOW C-F-2 C5.51 MT-105 MT 05GM012 Accept UT-209 UT 05GU030 Accept UT-209 UT 05GU029 Accept Comments:

05-MT: No Recordable lndications - Accept. UT: Base Metal Lamination - No Recordable Indications - Accept. UT: PDI - No Indications - Accept.

FW FW FW B-12 B-1 2 B-1 2 B-14 1094575 FWU-41 VARIABLE SPRING F-A F1.20C VT-106 VT 05GV399 Accept FW Comments:

05-VT: Required Cold Setting per ME 303 Rev 5 is 5339#, Actual 5778# - Acceptable. Indications noted on lower Hanger Rod - 1/64" to 1/32" deep X 360 degrees.

Acceptable per Engineering.

1094800 N1 ELBOW-TO-PIPE C-F-2 C5.51 PT-106 PT 05GP060 Accept FW B-14 MT-105 MT 05GM005 Accept FW B-14 RT-104 RT 05GRT012 Accept FW B-14 Comments:

05 - MT: No Recordable Indications - Limited exam due to support - 87% - Accept. PT: No Recordable Indications - exam of weld face in area MT could not be performed -

12% - Accept. RT: No Recordable Indications - Film trimmed to fit between support - Accept.

1099900 BB-R ELBOW-TO-SAFE END (S/G-B)

C-F-2 C5.51 PT-106 PT 05GP051 Accept FW B-13 Comments:

05-PT: No Recordable Indications - Accept. UT: PDI - Deferred to RFO 06 Outage - Need specific Squint Angle and Focal Depth for transducers.

1108100 21R (WELD 35)

ELBOW-TO-TEE C-F-1 THIN PT-106 PT 05GPOOI Accept UT-208 UT 05GUO01 Accept UT-102 UT 05GU032 Info Comments:

05 - PT: No Recordable Indications -Accept. UT: PDI Exam - No Recordable Indications - Accept. Base Metal Lamination/Profile performed in 2005.

HPSI HPSI HPSI B-16A B-16A B-16A

(

(

Owner:

Plant:

Plant Unit: A - ISI Report - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 1

Page of 10 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary #

1110650 Comments:

Comp ID Comp Desc.

RHU-9 RIGID SUPPORT (IA) 05-VT: No changes from last inspection - Acceptable Category Item Procedure Method/SheetlResults VT-106 VT 05GV350 Accept

= System RHR

=

lSO #

B-17

=

F-A F1.20A 1110655 RHU-9 (IA)

INTEGRAL ATTACHMENT Comments:

05-PT: No changes from previous inspection - Acceptable C-C C3.20 PT-106 PT 05GP053 Accept RHR B-1 7 1124200 RHU-102 RIGID SUPPORT (IA)

F-A F1.20A VT-106 Comments:

05-VT: Over sized Support Base Plate noted and conforms to ME-121 & CE-1 53 requirements - Acceptable.

VT 05GV225 Accept HPSI B-19 1130050 RHU-93 VARIABLE SPRING (IA)

F1.20C VT-106 VT 05GV244 Accept RHR B-21 VT-106 VT 05GV238 Accept RHR B-21 Comments:

05-VT: Required setting per ME 303 is 1903#, Actual setting is 1935#, Light corrosion noted on inside of can - (Ref. N05074 & N05118) - Acceptable.

1130150 RHU-92 MECHANICAL SNUBBER F1.20C VT-106 VT 05GV215 Accept RHR B-21 VT-1 06 VT 05GV214 Accept RHR B-21 Comments:

05-VT: BAMP inspection (Sum# N05392) noted Snubber SIN 22190 having Boron on it. AR# 2005-0589 generated for Functional testing. Snubber operable, Old Snubber replaced under WO 20501165 with SIN 18750 due to light corrosion on housing. Required setting per IP IIT 5 rev 4 is 2", Actual is 2 1/4". NRI - Accept.

1130450 RHU-79 RIGID RESTRAINT F-A F1.20A VT-106 VT 05GV392 Accept RHR B-20 Comments:

05-VT: No Recordable Indications - Acceptable 1131710 RHU-75 MECHANICAL SNUBBER F-A F1.20C VT-106 VT 05GV206 Accept RHR B-20 Comments:

05-VT: Required Cold setting per IP lIT 5 is 3", Actual setting 3 1/2", Serial # 8632, Light rust noted on Base Plate, shim under new Base Plate - Acceptable. Ref. WO #

20300818 for base plate modification.

1137800 RHU-68 VARIABLE SPRING (IA)

F-A F1.20C VT-106 VT 05GV389 Accept RHR B-20A VT-106 VT 05GV349 Accept RHR B-20A Comments:

05-VT: Required Setting per ME 303 Rev 5 cold is 474#, Actual 474#, Spring Can replaced and support modified, Base Plate and welds were not coated, No grout at time of inspection, see Engineering acceptance Memo and AR 2005-1537 - Acceptable.

1139850 RHU-37 GUIDE (IA)

F-A F1.20A VT-106 VT 05GV227 Accept RHR B-23 VT-106 Comments:

05-VT: Two (2) shims added to reduce gap to 1/8", Ref AR# 2005-0592 and Sum # R05006 - Acceptable VT 05GV228 Accept RHR B-23 1140000 RHU-38 RIGID HANGER Comments:

05-VT: No Recordable Indications - Acceptable. Expansion for RHU-41 Reject.

F-A F1.20A VT-106 VT 05GV247 Accept RHR B-23 1141400 RHU-47 VARIABLE SPRING F-A F1.20C VT-106 VT 05GV250 Accept RHR Comments:

05-VT: No Recordable Indications - Required setting per ME 303, 1301#, Actual setting is 1300# - Acceptable. Expansion for RHU-41 Reject.

B-25

(

(

Owner:

Plant:

Plant Unit:

Affachment 1A - ISI Report - 2005 Outagie R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 1

I Page of 11 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheetlResults System ISO #

1142210 RHU-41 VARIABLE SPRING F-A F1.20C VT-106 VT 05GV452 Accept RHR B-23 VT-106 VT 05GV240 Reject RHR B-23 Comments:

05-VT: Wrench marks were noted on hanger rod. Required setting per ME 303 rev 5 is 689# +/- 10%, actual setting was 1000# - Reject. AR 2005-0765 generated for setting.

Spring can was re-adjusted to a setting of 700# & wrench marks filed. Re-inspected and found to be Acceptable.

1142600 RHU-42 GUIDE F-A Fl.20A VT-106 VT 05GV248 Accept RHR B-23 Comments:

05-VT: No Recordable Indications - Acceptable. Expansion for RHU-41 Reject.

1143500 RHU-44 VARIABLE SPRING F-A Fi.20C VT-106 VT 05GV249 Accept Comments:

05-VT: No Recordable Indications - Required setting per ME 303 1416#, Actual setting is 1310# - Acceptable. Expansion for RHU-41 Reject.

RHR B-24 1160664 RHU-113 RIGIDSUPPORT(IA)

Comments:

05-VT: No Recordable Indications - Acceptable. Expansion for RHU-1 14 Reject.

F-A FI.20A VT-106 VT 05GV028 Accept HPSI B-16B 1160715 RHU-114 GUIDE F1.20B VT-106 VT 05GV025 Accept RHR B-16B Comments:

05-VT: No ID tag, AR 2004-1290 generated & WO 20402493 written to tighten item #6, loose part was observed during an inspector plant walk through - No Recordable Indications - Acceptable. Expansion performed.

1160720 RHU-115 RIGID RESTRAINT F1.20A VT-106 VT 05GV037 Accept RHR B-16B Comments:

05-VT: North Support Rod in contact with St Pump Air Duct Vent, Gap North side.035", Gap South side 3/16"- drawing indicates 1/16" - Component Support is Acceptable per Engineering - Support Acceptable. Expansion for RHU-I 14 Reject.

1160740 RHU-117 GUIDE F-A F1.20A VT-106 VT 05GV026 Accept HPSI B-16B Comments:

05-VT: No Recordable Indications - Acceptable. Expansion for RHU-1 14 Reject.

1160750 RHU-118 VARIABLE SPRING F-A FI.20C VT-106 Comments:

05-VT: Required setting per ME 303 is 173#, Actual setting is 169#. No Recordable Indications - Acceptable VT 05GV027 Accept HPSI B-16B 1161270 SIU-75 RIGID RESTRAINT Comments:

05-VT: No Recordable Indications - Acceptable F-A F1.20A VT-106 VT 05GV218 Accept HPSI B-37 1163890 28 PIPE-TO-ELBOW C-F-1 Comments:

05-PT: 1/16" dia. rounded indication - Accept. UT: PDI exam - No Recordable Indications - Accept.

C5.21 UT-208 PT-1 06 UT-1 02 FI.20A VT-106 UT 05GU002 Accept HPSI PT 05GP002 Accept HPSI UT 05GU003 Info HPSI VT 05GV351 Accept HPSI B-42 B-42 B-42 B-43 F-A 1164050 SIU-21 RIGID HANGER Comments:

05-VT: No Recordable Indications - Acceptable

(

( A - ISI Report - 2005 Outage Owner:

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

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

1 (I

Page of 12 - 21 Owner Certificate of Authorization (If Req.):

NIA Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetlResults System ISO #

1164180 47 ELBOW-TO-PIPE C-F-1 C5.21 PT-1 06 PT 05GP008 Accept HPSI B-43 UT-208 UT 05GU005 Accept HPSI B-43 Comments:

05-PT: No Recordable Indications - Accept. UT: PDI - No Indications - Accept. Base Metal Lamination scan and coverage plot was performed in 1995 and utilized for this exam.

1169041 INSRHE-1A INLET NOZZLE-TO-SHELL WELD C-B C2.33 VT-109 VT 05GV407 Accept RHR B-109 Comments:

05-VT-2: No Recordable Indications - Acceptable 1169051 ONSRHE-1A OUTLET NOZZLE-TO-SHELL WELD Comments:

05-VT-2: No Recordable Indications - Acceptable C-B C2.33 VT-109 VT 05GV408 Accept RHR B-1 09 1169090 ORPRHE-1A OUTLET REINFORCING PLATE WLD C-B C2.31 PT-1 06 PT 05GP006 Accept RHR B-109 PT-106 PT 05GP005 Reject RHR B-109 Comments:

05-PT: Construction indications identified and rejected. AR 2005-1040 generated & Code Repair by grinding performed under WO 20400669. Re-exam after repair -

Acceptable.

1169220 LHLSWRHE-1B LOWER HEAD-TO-LOWER SHELL CIRC WELD C-A C1.20 UT-303 UT 05GUO04 Accept RHR B-109 Comments:

05-UT: Identical geometric indications as noted in last exam - No change since last exam - Accept. 1994 Lamination Scan & Coverage Plot utilized.

1169270 IRPRHE-1B INLET REINFORCING PLATE WELD C-B C2.31 PT-106 PT 05GP007 Accept RHR PT-106 PT 05GPOO4 Reject RHR Comments:

05-PT: Construction indications identified and rejected. AR 2005-1039 generated & Code Repair by grinding performed under WO 20400669. Re-exam after repair -

Acceptable 1200445 Zi PIPE-TO-ELBOW HE-CB CB MT-105 MT 05GM015 Accept FW B-109 B-1 09 B-11 B-11 B-1I RT-1 04 VT-1 03 RT 05GRTOIO Accept FW VT 05GV347 Accept FW Comments:

05 - VT & MT: No Recordable Indications - Accept. RT: Insignificant - EUC, Root concavity - Accept 1200450 Z2 ELBOW-TO-PIPE HE-CB CB MT-1 05 VT-103 RT-104 I

Comments:

05 - VT & MT: No Recordable Indications - Accept. RT: Insignificant indications - porosity - Accept.

MT 05GM009 Accept FW VT 05GV267 Accept FW RT 05GRT009 Accept FW RT 05GRT006 Accept FW VT 05GV268 Accept FW MT 05GM008 Accept FW B-11 B-11 B-1I B-1I B-1I B-1I 1200455 Z3 PIPE-TO-ELBOW HE-CB CB RT-104 VT-1 03 MT-105 Comments:

05 - VT & MT: No Recordable Indications - Accept. RT: No Recordable Indications - No change since last examination - Accept.

(

(

Owner:

Plant:

Plant Unit:

Affachment 1A - ISI Report - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 1

I Page of 13 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/Sheet/Results System ISO #

1200460 Z4 ELBOW-TO-PIPE HE-CB CB VT-103 VT 05GV348 Accept FW B-11 MT-105 MT 05GM016 Accept FW B-11 RT-1 04 RT 05GRT003 Accept FW B-11 Comments:

05 - VT: No Recordable Indications - Accept. MT: No Recordable Indications - Accept. RT: Insignificant - Porosity, Slag, IUC, Concavity - Accept 1200565 N1 ELBOW-TO-PIPE HE-CB CB PT-106 PT 05GP059 Accept FW RT-104 RT 05GRT008 Accept FW VT-103 VT 05GV345 Accept FW MT-105 MT 05GM013 Accept FW Comments:

05 - VT: No Recordable Indications - Accept. MT: No Recordable Indications - Limited exam due to support - 87% - Accept. PT: No Recordable Indications - PT MT could not be performed - 12% - Accept. RT: No Recordable Indications - Film trimmed to fit between support - Accept.

1200570 0

PIPE-TO-ELBOW HE-CB CB RT-104 RT 05GRT007 Accept FW MT-105 MT 05GM014 Accept FW VT-1 03 VT 05GV346 Accept FW Comments:

05 - VT & MT: No Recordable Indications - Accept. RT: Insignificant - Porosity, Root concavity, under cut - Accept B-14 B-14 B-14 B-14 area where B-1 4 B-14 B-14 B-14 B-14 B-14 1200580 P

PIPE-TO-ELBOW HE-CB CB RT-104 RT 05GRT005 Accept VT-1 03 VT 05GV280 Accept MT-105 MT 05GM011 Accept Comments:

05 - VT: Minor corrosion - Accept. MT: No Recordable Indications - Accept. RT: Insignificant - Porosity, slag. No change since last examination - Accept.

FW FW FW 1411200 MAINSTEAM OUTSIDE CONTAINMENT Comments:

05-VT-2: Light rust noted on various valves - no degradation. Leakage Exam Acceptable C-H C7.XX VT-109 C7.XX VT-1 09 VT 05GV002 Accept MS L-A L-1 1411600 FW OUTSIDE CONTAINMENT FEEDWATER SYSTEM LEAKAGE EXAMINATION C-H Comments:

05-VT-2: Light rust noted on various Valves - no degradation noted. Leakage Exam Acceptable VT 05GV009 Accept FW 1412500 SAFETY INJECTION "A" PUMP IN/OUT CONTAINMENT C-H C7.XX VT-109 Comments:

05-VT-2: Partial Exam - Inside CV only. No Recordable Indications - Accept. Outside CV will be performed in 2006 Outage.

1412600 SAFETY INJECTION "B" PUMP IN/OUT CONTAINMENT C-H C7.XX VT-109 Comments:

05-VT-2: Partial Exam - Inside CV only. No Recordable Indications - Accept. Outside CV will be performed in 2006 Outage.

VT 05GV430 Accept VT 05GV429 Accept Si L-1 Si L-1 1413200 RHR LOW PRESSURE "A" PUMP C-H C7.XX VT-109 VT 05GV405 Accept RHR Comments:

05-VT-2: Boric Acid noted on Pump Shaft Seal (AR# 2005-1757), Boric Acid noted on Valve 850A stem / packing area (AR# 2005-1744) - Acceptable L-A

(

( A - ISI Report - 2005 Outage Page of 14 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Reg.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

I National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheetlResults System ISO #

1413300 RHR LOW PRESSURE "B" PUMP C-H C7.XX VT-109 VT 05GV404 Accept RHR L-1 Comments:

05-VT-2: Boric Acid noted on Pump shaft seal area (AR# 2005-1758) - Acceptable 1413400 RHR PUMP "A" IN/OUT CONT.

C-H C7.XX VT-109 VT 05GV403 Accept RHR L-1 Comments:

05-VT-2: Boric Acic noted on Valves 694A (AR# 2005-1752), 709A (AR# 2005-1751), 709C (AR# 2005-1749), 705C (AR# 2005-1746), 850A (AR# 2005-1744), 822A (AR#

2005-1743), - Acceptable 1413500 RHR PUMP "B" IN/OUT CONT.

C-H C7.XX VT-109 VT 05GV406 Accept RHR L-1 Comments:

05-VT-2: Boric Acid noted on RCDT drain line (AR# 2005-1756), FT-931 B & 12074L-Swagelok fitting (AR# 2005-1755), 857B (AR# 2005-1754), FE-626 (AR# 2005-1753),

709B (AR# 2005-1750), 709D (AR# 2005-1748), 711 E (AR# 2005-1745) -Acceptable 1414600 CHARGING & SEAL WATER FROM PUMPS (IN/OUT CV)

C-H C7.XX VT-109 VT 05GV431 Accept CVCS L-1 Comments:

05-VT-2: Partial Exam - Inside CV only. No Recordable Indications -Accept. Outside CV will be performed in 2006 Outage.

1414700 LETDOWN SYSTEM IN/OUT CONTAINMENT C-H C7.XX VT-109 VT 05GV432 Accept CVCS L-1 Comments:

05-VT-2: Partial Exam - Inside CV only. No Recordable Indications -Accept. Outside CV will be performed in 2006 Outage.

1415650 RPV (RPC01)

CLASS 2 INSTRUMENTATION C-H C7.XX VT-109 VT 05GV428 Accept RC L-1 Comments:

05-VT-2: No Recordable Indications -Acceptable 1600380 AFU-111 MECHANICAL SNUBBER SN-VT VT VT-106 VT 05GV033 Accept AFW C-IA Comments:

05-VT: Required Snubber setting per IP lIT 5 Rev 3 is 2", Actual is 2". Serial # 16597. No Recordable Indications -Acceptable. Note: elevated temperature is from FW System.

1601100 FWU-3 HYDRAULIC SNUBBER SN-VT VT VT-107 VT 05GV287 Accept FW B-12 VT-106 VT 05GV367 Accept FW B-12 Comments:

"05-VT: Pre-Functional -S/N 2500-10-152 -required cold setting 4 1/16" -actual 3 25/32". Vise marks on piston where the setting prick punch mark is located, prick punch mark was not evident -Accept. VT: Post-Functional - S/N 2500-10-152 -required cold setting 4 1/16" -actual 3 5/8" -No Recordable Indications -Accept.

1601101 FWU-3 HYDRAULIC SNUBBER SN-FT FT FT VT 05GV437 Accept FW B-12 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 2500-10-152.

1601320 FWU-54 MECHANICAL SNUBBER SN-VT VT VT-106 VT 05GV371 Accept FW B-14 VT-107 VT 05GV223 Accept FW B-14 Comments:

05-VT: Pre-Functional - Snubber S/N 7482, Required hot setting per IP IlT 5 rev 4 is 3 1/8", Actual 3 1/2", no ID tag, bird feces noted on snubber - Accept. VT: Post-Functional

- Snubber S/N 7482, Required cold setting is 3 13/16", Actual 4 1/8", No Recordable Indications -Accept.

1601321 FWU-54 MECHANICAL SNUBBER SN-FT FT FT VT 05GV438 Accept FW B-14 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 7482.

1601369 MSU-7 (TOP/WEST)

MECHANICAL SNUBBER SN-VT VT VT-1 06 VT 05GV373 Accept MS B-8 VT-107 VT 05GV314 Accept MS B-8 Comments:

05-VT: Pre-Functional - Snubber S/N 7051 - Required cold setting 3", actual 2 5/8" - No Recordable Indications - Accept. VT: Post-Functional - Snubber S/N 4765 - Required cold setting 3" - actual 2 5/8" - No Recordable Indications - Accept.

(

(

C Affachment 1A - ISI Report - 2005 Outage Page of 15 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Req.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetiResults System ISO #

1601370 MSU-7 (BOTTOM/EAST)

MECHANICAL SNUBBER SN-VT VT VT-1 07 VT 05GV315 Accept MS B-8 VT-1 06 VT 05GV372 Accept MS B-8 Comments:

05-VT: Pre-Functional - Snubber SIN 7047 - Required cold setting 3", actual 3" - No Recordable Indications - Accept. VT: Post-Functional - Snubber S/N 7047 - Required cold setting 3" - actual 3" - No Recordable Indications - Accept.

1601371 MSU-7 (TOP/NEST)

MECHANICAL SNUBBER SN-FT FT FT VT 05GV453 Accept MS B-8 Comments:

05-FT: Functionally Tested - Unsat for SIN 7051 - Failed Friction. Replaced with previously is service spare. Re-installed Snubber S/N 4765 - Functionlly tested OK.

1601372 MSU-7 (BOTTOM/EAST)

MECHANICAL SNUBBER SN-FT FT FT VT 05GV439 Accept MS B-8 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-SIN 7047.

1601409 MSU-15 (NORTH)

MECHANICAL SNUBBER SN-VT VT VT-1 07 VT 05GV383 Accept MS B-10A VT-106 VT 05GV393 Accept MS B-1 OA Comments:

05-VT: Pre-Functional & Post-Functional exams were performed on Snubber MSU-1 5 North, SIN 7476, Required cold setting per IP lIT 5 rev 4 is 3 3/4", Actual 3 3/4" -Accept.

Exams not required since MSU-1 5 North was not pulled for functional test, MSU-1 6 South was pulled-AR 2005-2756 generated.

1601411 MSU-15 (NORTH)

MECHANICAL SNUBBER SN-FT FT FT VT 05GV455 Info MS B-1OA Comments:

05-FT: Functional test was not performed, MSU-16 South was pulled inadvertently, AR 2005-2756 was generated.

1601420 MSU-16 (SOUTH)

MECHANICAL SNUBBER SN-VT VT VT-106 VT 05GV457 Accept MS B-10A Comments:

05-VT: Post-Functional, Required setting per ME 303 rev 4 is 4 3/16" +/- 10%, Actual was 4 1/8", No Tag on Support & Bird Feces noted on snubber -Acceptable 1601422 MSU-16 (SOUTH)

MECHANICAL SNUBBER SN-FT FT FT VT 05GV456 Accept MS B-10A Comments:

05-FT: Functionally Tested as part of Expansion - Results are Sat. Re-installed Snubber-SIN 7480, ref AR 2005-0443.

1601460 MSU-25 MECHANICAL SNUBBER SN-VT VT VT-107 VT 05GV395 Accept MS B-1OA VT-106 VT 05GV388 Accept MS B-10A Comments:

05-VT: Pre-Functional - Snubber SIN 1465, Required cold setting per IP lIT 5 rev 4 is 1 3/4", Actual 2", bird feces noted on snubber - Accept. VT: Post-Functional -Snubber S/N 1465, Required cold setting 1 3/4", Actual 1 1/2", No Recordable Indications - Accept.

1601461 MSU-25 MECHANICAL SNUBBER SN-FT FT FT VT 05GV440 Accept MS B-10A Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-SIN 1465. Part of Scope Expansion per AR 2005-0443.

1601480 MSU-27 MECHANICAL SNUBBER SN-VT VT VT-1 07 VT 05GV222 Accept MS B-10A VT-1 06 VT 05GV384 Accept MS B-1OA Comments:

05-VT: Pre-Functional-Snubber S/N 9398, Required setting per IP IIT 5 rev 4 Hot 4 3/8", Actual 4 1/4", tag loose, bird feces -Accept. VT: Post-Functional-Snubber S/N 9398, Required cold setting 1 3/8", Actual 1 3/8". No Recordable Indications -Accept, 1601481 MSU-27 MECHANICAL SNUBBER SN-FT FT FT VT 05GV441 Accept MS B-10A Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 9398.

(

(( A - ISI Report - 2005 Outage Page of 16 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Req.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetlResults System ISO #

1601520 MSU-38 MECHANICAL SNUBBER SN-VT VT VT-107 VT 05GV212 Accept MS B-9A VT-106 VT 05GV370 Accept MS B-9A Comments:

05-VT: Pre-Functional-Subber SIN 1090, Required setting per IP lIT 5 rev. 4 - hot is 1 5/8", Actual 1 1/2", No Recordable Indications - Accept. VT: Post-Functional-Required cold setting is 3", Actual cold setting 3", No Recordable Indications - Accept. SIN 1090 1601521 MSU-38 MECHANICAL SNUBBER SN-FT FT FT VT 05GV442 Accept MS B-9A Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-SIN 1090.

1601710 RHU-36 MECHANICAL SNUBBER SN-VT VT VT-1 06 VT 05GV246 Accept RHR B-23 VT-107 VT 05GV242 Accept RHR B-23 Comments:

05-VT: Pre-Functional-Snubber SIN 15756, Required setting per IP IIT 5 rev 4 is 2 1/2", Actual 2 1/4", there were no increments remaining on snubber, items #6 & 7 are inverted per drawing. - Accept. VT: Post-Functional-Snubber SIN 15756, Required Setting 2 1/2", Actual 2 5/8". No Recordable Indications - Accept.

1601711 RHU-36 MECHANICAL SNUBBER SN-FT FT FT VT 05GV445 Accept RHR B-23 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 15756.

1601800 RHU-92 MECHANICAL SNUBBER SN-VT VT VT-1 06 VT 05GV216 Accept RHR B-21 Comments:

05-VT: BAMP inspection (Sum# N05392) noted Snubber SIN 22190 having Boron on it. AR# 2005-0589 generated for Functional testing. Snubber operable, Old Snubber replaced under WO 20501165 with S/N 18750 due to light corrosion on housing. Required setting per IP IIT 5 rev 4 is 2", Actual is 2 1/4". NRI - Accept.

1601910 SWU-309 MECHANICAL SNUBBER SN-VT VT VT-1 07 VT 05GV213 Accept SW B-50A VT-1 06 VT 05GV368 Accept SW B-50A Comments:

05-VT: Pre-Functional-Snbber SIN 10073, Required setting per IP IIT 5 rev. 4 is cold 3 3/8", Actual 3 1/4", No Recordable Indications - Accept. VT: Post-Functional-Snbber S/N 10073 -Required cold setting is 3 3/8", Actual 3 1/2", No Recordable Indications - Accept.

1601911 SWU-309 MECHANICAL SNUBBER SN-FT FT FT VT 05GV447 Accept SW B-50A Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 10073.

1601990 AFU-225 (AFW-29)

HYDRAULIC SNUBBER SN-VT VT VT-107 VT 05GV344 Accept SAFW C-20 VT-1 06 VT 05GV307 Accept SAFW C-20 Comments:

05-VT: Pre-Functional-Snub. S/N 12906-Req. cold setting 2 1/4", Actual 3 1/16". Engineering provided new calculated cold setting of 2 5/8", reservoir 75% full, No Recordable Indications (NRI)- Accept. VT: Post-Functional-Snub. S/N 12905 - Req. new setting per Engineering is 2 5/8", Actual 3", reservoir acceptable, NRI-Accept.

1602500 AFU-229 HYDRAULIC SNUBBER SN-VT VT VT-106 VT 05GV306 Accept SAFW C-20 VT-1 07 VT 05GV262 Accept SAFW C-20 Comments:

05-VT: Pre-Functional-Snub. SIN 21009-Req. setting 1 1/2", Actual 1 3/4", reservoir is >50% full, No Recordable Indications(NRI)- Accept. Snubber removed & put back in prior to pre inspection-AR generated. VT: Post-Functional-Snub. S/N 129C4-Req. setting 1 1/2", Actual 1 3/4", reservoir is 70% full, NRI-Accept.

Class 3 1411700 AUX FW "A" PUMP AFW SYSTEM LEAKAGE EXAMINATION D-B D2.XX VT-109 VT 05GV411 Accept AFW L-1 VT-1 09 VT 05GV004 Reject AFW L-1 Comments:

05-VT-2: Valves 4000A & 4357, Ref AR's 2003-1869 & 2003-1870, Leakage also noted at Pump Casing Bolting due to gasket seepage, RE performed an Acceptance by Analytical Evaluation for the leakage at Pump Casing Bolting, Ref AR 2005-1855 - Acceptable

(

(

Owner:

Plant:

Plant Unit:

Affachment 1A - ISI ReDort - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 I

Page of 17 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheet/Results System ISO #

1411800 AUX FW "B" PUMP AFW SYSTEM LEAKAGE EXAMINATION D-B D2.XX VT-109 VT 05GV409 Accept AFW L-1 VT-1 09 VT 05GV410 Accept AFW L-1 Comments:

05-VT-2: Leakage noted at Pump Casing Bolting due to gasket seepage, RE performed an Acceptance by Analytical Evaluation for the leakage at Pump Casing Bolting, Ref AR 2005-1773 & 2005-1775 - Acceptable 1411900 AUXFWTURBINE DRIVEN PUMP AFW SYSTEM LEAKAGE EXAMINATION D-B D2.XX VT-109 VT 05GV417 Accept AFW L-1 Comments:

05-VT-2: Leakage noted at Pump Casing Bolting due to gasket seepage, RE performed an Acceptance by Analytical Evaluation for the leakage at Pump Casing Bolting, Ref AR 2005-1855 - Acceptable 1414000 SERVICE WATER OUTSIDE CONTAINMENT D-B D2.XX VT-109 VT 05GV359 Accept SW L-1 VT-109 VT-109 Comments:

05-VT-2: Exan performed at 3 different times do to Valves not being aligned for normal operation - Acceptable VT 05GV010 Accept VT 05GV205 Accept SW SW L-1 L-1 1414100 SERVICE WATER TO AUX FW PUMP "A" Comments:

05-VT-2: No Recordable Indications - Leakage Exam Acceptable D-B D2.XX VT-109 VT 05GV005 Accept SW L-1 1415100 Diesel Gen. A Diesel Gen. "A" D-B D2.XX VT-109 VT 05GV207 Accept DG L-1 Comments:

05-VT-2: Performed on Coolant Water, Fuel Oil, Lube Oil & Starting Air Piping & Components - Minor Air leak at threaded connection up/st of V5933B, AR# 2004-1261 generated - Fittings tighten - Leakage Exam Acceptable 1415200 Diesel Gen. B Diesel Gen. "B" D-B D2.XX VT-109 VT 05GV208 Accept DG L-1 Comments:

05-VT-2: No Recordable Indications - Leakage Exam is Acceptable.

1415550 SPENT FUEL POOL COOLING-B SFP COOLING SYSTEM LEAKAGE EXAMINATION D-B D2.XX VT-109 VT 05GV038 Accept SF L-1 Comments:

05-VT-2: Noted components have Boric Acid: Valve 8669A (ref AR 2004-2030), V 8659 (ref AR 2004-2820), V 8667D (ref AR 2004-2026), V 782 (ref AR 2004-2024), "B" SFP pump (AR 2004-2023), FIg near V 799E (ref AR 2004-2031) - Leakage Exam Acceptable.

1500105 DGIN-1A RIGID SUPPORT (IA)

F-A F1.30A VT-106 VT 05GV229 Accept DG C-39 Comments:

05-VT: Poor workmanship was noted on welds - Ref NCR94-054 - Acceptable 1500765 CCU-156 RIGID SUPPORT (IA)

Comments:

05-VT: No Recordable Indications - Acceptable. No ID tag.

F-A F1.30A VT-106 VT 05GV226 Accept AC C-6 1500960 CCU-218 (IA)

INTEGRAL ATTACHMENT D-A D1.20 VT-103 VT 05GV220 Accept AC C-7 Comments:

05-VT: Intragal Attachment (IA) is not an IA, lugs left from initial construction. Component Support Drawing does not identify or require an IA. Remove from schedule.

1500965 CCU-218 RIGID HANGER (IA)

Comments:

05-VT: No Recordable Indications - Accept.

1501660 SWU-164 (IA)

INTEGRAL ATTACHMENT Comments:

05-VT: No Recordable Indications - Acceptable. Ref. WO # 20403212 F-A F1.30A VT-106 VT 05GV219 Accept AC VT 05GV203 Accept SW C-7 C-1I D-A D1.20 VT-1 03

(

( A - 1St Report - 2005 Outage

(

Page of 18 - 21 Owner:

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

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

1 Owner Certificate of Authorization (If Reg.):

Commercial Service Date:

National Board Number for Unit:

N/A 7/1/1970 N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetlResults System ISO #

1501665 SWU-164 RIGID HANGER (IA)

Comments:

05-VT: No Recordable Indications - Acceptable. Ref. WO 20403212 F-A F1.30B VT-106 VT 05GV204 Accept SW C-11 1505240 AFU-101 MECHANICAL SNUBBER F-A F1.30C VT-106 VT Comments:

05-VT: Required Cold setting per IP lIT 5 is 3", Actual setting is 3 318", Serial # 15751. No Recordable Indications - Acceptable 05GV035 Accept AFW C-1 C 1505410 AFU-43 RIGID RESTRAINT Comments:

05-VT: No Recordable Indications - Acceptable F-A 1505480 AFU-50 GUIDE Comments:

05-VT: No Recordable Indications - Acceptable F-A F1.30A VT-106 F1.30B VT-106 F1.30A VT-106 F1.30A VT-106 VT 05GV209 Accept VT 05GV260 Accept VT 05GV032 Accept VT 05GV036 Accept AFW AFW AFW AFW C-1D C-1A C-1 C-1 1505920 AFU-83 RIGID RESTRAINT Comments:

05-VT: No Recordable Indications - Acceptable 1505930 AFU-84 RIGID RESTRAINT Comments:

05-VT: No Recordable Indications - Acceptable F-A F-A 1600260 AFU-52 MECHANICAL SNUBBER SN-VT VT VT-1 06 VT 05GV266 Accept VT-1 07 VT 05GV261 Accept AFW AFW C-1A C-iA Comments:

05-VT: Pre-Functional-Snubber S/N 24453, Required setting per IP IIT 5 Rev 4 is 1 7t8", Actual 1 3/4", No Recordable Indications - Accept. VT: Post-Functional-Required setting 1 7/8", Actual 1 3/4", No Recordable Indications - Accept. S/N 24453 1600261 AFU-52 MECHANICAL SNUBBER SN-FT FT FT VT 05GV435 Accept AFW C-1A Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 24453.

1601610 MSU-74 MECHANICAL SNUBBER SN-VT VT VT-107 VT 05GV211 Accept MS C-32 VT-1 06 VT 05GV377 Accept MS C-32 Comments:

05-VT: Pre-Functional-S/N 10066, Required hot setting per IP IIT 5 rev. 4 is 3 5116 ", Actual 3 1/4". No Recordable Indications - Accept. VT: Post-Functional-S/N 10066, Required cold setting is 3", Actual cold setting 3 3/8". No Recordable Indications - Accept.

1601611 MSU-74 MECHANICAL SNUBBER SN-FT FT FT VT 05GV443 Accept MS C-32 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 10066.

1601650 MSU-82 MECHANICAL SNUBBER SN-VT VT VT-1 06 VT 05GV369 Accept MS C-32 VT-107 VT 05GV221 Accept MS C-32 Comments:

05-VT: Pre-Functional-Snbber S/N 15768, Required setting per IP IIT 5 rev. 4 hot is 2 11/16", Actual 2 3/4". No Recordable Indications - Accept. VT: Post-Functional-Snubber S/N 15768, Required cold setting 2 1/2", Actual 2 3/8". No Recordable Indications - Accept.

1601651 MSU-82 MECHANICAL SNUBBER SN-FT FT FT VT 05GV444 Accept MS C-32 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N 15768.

(

( A - ISI Report - 2005 Outage Owner:

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

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

1 Page of 19 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure Method/SheetlResults System ISO #

NonClass 1411400 Comments:

MS HIGH ENERGY HE MS LEAKAGE EXAM HE-I 05-VT-2: Light rust noted on various valves - no degradation noted. Leakage Exam Acceptable HE-I

.K LEAK VT-109

..K LEAK VT-109 VT 05GV003 Accept MS VT 05GV006 Accept FW L-1 L-1 1412200 HE FEEDWATER HE FW LEAKAGE EXAMINATION Comments:

05-VT-2: Light Rust noted on various valves - no degradation. Leakage Exam Acceptable 1700170 CVU-39 VARIABLE SPRING SS-CS SSF1.20(VT-106 Comments:

05-VT: Required Cold Setting per ME 303 RevS is 107# - Actual 114# - No Recordable Indications - Acceptable.

VT 05GV394 Accept CVCS-LTC A-23A 1700180 CVU-40 VARIABLE SPRING SS-CS SSF1.20(VT-106 VT 05GV316 Accept CVCS-LTCA-23A Comments:

05-VT: Required setting per ME 303 rev 5 is 95# +/- 10%, actual is 103#, size of can per drawing states size 1, actual is size 2, ref AR 2005-1685, RE notified - use as is, this is the correct size can, Acceptable. DCR Generated by RE.

1700480 MSU-52 RIGID SUPPORT& IA SS-CS SSF1.20, VT-106 VT 05GV374 Accept MS B-9A Comments:

05-VT: No Recordable Indications - Acceptable Class Q 1200275 C

PIPE-TO-ELBOW HE-CB CB UT-209 VT-1 03 MT-105 Comments:

05-VT: Undercut <1/32" - Accept. MT: No Recordable Indications - Accept. UT: Base Metal Lamination - performed 3130194.

UT 05GU008 Accept MS HE-7A VT 05GV289 Accept MS HE-7A MT 05GM002 Accept MS HE-7A UT: PDI - Geometry Indication - Accept.

1200280 C1 ELBOW-TO-PIPE HE-CB CB VT-103 VT 05GV288 Accept MS HE-7A MT-105 MT 05GM004 Accept MS HE-7A UT-209 UT 05GU009 Accept MS HE-7A Comments:

05, VT: Minor pitting on pipe <1/32" - Accept. MT: No Recordable Indications - Accept. UT: PDI - No Recordable Indications - Accept. Base Metal Lamination performed in 1995.

1200285 D

PIPE-TO-ELBOW HE-CB CB UT-209 UT 05GU012 Accept MS HE-7A MT-105 MT 05GM006 Accept MS HE-7A VT-1 03 VT 05GV265 Accept MS HE-7A Comments:

05 - VT: Minor Pitting noted in base material <1/32" - Accept. MT: No Recordable Indications - Accept. UT: PDI - Geometry Indication noted - Accept. Base Metal Lamination performed in 1995.

C C

( A - ISI Report - 2005 Outage Page of 20 - 21 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorization (If Req.):

N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit:

1 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

Category Item Procedure MethodlSheetlResults System ISO#

1200320 M2 ELBOW-TO-PIPE HE-CB CB MT-105 MT 05GM003 Accept FW HE-6 UT-209 UT 05GUOIO Accept FW HE-6 VT-1 03 VT 05GV290 Accept FW HE-6 Comments:

05-VT & MT: No Recordable Indications -Accept. UT: PDI - ID Geometry, Intermittantly 3600 -Accept. Utilized lamination scan from 1995.

1201420 MS-45 (S21)

VARIABLE SPRING HE-CS HEFI.201VT-106 VT 05GV381 Accept MS HE-7A Comments:

05-VT: Required setting per ME 303 rev 5 cold is 5205 #'s, Actual 4733 #'s. No Recordable Indications - Acceptable.

1201440 MS-46 (S22)

VARIABLE SPRING (IA)

HE-CS HEF1.201VT-106 VT 05GV382 Accept MS HE-7A Comments:

05-VT: Required Cold Setting per ME 303 Rev 5 is 6721# - Actual 6574# - No Recordable Indications -Acceptable.

1202220 FW-43 (S31)

VARIABLE SPRING HE-CS HEF1.201VT-106 VT 05GVOOI Accept FW HE-6 Comments:

05-VT: Required setting per ME 303 is 7962#, Actual is 8200#. No Recordable Indications -Acceptable. (Ref. WO 20303027).

1601060 CVU-351 MECHANICAL SNUBBER SN-VT VT VT-106 VT 05GV239 Accept CVCS-LTE B-35 VT-107 VT 05GV243 Accept CVCS-LTC B-35 Comments:

05-VT: Pre-Functional - Snubber S/N 9472 - Required hot setting 7/8", Actual 1". Transition tube kit, pipe clamp & bolting have light to moderate rust. -Accept. VT: Post-Functional - Snubber SIN 9472 - Required cold setting 1 1/4", actual 1", no change from previous inspection -Accept.

1601061 CVU-351 MECHANICAL SNUBBER SN-FT FT FT VT 05GV436 Accept CVCS-LTC B-35 Comments:

05-FT: Functionally Tested-Results are Sat. Re-installed Snubber-S/N 9472.

1602060 N608 HYDRAULIC SNUBBER SN-VT VT VT-1 07 VT 05GV264 Accept PZR S-2 VT-1 06 VT 05GV303 Accept PZR S-2 Comments:

05-VT: Pre-Functional - Snubber SIN 6563, Required cold setting per IP IIT 5 rev. 4 is 3 5/8", Actual 3 7/8", No Recordable Indications -Accept. VT: Post-Functional -

Snubber SIN 32844, Required cold setting is 3 5/8", Actual 4 3/8", No Recordable Indications - Accept.

1602061 N608 HYDRAULIC SNUBBER SN-FT FT FT VT 05GV448 Accept PZR S-2 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-SIN 32844.

1602090 PS-2 HYDRAULIC SNUBBER SN-VT VT VT-1 07 VT 05GV263 Reject PZR S-1 VT-106 VT 05GV305 Accept PZR S-1 Comments:

05-VT: Pre-Functional -Snubber SIN PD-87239-1244 -Req. Cold setling per IP lIT 5 Rev 4 is 4 3/8", Actual 4 114", Fluid indicator -no green band showing -Rejected -AR 2005-1279 generated. Functionally tested -operable -Accept. VT: Post-Functional - same S/N - setting 4 1/8" & fluid level OK -Accept.

1602091 PS-2 HYDRAULIC SNUBBER SN-FT FT FT VT 05GV449 Accept PZR S-1 Comments:

05-FT: Functionally Tested - Results are Sat. Re-installed Snubber-S/N PD 87239-1244.

1700200 FWU-39 MECHANICAL SNUBBER & IA SS-CS SSF1.20(VT-106 VT 05GV210 Accept FW B-14 Comments:

05-VT: Snubber SIN 9354, Required setting per IP lIT 5 rev 4 is 3 1(8", Actual setting 3 1/2", No Recordable Indications -Acceptable

C

(. A - ISI Report - 2005 Outage Owner:

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

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

I Page of 21 - 21 Owner Certificate of Authorization (If Reg.):

N/A Commercial Service Date:

7/1/1970 National Board Number for Unit:

N/A Summary # Comp ID Comp Desc.

1700580 RHU-87 RIGID SUPPORT & IA Comments:

05-VT: Heavy paint and light to medium rust noted, ID tag was painted - Acceptable Category Item Procedure Method/SheetlResults System SS-CS SSF1.20,VT-106 VT 05GV217 Accept RHR

=

ISO #

B-21

.=

(

Owner:

Plant:

Plant Unit:

Attachment lB - IWE/IWL ISI Report - 2005 Outage R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatik R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

I National Board Number for Unit:

Page of 1 -17 N/A 7/1/1970 N/A System Sum #

Comp ID Class CC Comp Desc.

Cat. # Item # Procedure MethodlSheet/Results 1950000 Comments:

1950010 Comments:

1950020 Comments:

1950030 Comments:

1950040 Comments:

1950050 Comments:

1950060 Comments:

1950070 Comments:

1950080 Comments:

1950090 Comments:

1950100 Comments:

1950110 Comments:

DOOME, TENDONS & AREAS CONCRETE SURFACE ALL AREAS L-A L1.11 VT-113 VT 05GV043 Accept CONTAINMENT VT-113 VT 05GV042 Accept CONTAINMENT VT-113 VT 05GV041 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor chages were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE EQUIPMENT HATCH AREAS CONCRETE SURFACE ALL AREAS L-A L1.11 VT-113 VT 05GV016 Accept CONTAINMENT 05-VT-3C: Perforned on CV Concrete Surfaces, Ref WO 20303181, minor chages were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

SUB-BASEMENT @ 237-0 & 238 INT. BLDG. SOUTH (RAD AREA) CONCRETE SURFACE L-A 1-11 VT-113 VT 05GV029 Accept CONTAINMENT 05-VT-3C: Exam Performed on CV Concrete Surfaces, Ref WO 20303181, minor chages were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

BASEMENT@ 253-6 INT. BLDG. SOUTH (RADAREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV018 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no change from baseline noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

PLATFORM @ 267-3 INT. BLDG. SOUTH (RADAREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV014 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor chages were noted, Results of the Exam were reported to RPE for Review, Exam Acceptable per RPE.

FLOOR@ 271-0 (RP DESK AREA)

INT. BLDG. SOUTH (RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV017 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, chage noted - 1 1/2 dia. pipe sticking out of wall - not noted on previous inspection, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

FLOOR@ 293-0 INT. BLDG. SOUTH (RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV019 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no change from last inspection, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

ROOFTOP @ 318-0(lB LOW ROOF)

INT. BLDG. SOUTH (RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV013 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor chages noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

BASEMENT@ 253-6 INT. BLDG. NORTH (NON-RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV020 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no chage noted from previous exam other than the Azimuths 200 to 304 are actually 300 to 304. Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

PLATFORM @267-3 INT. BLDG. NORTH (NON-RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV022 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no chages noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE.

FLOOR @267-3 INT. BLDG. NORTH (NON-RADAREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV021 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no chages were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE Acceptable.

FLOOR @2984 INT. BLDG. NORTH (NON-RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV023 Accept CONTAINMENT 05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no chage noted since last exam, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE

Attachment I B - IWE/IWL ISI Report - 2005 Outage Page of 2 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure MethodlSheetlResults System 1950120 FLOOR @315-4 INT. BLDG. NORTH (NON-RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV024 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no change noted since last exam, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1950130 ROOFTOP @336-6(IB HIGH ROOF)

INT. BLDG. NORTH (NON-RAD AREA) CONCRETE SURFACE L-A L1.11 VT-113 VT 05GV011 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no change noted since last exam, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1950140 BASEMENT FLOOR @258-8 AUX. BLDG. CONCRETE SURFACES L-A L1.11 VT-113 VT 05GV031 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor changes were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1950150 INTERMEDIATE FLOOR @ 253-0 AUX. BLDG. CONCRETE SURFACES L-A L1.11 VT-113 VT 05GV015 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, no changes were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1950160 OPERATING FLOOR @ 271-0 AUX. BLDG. CONCRETE SURFACES L-A L1.11 VT-113 VT 05GV030 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor changes were noted, Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1950170 PLATFORM @ 311-6 AUX. BLDG. CONCRETE SURFACES L-A L1.11 VT-113 VT 05GV012 Accept CONTAINMENT Comments:

05-VT-3C: Exam performed on CV Concrete Surfaces, Ref WO 20303181, minor changes were noted. Results of the Exam were reported to RPE for Review. Exam Acceptable per RPE 1957001

1. 1 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV040 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets. Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957002

1. 2 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV044 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957003

1. 3 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV045 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base & lid - Sat, Oil Leakage - Sat, Upper & Lower Gaskets = lower gasket has minor checking-Sat, Vent -

Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957004

1. 4 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV046 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base and lid - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat, Exam Acceptable per RPE Review 1957005

1. 5 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV047 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957006

1. 6 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV048 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957007

1. 7 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV049 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

C

( B - IWEIIWL ISI Report - 2005 Outage Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatik Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

Plant Unit: 1 National Board Number for Unit:

Page of 3 -17 N/A 7/1/1970 N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure Method/Sheet/Results System 1957008

1. 8 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV050 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957009

1. 9 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV051 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957010

1. 10 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV052 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957011

1. 11 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV053 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957012

1. 12 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV054 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust = minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minoe checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957013

1. 13 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV055 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957014

1. 14 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV056 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957015

1. 15 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV057 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957016

1. 16 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV058 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957017

1. 17 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV059 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957018

1. 18 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV060 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957019

1. 19 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV061 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957020

1. 20 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV062 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

Attachment I B - IWE/IWL ISI Report - 2005 Outage Page of 4 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: I National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure MethodlSheet/Results System 1957021

1. 21 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV063 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957022

1. 22 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV064 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957023

1. 23 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV065 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957024

1. 24 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV066 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957025

1. 25 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV067 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957026

1. 26 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV068 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957027

1. 27 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV069 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957028

1. 28 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV070 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957029

1. 29 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV071 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957030

1. 30 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV072 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957031

1. 31 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV073 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957032

1. 32 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV074 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957033

1. 33 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV075 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(

~(C Affachment I B - IWEIIWL ISI Report - 2005 Outage Page of 5 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure MethodlSheetlResults System 1957034

1. 34 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV076 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957035

1. 35 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV077 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957036

1. 36 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV078 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957037

1. 37 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV079 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957038

1. 38 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV080 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957039

1. 39 TENDON GREASE CAP L-GC GC-1 VT-1 13 VT 05GV081 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957040

1. 40 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV082 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957041

1. 41 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV083 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957042

1. 42 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV084 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957043

1. 43 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV085 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957044

1. 44 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV086 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957045

1. 45 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV087 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957046

1. 46 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV088 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(

(

Affachment 1B - IWE/IWL ISI Report - 2005 Outage Page of 6 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure Method/SheetResults System 1957047

1. 47 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV089 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957048

1. 48 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV090 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957049

1. 49 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV091 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957050

1. 50 TENDON GREASE CAP L-GC GC-1 VT-113 VT OSGV092 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957051

1. 51 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV093 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957052

1. 52 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV094 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957053

1. 53 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV095 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket, also curling upward at Southeast quadrant, the can appears to be off center to the Northwest - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957054

1. 54 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV096 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957055

1. 55 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV097 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat, No Recordable Indications. Exam Acceptable per RPE Review 1957056

1. 56 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV098 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957057

1. 57 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV099 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957058

1. 58 TENDON GREASE CAP L-GC GC-1 VT-113 VT O5GV100 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957059

1. 59 TENDON GREASE CAP L-GC GC-1 VT-113 VT O5GV101 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(

( B - IWEIIWL ISI Report - 2005 Outage Page of 7 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic NMA Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item # Procedure MethodlSheetResults System 1957060

1. 60 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV102 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957061

1. 61 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV103 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957062

1. 62 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV104 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957063

1. 63 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV105 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957064

1. 64 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV106 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957065

1. 65 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV107 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat, No Recordable Indications. Exam Acceptable per RPE Review 1957066

1. 66 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV108 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957067

1. 67 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV109 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957068

1. 68 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV110 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957069

1. 69 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV111 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957070

1. 70 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV112 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957071

1. 71 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV113 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957072

1. 72 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV114 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

((

(I Attachment IB - IWE/IWL ISI Report - 2005 Outage Page of 8 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure MethodlSheetlResults System 1957073

1. 73 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV115 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957074

1. 74 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV116 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957075

1. 75 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV117 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957076

1. 76 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV118 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957077

1. 77 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV119 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957078

1. 78 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV120 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957079

1. 79 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV121 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957080

1. 80 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV122 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957081

1. 81 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV123 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at lid bolting - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957082

1. 82 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV124 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957083

1. 83 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV125 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957084

1. 84 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV126 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957085

1. 85 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV127 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(

(

(7 Attachment lB - IWE/IWL ISI Report - 2005 Outage Page of 9 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat # Item #

Procedure MethodlSheetlResults System 1957086

1. 86 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV128 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957087

1. 87 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV129 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957088

1. 88 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV130 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking of lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957089

1. 89 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV131 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957090

1. 90 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV132 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957091

1. 91 TENDON GREASE CAP L-GO GC-1 VT-113 VT 05GV133 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957092

1. 92 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV134 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957093

1. 93 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV135 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957094

1. 94 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV136 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957095

1. 95 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV137 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can plug at Northeast quadrant - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat.

Exam Acceptable per RPE Review 1957096

1. 96 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV138 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957097

1. 97 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV139 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957098

1. 98 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV140 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Minor Rust at Can Base. Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Lower gasket has major checking - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

Attachment I B - IWE/IWL ISI Report - 2005 Outage Page of 10 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

711/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure Method/SheetlResults System 1957099

1. 99 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV141 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957100

1. 100 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV142 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957101

1. 101 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV143 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957102

1. 102 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV144 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957103

1. 103 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV145 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957104

1. 104 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV146 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957105

1. 105 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV147 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957106

1. 106 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV148 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957107

1. 107 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV149 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957108

1. 108 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV150 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957109

1. 109 TENDON GREASE CAP L-GC GC-1 VT-1 13 VT 05GV151 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957110

1. 110 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV152 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat, No Recordable Indications. Exam Acceptable per RPE Review 1957111

1. 111 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV153 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(9

(( B - IWE/IWL ISI Report - 2005 Outage Page of 11 -17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item # Procedure MethodlSheetlResults System 1957112

1. 112 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV154 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets. Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957113

1. 113 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV155 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957114

1. 114 TENDON GREASE CAP L-GC GC-1 V1T-113 VT 05GV156 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent -Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957115

1. 115 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV157 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957116

1. 116 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV158 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957117

1. 1i7 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV159 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications - Exam Acceptable per RPE Review 1957118

1. 118 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV160 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957119

1. 119 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV161 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957120

1. 120 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV162 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957121

1. 121 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV163 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957122

1. 122 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV164 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957123

1. 123 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV165 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sal, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957124

1. 124 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV166 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

Attachment I B - IWE/IWL ISI Report - 2005 Outage Page of 12 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure Method/SheetResults System 1957125

1. 125 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV167 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957126

1. 126 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV168 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957127

1. 127 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV169 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957128

1. 128 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV170 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957129

1. 129 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV171 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957130

1. 130 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV172 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957131

1. 131 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV173 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957132

1. 132 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV174 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957133

1. 133 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV175 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957134

1. 134 TENDON GREASE CAP 1-GC GC-1 VT-113 VT 05GV176 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. No Recordable Indications. Exam Acceptable per RPE Review 1957135

1. 135 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV177 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957136

1. 136 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV178 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957137

1. 137 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV179 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review

(C

(

Affachment lB - IWElIWL ISI Report - 2005 Outage Page of 13 -17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item # Procedure MethodlSheetlResults System 1957138

1. 138 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV180 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957139

1. 139 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV181 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957140

1. 140 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV182 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957141

1. 141 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV183 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957142

1. 142 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV184 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957143

1. 143 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV185 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957144

1. 144 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV186 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust -minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957145

1. 145 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV187 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957146

1. 146 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV188 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957147

1. 147 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV189 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957148

1. 148 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV190 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957149

1. 149 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV191 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957150

1. 150 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV192 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Can has Upper Gasket & no lower gasket - is a different style - upper & lower welded flange - Sat, Vent

- Sat, Bolting - Sat. Exam Acceptable per RPE Review

C

(

(C Attachment IB - IWE/IWL ISI Report - 2005 Outage Page of 14 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure MethodlSheetlResults System 1957151

1. 151 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV193 Accept CONTAINMENT Comments:

05-VT Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket-Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957152

1. 152 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV194 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - major checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957153

1. 153 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV195 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957154

1. 154 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV196 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957155

1. 155 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV197 Accept CONTAINMENT Comments:

05 - VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking & is curled up at the Southwest quadrant - can appears to be shifted to the Northeast - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957156

1. 156 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV198 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at the lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957157

1. 157 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV199 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - minor checking at the lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review 1957158

1. 158 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV200 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Upper & Lower Gaskets - Sat, Vent - Sat, Bolting - Sat, No Recordable Indications. Exam Acceptable per RPE Review 1957159

1. 159 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV201 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - Sat, Oil Leakage - Sat, Can has Upper Gasket only - different style - no lower gasket - Sat, Vent - Sat, Bolting - Sat, Upper &

Lower Flanges are welded. No Recordable Indications. Exam Acceptable per RPE Review 1957160

1. 160 TENDON GREASE CAP L-GC GC-1 VT-113 VT 05GV202 Accept CONTAINMENT Comments:

05-VT: Performed on Tendon Grease Cans & Gaskets, Paint & Rust - minor rust at can base - Sat, Oil Leakage - Sat, Upper & lower gasket - Sat, Vent - Sat, Bolting - Sat. Exam Acceptable per RPE Review Class MC 1900002 SUMP A LINER CONTAINMENT SUMP A LINER E-A E1.11 VT-112 VT 05GV402 Reject CONTAINMENT VT-112 VT 05GV398 Reject CONTAINMENT Comments:

'05-VT: Failed coating noted & documented. Rej. -AR# 2005-1624 generated. UT readings taken under Summary # N05442. Lowest readings: N. wall top=.270, N. wall bottom=.140', W. wall bottom=.130'. Accept per AR#2003-2505. Areas left unpainted due to cavity leakage-clean & recoat In 06 RFO when dry.

1900222 PEN. CE9 PEN CE9 ELECTRICAL PEN.

E-A E1.11 VT-112 VT 05GV427 Accept ELECTRICAL PEN.

Comments:

05-VT: General Visual - Outside - No Recordable Indications - Acceptable

(

(

(

Attachment lB - IWEIIWL ISI Report - 2005 Outaqe Page of 15 - 17 Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic N/A Plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

7/1/1970 Plant Unit: 1 National Board Number for Unit:

N/A Sum #

Comp ID Comp Desc.

Cat. # Item # Procedure MethodlSheet/Results System 1901001 P29VTArea P29 Liner FloorArea Aug VT E-C E4.11 VT-112 VT 05GV421 Accept CONTAINMENT VT-112 VT 05GV309 Accept CONTAINMENT VT-112 VT 05GV310 Accept CONTAINMENT Comments:

05-VT-1: Performed East of Pen 29, at Pen 29, West of Pen 29. Rust, Flaking & Peeling paint noted -Acceptable. See UT thickness readings under Summary # 1901501.

1901501 P29 UTArea P29 Liner Floor Area Aug UT E-C E4.12 UT-102 UT 05GU017 Accept UT-102 UT 05GU014 Accept Comments:

1902301 Comments:

1903122 Comments:

1903124 Comments:

1903126 Comments:

1903128 Comments:

1903130 Comments:

1903132 Comments:

1903134 Comments:

1903136 Comments:

1903138 Comments:

UT-102 UT 05GUO15 Accept "05-UT: CV Liner near floor-i 20 deg. to 240 deg. Lowest reading East of Pen 29=.356", lowest reading at Pen 29=.334", lowest reading West of Pen 29=370". No wall Inside Pen 29-area noted to be <10% wall loss. Areas reported to RPE - Eng. Min. Wall 0.281"- Accept. Ref AR #2000-1406 & EWR 5190.

BASEMENT 120 TO 240 DEG.

MOISTURE BARRIER E-D E5.30 VT-112 VT 05GV422 Accept 05-VT: Moisture Barrier & Insulation Seal - No Recordable Indications - Acceptable PEN. AE12 BOLTING, 16-1 118" E-G E8.10 VT-112 VT 05GV321 Accept 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable. Removed protective screen for inspection.

PEN. AE13 BOLTING, 16-1 1/8" E-G E8.10 VT-112 VT 05GV322 Accept 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable. Removed protective screen for inspection.

PEN. AE14 BOLTING, 16-1 1/8" E-G E8.10 VT-112 VT 05GV323 Accept 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable. Removed protective screen for inspection.

PEN. BE1 BOLTING, 16 - 1 1/8" E-G E8.10 VT-112 VT 05GV324 Accept 05-VT-I: No Recordable Indications - no change from previous inspection -Acceptable PEN. BE2 BOLTING, 16-1 1/8" E-G E8.10 VT-112 VT 05GV325 Accept 05-VT-I: No Recordable Indications - no change from previous inspection - Acceptable PEN. BE3 BOLTING, 16-11/8" E-G E8.10 VT-112 VT 05GV326 Accept 05-VT-i: No Recordable Indications - no change from previous inspection - Acceptable PEN. BE4 BOLTING, 16-11/8" E-G' E8.10 VT-112 VT 05GV327 Accept 05-VT-i: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE1 BOLTING, 16-1 1/8" E-G E8.10 VT-112 VT 05GV328 Accept 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable PEN. CE2 BOLTING, 16-1 1/8" E-G E8.10 VT-112 VT 05GV329 Accept 05-VT-1: No Recordable Indications - front flange is painted - back flange and bolting is not painted - Acceptable CONTAINMENT CONTAINMENT CONTAINMENT loss >10% outside Pen 29.

MOISTURE BARRIER ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING

(.

(

Page of 16 -17 Attachment lB - IWEIIWL ISI Report - 2005 Outaqe Owner:

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

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Plant Unit: 1 Owner Certificate of Authorizatic Commercial Service Date:

National Board Number for Unit:

Sum #

Comp ID Comp Desc.

Cat. # Item #

Procedure Method/Sheet/Results 1903156 Comments:

1903158 Comments:

1903160 Comments:

1903162 Comments:

1903164 Comments:

1903166 Comments:

1903168 Comments:

1903170 Comments:

1903172 Comments:

1903174 Comments:

1903176 PEN. CE11 BOLTING, 16 - 1 1/8" 05-VT-i: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE12 BOLTING, 16 - 1 118" 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable PEN. CE13 BOLTING, 16-1 1/8" 05-VT-1: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE14 BOLTING, 16-1 1/8" 05-VT-1: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE15 BOLTING, 16-I 1/8" 05-VT-1: No Recordable Indications - no change from previous inspection - Acceptable PEN. CE16 BOLTING, 16-1 118" 05-VT-i: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE17 BOLTING, 16-1 1/8" 05-VT-i: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE18 BOLTING, 16-1 1/8" 05-VT-I: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE19 BOLTING, 16-1 1/8" 05-VT-1: No Recordable Indications - no change from previous inspection -Acceptable.

PEN. CE20 BOLTING, 16-1 1/8" 05-VT-1: No Recordable Indications - no change from previous inspection -Acceptable PEN. CE21 BOLTING, 16-I 1/8" E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 E8.10 VT-112 VT-112 VT-112 VT-112 VT-112 VT-1 12 VT-112 VT-112 VT-112 VT-112 VT-112 VT 05GV330 Accept VT 05GV331 VT 05GV332 VT 05GV333 VT 05GV334 VT 05GV335 VT 05GV336 VT 05GV337 VT 05GV338 VT 05GV339 VT 05GV340 Accept Accept Accept Accept Accept Accept Accept Accept Accept Accept N/A 7/1/1970 N/A System ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING ELECT. PEN. BOLTING CONTAINMENT Comments:

05-VT-i: No Recordable Indications - no change from previous inspection -Acceptable 1904300 SEALS AND GASKETS CONTAINMENT VESSEL E-P E9.40 VT-109 VT 05GV412 Accept Comments:

05-Appendix J Testing - See attached listing of performed PT & PTT Tests that were performed and Acceptable. Also, see Attachment IC of the 2005 90 Day Report.

(C B - IWEIIWL ISI Report - 2005 Outage Owner:

R.E.Ginna Nuclear Power Plant, LLC, 1503 Lake Road, Ontario NY 14519 Owner Certificate of Authorizatic plant:

R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519 Commercial Service Date:

Plant Unit: I National Board Number for Unit:

Page of 17 -17 N/A 7/1/1970 N/A Sum #

Comp ID 1905001 P29 Area Comp Desc.

Paint/Coating Prior to Removal Cat. # Item #

Procedure E-PC PC-1 VT-112 VrT-112 VT-112 MethodlSheet/Results VT 05GV275 Accept VT 05GV276 Accept VT 05GV376 Accept

=

System CONTAINMENT CONTAINMENT CONTAINMENT Comments:

05-VT: Prior to paint/coating removal - East of Pen 29, at Pen 29, & West of Pen 29. Rust, Flaking & Peeling paint were noted.

1906001 P29 Area Applied Paint/Coating E-PC PC-2 VT-112 VT-1 12 VT-112 VT 05GV397 Accept VT 05GV380 Accept VT 05GV396 Accept CONTAINMENT CONTAINMENT CONTAINMENT Comments:

05-VT: Water Noted on floor inside Pen 29 Cubical - No Recordable Indications for the remainder area - Acceptable..

Attachment IC Page I of 2 Inservice Inspection Report First Interval (I 997-2008), Second Period, Third Outage (2005) - IWE/IWL I.

Owner:

R. E. Ginna Nuclear Power Plant, L.TC. 1503 Lake Road, Ontario New York 14519

2.

Plant:

R. E. Ginna Nuclear Power Plant, 1503 l.ake Road, Ontario New York 14519

3.

Plant Unit:

I

4.

Owner Certificate of Authorization (If Req.) NIA

5.

Commercial Service Date:

7/01/1970

6.

National Board Number for Unit:

N/A 2005 Class MC Appendix J Components:

Summarv No.

1904300 Component ID Pen. AE-1 AE-2, AE-3 AE-4, AE-5 AE-6, AE-7 AE-8, AE-9 AE-10,AE-11 AE-12, AE-13 AE-14 Component Description Electrical Manifold 111, PT-22.20 Category E-P Item No.

E9.40 Iso Dwe Number Method:

Comments:

Appendix I Test - Accept.

0.0 SCCM-Passed. See Record Category 1.0 for completed PT Appendix J Test Results Summary No.

Component ID Component Description Categorv Item No.

Iso DwP Number 1904300 Pen. 2 S/G Communication Flange E-P E9.40 (Inside), PTT-23.53.1 Method:

Appendix J Test - Accept.

Comments:

4.0 SCCM-Passed. See Record Category 1.0 for completed PTT Appendix J Test Results Summara No.

Component ID Component Description Categorv Item No.

Iso Dwg Number 1904300 Pen. 2 S/G Communication Flange E-P E9.40 (Outside), PTT-23.53.2 Method:

Appendix J Test - Accept.

Comments:

10.0 SCCM-Passed. See Record Category 1.0 for completed PTT Appendix J Test Results Summary No.

Component ID Component Description Categorv Item No.

Iso Dwe Number 1904300 Pen. 29 Fuel Transfer Flange, PTT-23.54 E-P E9.40 Method:

Appendix J Test -Accept.

Comments:

0.0 SCCM-Passed. See Record Category 1.0 for completed PTT Appendix J Test Results Summarv No.

Component ID Component Description Catepory Item No.

Iso Dwg Number 1904300 Pen. 204 Purge Supply Flange, PTT-23.35.1 E-P E9.40 Method:

Appendix J Test - Accept.

Comments:

2.0 SCCM-Passed. See Record Category 1.0 for completed PTT Appendix J Test Results Summarv No.

Component ID Component Description Category Item No.

Iso Dwe Number 1904300 Pen. 300 Purge Exhaust Flange, PTT-23.36.1 E-P E9.40 Method:

Appendix J Test - Accept.

Comments:

0.0 SCCM-Passed. See Record Category 1.0 for completed PTT Appendix J Test Results

Attachment IC Page 2 of 2 Inservice Inspection Report First Interval (1997-2008), Second Period, Third Outage (2005) - IWEAIWL

1.

Owner:

R. F. Ginn

2.

Plant:

R. E. Ginn

3.

Plant Unit:

I

4.

Owvner Certificate of Authorization (If Req.) N/A

5.

Commercial Service Date:

7/01/1970

6.

National Board Number for Unit:

N/A a Nuclear Power Plant LLC. 1503 Lake Road. Ontario New York 14519 a Nuclear Power Plant. 1503 Lake Road. Ontario New York 14519 2005 Class MC Appendix J Components:

Summary No.

1904300 Component ID Pen. 1000 Component Description Personnel Hatch Door Seal, PT-22.2 Cateeorv E-P Item No.

E9.40 Iso Dwg Number Method:

Comments:

Appendix J Test - Accept.

Inner Door - 65.0 SCCM, Outer Door- 0.0 SCCM, -Passed. See Record Category 1.0 for completed PT Appendix J Test Results Summary No.

Component ID Component Description Category Item No.

Iso Dwe Number 1904300 Pen. 2000 Equipment Hatch O-Ring, E-P E9.40 PT-22.7 Method:

Appendix J Test - Accept.

Comments:

740.0 SCCM-Passed. See Record Category 1.0 for completed PT Appendix J Test Results Summarv No.

Component ID Component Description Cateeory Item No.

Iso Dwc Number 1904300 Pen. 2000 Equipment Hatch Door Seal, E-P E9.40 PT-22.1 Method:

Appendix J Test - Accept.

Comments:

Inner Door - 750.0 SCCM, Outer Door - 740.0 SCCM, -Passed. See Record Category 1.0 for completed PT Appendix J Test Results

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II ASME Section XI Repair and Replacement Program Report (NIS-2) i

APPENDIX 11-MANDATORY Form NIS-2 FORM NIS-2 OWN'ER'S REPORT FOR REPAIR/REPLACEAMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner R. E. Ginna Nuclear Power Plant. LLC Name Date 16 June 2005 1...3 Lake R.ad. Ontari,. New.. rk 14.19 Sheet 1

of 29 Address

2. Plant R. F. (inna Nuclear Power Plant Name Unit 1

1503 Lake Rnad. Ontario, NY 14519 Address

3. Work Performed by (k)

Name

( ).

Address Repair/Replacement Organization P.O. No, Job No, etc.

Type Code Symbol Stamp Authorization No.

rrn;"ntsn nlte I

N/A N/A N/A

^Sm H

o

4. Identification ofSystem

(*I

5. (a) Applicable Construction Code

()

.19 (J*)Edition, (*_)

Addenda l

Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1995 Edition, 1996 Addenda (Class 1.23)

.1992 Edition. 1992 Addenda IWFVF/lQ __

6. Identification of Components ASNIE Corrected, Code Name of Name of Manufacturer National Other Year Removed, or Stamped Component Manufacturer Serial No.

Board Identification Built Installed (Yes No.

or No)

(*

(*

(*

(*

(*

(*N*

7. Description of Wor k 1*1

8. Tests Conducted: (*)

HydrostaticO PneumaticO OtherO Pressure psi Nominal Operating PressureO Test Temp.

F Exempt]

Note: Supplemental sheets in form of list, sketches, or drawings may be used, provided (I) size is 81/2 in. x II In, (2) Information In items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of the sheets is recorded at the top of this form.

(*) See "Attachment II" for Applicable Information This Form (E00030) may be obtained from the ASME Order Dept, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300

1995 SECTION XI - Division I Page 2 FORM NIS-2 (Back)

Remarks Application Manufacturer's Data Report to be attached CERTIFICATE OF COMPLAINCE I certify that the statements made in the report are correct and that this conforms to the requirements of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Certificate of Authorization No.

N/A Expiration Date N/A Signed

'A L

5 t

)

Date 16 June

.2005 Frank A. Klepacki - ISIEngineer Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspection and the State or Province of N/A and employed by ABS of

Houston, TX have inspected the components described in this Owner's Report during the period 12/0212003 to 6/1612005 and state that to the best of my knowledge and belief, the Owner has performed examination and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examination 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.

+

2

°.

Commissions NB10195

/M:Z.

C~fispector's Signature National Board. State, Province, and Endorsements Date 20 Pi

(*) See "Attachment II" for Applicable Information

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Rcport Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Ow ner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IST) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II REPAIR, REPLACEMENT and MODIFICATION PROGRAM The Repair and Replacement (R&R) Program, as identified within the "Fourth Interval Inservice Inspection (ISI) Program", identifies component jurisdiction and associated requirements. Applicable Repair or Replacement activities have been performed in accordance with ASME Section XI Code, 1995 Edition, 1996 Addenda or the 1992 Edition with 1992 Addenda for IWE/IWL (Containment).

When an item under the rules and requirements of the "Inservice Inspection (ISI)

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 or Replacement; 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 R&R 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 have additional expanded examinations performed, as required. The associated expanded examinations shall be performed in accordance to the requirements of ASME Section XI Code.

A "Code Rejectable Indication" occurs when a component under the R&R 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 replacement activity identified during ISI preservice examinations or component damage caused by human involvement.

3

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario, N.Y. 14519

2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3.

Applicable Edition of Section Xl Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (WEll WL Containment)

ATTACHMENT II A "Corrective Action Activity" may occur when a component under the R&R Program requires corrective action. This corrective action may be a result from a maintenance operation that identifies a need to perform a Code Repair or Replacement. 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 or Replacement activities. Each group is identified by a number, and the number will correspond to the groups' name and address. In the below listing of Code Repairs or Replacements; the work group will be identified by a number within the component discussion.

1.

R. E. Ginna Nuclear Power Plant, LLC

4.

Southeast Valve Inc.

1503 Lake Road PO Box 7850 Ontario, NY 14519 Charlotte, NC 28241

2.

The Atlantic Group, Inc.

5426 Robin Hood Rd.

Norfolk, Va. 23513

3.

Portersville Valve Co.

PO Box 89 Portersville, PA. 16051 The following information will report applicable Repairs or Replacements performed at R. E.

Ginna Nuclear Power Plant during this reporting period as required by ASME Section XI Code. It should be noted that the first two numbers contained within the "GORR Number" identifies the outage number and not the year of the outage.

4

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT It

1.

ASME Class: 2 System: RHR GORR No.: 3 1-001 Line: 10" Category: Corrective Action Activity Construction Code: ASME III NF '74/'95/'96, EWR-2512, ME-318 Work Performed Bv: 1 Name of Component: Component Support RHU-75 Modification Work Description/Remarks: A Section XI Code replacement activity was initiated to extend the support base plate and install new hilti bolts. This activity was controlled by WO #

20300818, TE 2003-0035 & Action Report 2003-0614. Upon completion of this code activity, construction code VT and MT examinations were performed and acceptable.

ASME Section XI VT baseline examination was performed and acceptable. See NDE Summary # R03010 and I131710.

2.

ASME Class: 3 System: CCW GORR No.: 31-002 Line: 1 I/2" Category: Code Service Induced Rejectable Indication Construction Code: ASME III '92/'95/'96 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-1 Name of Component: Repair of Fillet Weld by V775C Work Description/Remarks: A Section XI Code activity was initiated to repair by metal removal a weld defect on a 1 1/2" line by Valve 775C. This activity was controlled by WO #

20300658 & Action Report 2003-0491. Upon completion of a code repair, construction code VT examination was performed and acceptable. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05002.

3.

ASME Class: 2 System: CVCS GORR No.: 31-003 Component: PCHO1C Category: Corrective Action Activity Construction Code: ME-318, Westinghouse G-676370, ASME III '65/'86/'92/'95/'96.

Work Performed By: 1 Code Case/Relief Reguest: Code Case N-416-1 Name of Component: Valve Seat on "C" Charging Pump.

Work Description/Remarks: A Replacement activity was initiated to remove and install two (2) valve seats on the "C" Charging Pump. This activity was controlled by Work Order #

20303459 and Action Report Number 2003-3371. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05050.

5

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

4.

ASME Class: 2 Svstem: CVCS GORR No.: 31-004 Component: PCHOIA Category: Corrective Action Activity Construction Code: ME-318, Westinghouse G-676370, ASME III '65/'86/'92/'95/'96.

Work Performed By: 1 Code Case/Relief Request: Code Case N-416-1 Name of Component: Valve Seat on "A" Charging Pump.

Work Description/Remarks: A Replacement activity was initiated to remove and install six (6) valve seats on the "A" Charging Pump. This activity was controlled by Work Order #

20400470 and Action Report Number 2004-0227. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05046.

5.

ASME Class: 3 System: DG GORR No.: 31-005 Line: 2 I/2" Category: Corrective Action Activity Construction Code: B31.1 1955, B16.34, ASME III '92/'95/'96 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-1 Name of Component: Relief Valve 5989 Mechanical Replacement Work Description/Remarks: A Section XI Code like-for-like replacement activity was initiated to perform a mechanical replacement of relief valve 5989. This activity was controlled by WO # 20400965. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05004.

6.

ASME Class: 3 System: AFW GORR No.: 31-006 Component: PAF01B Category: Corrective Action Activity Construction Code: Westinghouse G-676262, Gilbert SP-529 1, B31.1 1955, ME-318, ASME III '92/'95/'96 Work Performed By: 1 Name of Component: AFW Pump "B" Suction Flange Bolting Replacement Work Description/Remarks: A Like for Like replacement activity was initiated to install new suction flange bolting on the Auxiliary Feed Water Pump "B". This activity was controlled by WO # 20302896.

6

R. E. GINNA NUCLEAR POWER PLANT Inscrvice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Pcriod, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

7.

ASME Class: 2 System: SI GORR No.: 31-007 Component: PSIOIB Category: Corrective Action Activity Construction Code: Westinghouse G-676262, Gilbert SP-5291, B31.1 1955, ME-318, ASME III '92/'95/'96 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-1 Name of Component: SI Pump "B" Suction Flange Bolting Replacement Work Description/Remarks: A Like for Like replacement activity was initiated to install new 4" suction flange bolting on the Safety Injection Pump "B". This activity was controlled by WO # 20300864. An ASME Section XI VT-2 Leakage examination was performed and acceptable but was not required. See NDE Summary # R05007.

8.

ASME Class: 3 System: SFPC GORR No.: 31-008 Component: EAC14 Category: Corrective Action Activity Construction Code: Gilbert SP-5291, ASME VIII '92, NBIC '92, ASME III '92/'95/'96, ME-318 Work Performed Bv: 1 Code Case/Relief Request: Code Case N-416-1 Name of Component: Spent Fuel Pool Heat Exchanger shell coupling (2 l2") and associated pipe insert (2") Replacement Work Description/Remarks: A replacement activity was initiated to install a new 2 l2" shell coupling and a 2" pipe insert associated with the Spent Fuel Pool Heat Exchanger EAC 14.

This activity was controlled by WO # 20402451 & PCR 2004-0027. Construction Code MT and VT examinations were performed on associated required root and final welds and acceptable. An ASME Section XI VT-2 Leakage examination was performed and acceptable.

See NDE Summary # R05008.

7

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IVL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (I WE/IWL Containment)

ATTACHMENT II

9.

ASME Class: 2 System: CS GORR No.: 31-009 Component: PSI02B Category: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 1955, ME-318, ASME III '95/'96 Work Performed By: I Name of Component: CS Pump "B" Discharge Flange Bolting Replacement Work Description/Remarks: A Like for Like replacement activity was initiated to install new discharge flange bolting on the Containment Spray Pump "B". This activity was controlled by WO # 20401581 and Action Report 2004-0706.

10.

ASME Class: 2 System: CVCS GORR No.: 31-O1OA/B Component: V296, CVU-63 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Associated 2" piping and Valve 296 Replacement. Removed and reinstall Component Support CVU-63 by welding to obtain access to Valve 296.

Work Description/Remarks: A Like for Like replacement activity was initiated to install new 2" piping and valve 296. Component Support CVU-63 was removed and reinstalled by welding to obtain access to valve 296. This activity was controlled by WO # 20302819.

Construction Code PT and VT examinations were performed and acceptable on piping welds. Construction Code VT examination was performed and acceptable on the support welds. ASME Section XI baseline component support VT examination and a VT-2 Leakage examination on piping welds were performed and acceptable. See NDE Summary # R05024.

11.

ASME Class: 1 System: RCS GORR No.: 31-011 Line: 29" Category: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair-Reapplication of Seal Weld associated with TE-401A.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with TE-401A replacement. This activity was controlled by WO #

20500374, TSR 2005-0032 & TE-97-006. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary #

R05028.

8

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

12.

ASME Class: 1 System: RCS GORR No.: 31-012 Line: 29" Category: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Reapplication of Seal Weld associated with TE-408A.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with TE-408A replacement. This activity was controlled by WO #

20302867, TSR 2005-0032 & TE-97-006. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary #

R05030.

13.

ASME Class: 1 System:RCS GORRNo.:31-013 Line: 29" Category: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Reapplication of Seal Weld associated with TE-402A.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with TE-402A replacement. This activity was controlled by WO #

20401588, TSR 2005-0032 & TE-97-006. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary #

R05029.

14.

ASME Class: 3 System: SW GORR No.: 31-014 Component: Valve 4734 Categorv: Corrective Action Activity Construction Code: Westinghouse Specification G-676262, Gilbert SP-5291, B31.1 1955, ME-318, ASME III '95/'96 Work Performed By: 3 Name of Component: Valve 4734 Flange Bolting Replacement Work Description/Remarks: A Like for Like replacement activity was initiated to install new flange bolting associated with 14" Valve 4734. This activity was controlled by WO #

20203789 and Action Report 2004-1604.

9

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEJIWVL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IST) or 1992 Edition with 1992 Addenda (IWElIWL Containment)

ATTACHMENT II

15.

ASME Class: 3 System: SW GORR No.: 31-015 Line: 2 l/2" Category: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 '55, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Valve 4624 Replacement.

Work Description/Remarks: A Like for Like replacement activity was initiated to install a new 2 I2" valve 4624. This activity was controlled by WO # 20302590. Construction Code MT and VT examinations were performed and acceptable. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05039.

16.

ASME Class: 3 System: AFW GORR No.: 31-016 Component: PAFOlA, PAFOiB Category: Corrective Action Activity Construction Code: EWR-2512, B331.1 '67/'73, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Flange Bolting and 2" Recirculation Piping on AFW Pumps "A" &

"B" Replacement.

Work Description/Remarks: A Like for Like replacement activity was initiated to install new flange bolting and 2" recirculation piping on AFW Pumps "A" and "B". This activity was controlled by WO # 20403110, 20400903 and PCR 2003-0043. Construction Code VT examinations were performed and acceptable. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary #'s R05017 & R05018.

17.

ASME Class: 3 System: SW GORR No.: 31-017 Component: 4620 Category: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 '55, ASME III '95/'96, ME-318 Work Performed By: 1 Name of Component: Flange Bolting Replacement on Valve 4620.

Work Description/Remarks: A Like for Like replacement activity was initiated to install new 7/8" flange bolting on 14" Valve 4620 one at a time. This activity was controlled by WO #

20403212 and Action Report 2004-1859.

10

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

18.

ASMEClass:3 System: SW GORRNo.:31-018 Component: V4620, SWU-164 Category: Corrective Action Activity Construction Code: Gilbert SP-5291, EWR-2512, B31.1 '55, ASME III '92/'95/'96, ASME IIINF '74, ME-318, ME-121 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: 10"/14" piping replacement downstream of Valve 4620 & re-atachment of Integral Attachment associated with component support SWU-164.

Work Description/Remarks: A replacement activity was initiated to install new 10" and 14" piping downstream of Valve 4620 and the re-attachment of integral attachment associated with component support SWU-164. This activity was controlled by WO # 20403212, TE 2000-0047 and Action Report 2001-1205. Construction Code VT and RT examinations were performed and acceptable on piping welds. Construction Code VT examination was performed and acceptable on the integral attachment associated with component support SWU-164. ASME Section XI baseline component support VT examination and integral attachment examination was performed under ISI Summary Number I501660 & I501665.

ASME Section XI VT-2 Leakage examination on piping welds were performed and acceptable. See NDE Summary # R05033.

19.

ASME Class: 2 System: CVCS GORRNo.: 31-019 Component: PCHOlB Category: Corrective Action Activity Construction Code: ME-318, Westinghouse G-676370, ASME III '65/'86/'92/'95/'96.

Work Performed By: 1 Code Case/Relief Reguest: Code Case N-416-1 Name of Component: Valve Seat on "B" Charging Pump.

Work Description/Remarks: A Replacement activity was initiated to remove and install valve seats on the "B" Charging Pump. This activity was controlled by Work Order #

20403564 and Action Report Number 2004-2174. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R0505 1.

11

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEJIWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IST) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

20.

ASME Class: 2 System: CVCS GORR No.: 31-020 Component: FE 11 6A Categorv: Corrective Action Activity Construction Code: Westinghouse G-676262. Gilbert SP-5291, B31.1 '55, ASME III '92f'95/'96, ME-318 Work Performed By: 1 Name of Component: Flange Bolting Replacement on FE 11 6A.

Work Description/Remarks: A Like for Like replacement activity was initiated to install new flange bolting on FE 11 6A. This activity was controlled by WO # 20400186 and Action Report 2004-0128.

21.

ASME Class: 3 System: SW GORRNo.: 31-021 Component: SWU-531, SWU-582 Categorv: Corrective Action Activity Construction Code: EWR-2512, ASME III NF '74, ME-318, ME-121 Work Performed By: 1 Name of Component: Nut Replacement on Component Supports SWU-531 & SWU-582.

Work Description/Remarks: A Like for Like nut replacement activity was initiated to install new nuts on Component Supports SWU-531 & SWU-582. This activity was controlled by WO # 20401904. VT examinations were performed and acceptable. See NDE Summary #'s R05012 & R05013.

22.

ASME Class: 1 System: CVCS GORR No.: 31-022/022A Component: V9314 Categorv: Code Rejectable Indication Construction Code: Westinghouse G-676343, G-676496; EWR-2512, B3 1.1 '67/'73, ASME III '95/'96, ME-318 Work Performed By: 1 Name of Component: Repair Seal Weld on Valve 9314 and installation (Replacement) of 27" drain line..

Work Description/Remarks: A Repair activity was initiated to reapply a Seal Weld on Valve 9314 and a Replacement activity to install a /27" drain line due to a gasket leak. This activity was controlled by WO # 20403953, Action Report 2004-2510, TE 2004-0030 and TM 2004-0013. Construction Code PT and VT examinations were performed and acceptable. See NDE Summary # R05014.

12

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEJIWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

23.

GORRNo.:

31-023 Cancelled

24.

ASME Class: 1 System: CVCS GORR No.: 31-024 Component: V9315 Categorv: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Seal Weld Valve 9315.

Work Description/Remarks: A Section XI Code Repair activity was initiated to Seal Weld 2" Valve 9315. This activity was controlled by WO # 20403951, TE 2004-0030 and Action Report 2004-25 10. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary # R05015.

25.

ASME Class: 3 System: DG GORR No.: 31-025 Component: V 5990 Categorv: Corrective Action Activity Construction Code: B31.1 '55, B16.34, ASME III '92/'951'96, ME-318 Work Performed Bv: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Relief Valve 5990 Replacement.

Work Description/Remarks: A Like for Like replacement activity was initiated to install a 2 A2" reliefvalve 5990 by mechanical means. This activitywas controlled byWO #20401007.

ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05052.

26.

ASME Class: 3 System: DG GORR No.: 31-026 Component: V 5959 Category: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 '55, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Relief Valve 5959 Replacement.

Work Description/Remarks: A Like for Like replacement activity was initiated to install a 1

'2" relief valve 5959 by mechanical means. This activity was controlled by WO # 20401005.

ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05053.

13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISl) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

27.

GORR No.:

31-027 Cancelled

28.

ASME Class: 1 System: RHR GORR No.: 31-028 Line:

3/4" Categorv: Corrective Action Activity Construction Code: Westinghouse G-676343, G-676496; B31.1 '55, B16.5, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace %" line Flange & 3/8" Connection downstream of Valve 852C.

Work Description/Remarks: A Like for Like replacement activity was initiated to install a 3" line Flange and 3/8" connection downstream of Valve 852C. This activity was controlled by WO # 20303108. Construction Code VT and PT examinations were performed and accepted. ASME Section XI VT-2 Leakage examination was performed and acceptable under PT-7 but was not required by code. See NDE Summary # R05021.

29.

GORR No.:

31-029 Cancelled

30.

ASME Class: 2 System: CCW GORR No.: 31-030 Component: LACOI, V2752, V2753 Category: Corrective Action Activity Line: 4", 3" & 2" (Flange Bolting)

Construction Code: Gilbert SP-5291, B31.1 '55, ASME III '95/'96, ME-318 Work Performed By: 1 Name of Component: Flange Bolting Replacement on LACO 1, V2752, V2753 and 4", 3", &

2" Flanges.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install new flange bolting on component LACO 1, Valve 2752, Valve 2753 and 4", 3" and 2" Flanges. This activity was controlled by WO # 20403934.

31.

GORR No.:

31-031 Cancelled 14

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IST) or 1992 Edition with 1992 Addenda (IWEIWL Containment)

ATTACHMENT II

32.

ASME Class: 2 System: RHR GORR No.: 31-032 Component: FE 672 Categorv: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 '55, ASME III '95/'96, ME-318 Work Performed By: 1 Name of Component: Bolting Replacement on FE 672.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install new bolting on FE 11 6A. This activity was controlled by WO # 20402941.

33.

ASME Class: 2 System: SW GORR No.: 31-033 Component: V4619 Categorv: Corrective Action Activity Construction Code: Gilbert SP-5291, B31.1 '55, ASME III '95/'96, ME-318 Work Performed By: 1 Name of Component: Bolting Replacement on Valve 4619.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install new bolting on 14" Valve 4619. This activitywas controlled byWO #20403055 and Action Report 2004-1859.

34.

ASME Class: 2 System: CVCS GORR No.: 31-034A Component: CVU-414, CVU-415 Categorv: Corrective Action Activity Construction Code: EWR-2512, ASME IIINF '74, ME-318, ME-121 Work Performed By: 1 Name of Component: Nut Replacement on Component Supports CVU-414 & CVU-415.

Work Description/Remarks: A Like for Like nut replacement activity was initiated to install new nuts on Component Supports CVU-414 & CVU-415. This activity was controlled by Action Report 2004-1070 and WO #'s 20401160 & 20402269. ASME Section XI baseline VT examinations were performed and acceptable. See ISI Summary #'s I077800 & I077900.

15

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWVL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (1S1) or 1992 Edition with 1992 Addenda (TWEIVWL Containment)

ATTACHMENT II

35.

ASME Class: 2 Svstem: CVCS GORR No.: 31-035 Component: V294, CVU-59 Categorv: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, ASME III '92/'95/'96, ASME III NF '74, ME-318, ME-121 Work Performed By: 2 Name of Component: Replacement of Hilti Bolting on CVU-59 and Bonnet, Cage & Plug on V294.

Work Description/Remarks: A Like for Like replacement activity was initiated to install new hilti bolting on Component Supports CVU-59 which had its base plate rotated. Also, Valve 294 had its bonnet, cage and plug replaced. This activity was controlled by Action Report 2004-3027 and WO # 20404087. ASME Section XI VT-2 leakage examination was performed and acceptable. ASME Section XI baseline VT examination was performed and acceptable. See ISI Summary # I050966 & NDE Summary # R05048.

36.

ASME Class: 1 System: RC GORR No.: 31-036 Component: V509, V51 1, V534, V952 Category: Corrective Action Activity Construction Code: ASME III '92/'95/'96, Work Performed BY: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Repair undersize welds on 3/" line for valves 509, 511, 534 & 952.

Work Description/Remarks: A Repair activity was initiated to address undersize 3/" line welds on Valves 509,511,534 and 952. This activity was controlled by Action Report 2003-2566 and WO # 20303256. Construction Code VT and PT examinations were performed and acceptable. ASME Section XI VT-2 leakage examination was performed and acceptable.

See NDE Summary # R05041.

37.

ASME Class: 3 System: MS GORR No.: 31-037 Component: V3519 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '95/'96, ME-318 Work Performed By: 2 Name of Component: Disc Pin Replacement on Valve 3519.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install a new disc pin on 30" Valve 3519. This activity was controlled by WO # 20302604.

16

R. E. GINTNA NUCLEAR POWVER PLANT Inservicc Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWVE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS1) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

38.

ASME Class: 3 System: SW GORR No.: 31-038 Component: V4579, V4579A, V4579B Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.15, ASME III '921'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace Valves 4579, 4579A, 4579B & associated I 2A" Piping.

Work Description/Remarks: A Replacement activity was initiated to install valves 4579, 4579A, 4579B and associated 1 l/2" copper Piping. This activity was controlled by Action Reports 2004-0452, 2004-3256, 2004-3224, TE 2004-0036 and WO # 20400943.

Construction Code VT examinations were performed and acceptable. ASME Section XI VT-2 leakage examination was performed and acceptable. See NDE Summary # R05016.

39.

ASME Class: 3 Svstem: AFW GORR No.: 31-039 Component: PAFOlA Category: Corrective Action Activity Construction Code: WorthingtonPumpVM-W318-0017, Gilbert BM-22698, ASME I '74 Work Performed By: 1 Name of Component: Installation of Copper Washers on AFW Pump "A" Casing Studs.

Work Description/Remarks: A mechanical replacement activity was initiated to install copper washers on the casing studs on the Auxiliary Feed Water Pump "A" (PAF01 A). This activity was controlled by WO # 20402407 and Action Report 2004-1137. ASME Section XI VT-2 leakage examination was performed and acceptable. See ISI Summary # I411700.

40.

ASME Class: 3 System: SFP GORR No.: 31-040 Component: PAC07B Category: Corrective Action Activity Construction Code: EWR-1594, ASME III '77/'78/'951'96, ME-318 Work Performed By: 1 Name of Component: Flange Bolting Replacement on Spent Fuel Pool Recirculation Pump "B".

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install new flange (8" & 6") bolting on the Spent Fuel Pool Recirculation Pump "B". This activity was controlled by WO # 20403802.

17

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IVE/IWL

1. Owvner: R. E. Ginna Nuclear Power Plant.LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

41.

ASME Class: 3 System: MS GORR No.: 31-041 Component: V8527 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '55, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: I Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace Valve 8527 Work Description/Remarks: A Like for Like Replacement activity was initiated to install a new 1 %2" valve 8527. This activity was controlled by Action Report 2004-2001 and WO #

20403323. Construction Code VT examinations were performed and acceptable. ASME Section XI VT-2 leakage examination was performed and acceptable. See NDE Summary #

R05019.

42.

ASME Class: 2 System: FW GORR No.: 31-042/042A Component: V3993 Category: Corrective Action Activity Construction Code: B31.1 '55, ASME III '95/'96, Work Performed By: 4 Name of Component: Repair of Valve Body Base Metal, Disc and Guides Hardfacing of Valve 3993.

Work Description/Remarks: A Repair activity was initiated to weld repair the valve body base metal and hardfacing of the disc and guides associated with the 14" valve 3993. This activity was controlled by WO # 20400503. Construction Code VT and PT examinations were performed on the valve body and acceptable. Construction Code VT and PT examinations were performed on the hardfaced disc and guides and acceptable. See NDE Summary # R05043.

43.

ASME Class: 1 System: CVCS GORR No.: 31-043 Component: V9315 Cateaorv: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Seal Weld on Valve 9315.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with a 2" Valve 9315. This activity was controlled by WO # 20402897 and TE 2004-0030. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary # R05032.

18

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - I'WE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: RE. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

44.

ASME Class: 1 System: CVCS GORR No.: 31-044 Component: V9314 Category: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Seal Weld on Valve 9314.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with a 2" Valve 9314. This activity was controlled by WO # 20404124 and TE 2004-0030. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary # R0503 1.

45.

ASME Class: 1 System: CVCS GORR No.: 31-045 Component: V295 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace Valve 295 & associated 2" piping.

Work Description/Remarks: A Code Replacement activity was initiated to install a new 2" valve 295 with associated piping. This activity was controlled by Action Report 2004-2728, TE 2005-0005 and WO # 20404094. Construction Code VT and PT examinations were performed and acceptable. ASME Section XI VT-2 leakage examination was performed and acceptable. See NDE Summary # R05034. ASME Section XI baseline PT examinations were performed and acceptable.

See ISI Summary #'s I050750, I 050800, I050885 &

I050888.

46.

ASME Class: 2 System: FW GORR No.: 31-046/046A Component: V3992 Category: Corrective Action Activity Construction Code: B31.1 '55, ASME III '95/'96, Work Performed By: 4 Name of Component: Repair of Valve Body Base Metal & Hardface Disc on Valve 3992.

Work Description/Remarks: A Repair activity was initiated to weld repair the valve body base metal and hardfacing of the disc associated with the 14" valve 3992. This activity was controlled by WO # 20400502. Construction Code VT and PT examinations were performed on the valve body and acceptable. Construction Code PT examination was performed on the hardfaced disc and acceptable. See NDE Summary # R05036.

19

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

47.

ASME Class: 2 System: RHR GORR No.: 31-047 Component: PACOIB Category: Corrective Action Activity Construction Code: ASME III '65 Work Performed By: 1 Name of Component: Repair of RHR Pump "B" Gland by Machining & inserting a Y2" Tap within the Pump Casing.

Work Description/Remarks: A Repair activity was initiated to machine a Gland and relocating an l/2" tap hole within the pump casing. This activity was controlled by WO #

20404459 and TE 2004-0136. Construction Code VT and PT examinations were performed on the valve body and acceptable. Construction Code PT examination was performed on the hardfaced disc and acceptable. See NDE Summary # R05036.

48.

ASME Class: 2 System: RHR GORR No.: 31-048 Component: RHU-92 Category: Corrective Action Activity Construction Code: EWR-2512, ASME IIINF '74, MSS SP-58 Work Performed BY: 1 Name of Component: Snubber Replacement on Component Support RHU-92 Work Description/Remarks: A Like for Like Replacement activity was initiated to install a new Snubber for Component Support RHU-92 located on a 6" line. This activity was controlled by WO # 20501165. ASME Section XI VT baseline examination was performed and acceptable. See ISI Summary # I130150 & I601800.

49.

ASME Class:I System: RCS GORRNo.: 31-049 Component: PRCOIA, PRCOIB Categoly: Corrective Action Activity Construction Code: EWR-2512, ASME III NF '74/'86/'95/'96 Work Performed By: 1 Name of Component: Support Replacement on Reactor Coolant Pump "A" & "B" Work Description/Remarks: A Replacement activity was initiated to modify the supports on the Reactor Coolant Pumps ("A" & "B") by adding welded gussets to the existing base plate and "I" beam. This activity was controlled by WO # 20402521 and PCR 2004-0030.

Construction Code VT and MT examinations were performed and acceptable. See NDE Summary # R05027. ASME Section XI VT baseline examinations were performed and acceptable. See ISI Summary #I057310,I057320, I057330,I058130,I058140 & 1058150.

20

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3. Applicable Edition of Section Xl Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

50.

ASME Class: 2 System: RHR GORR No.: 31-050A/B Component: V856, RHU-79 Category: Corrective Action Activity Construction Code: EWR-2512, ASME III NF '74/'95/'96, ASME m '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Repair by Seal Welding Valve 856, Removal & Reinstallation of Component Support RHU-79 by welding to obtain access to Valve 856.

Work Description/Remarks: A Repair activity was initiated to seal weld 10" Valve 856. A Replacement activity was also performed to remove and reinstall by welding Component Support RHU-79 that was needed to be removed to gain access to Valve 856. This activity was controlled by WO # 20501522 and Action Report 2005-0788. Construction Code PT and VT examinations were performed and acceptable on the seal weld. Construction Code VT examination was performed and acceptable on the support welds. ASME Section XI baseline component support VT examination was performed and acceptable under ISI Summary # 1130450. An ASME Section XI VT-2 Leakage examination was performed and acceptable but not required. See NDE Summary # R05022.

51.

ASME Class: 1 System: CVCS GORR No.: 31-051 Component: ECH03 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '55, ASME III '92/'95/'96, ME-318 Work Performed By: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace 3/4" Coupling on Excess Letdown Heat Exchanger (ECH03)

Line.

Work Description/Remarks: A Code Replacement activity was initiated to install a new coupling on a 3/4" Excess Letdown Heat Exchanger Line. This activity was controlled by WO # 20401573 and DBCOR 2005-0007. Construction Code VT and PT examinations were performed and acceptable. ASME Section XI VT-2 Leakage examination is not required but was performed and acceptable under PT-7. See NDE Summary # R05026.

21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

52.

ASME Class: 2 Svstem: RHR GORR No.: 31-052 Component: EAC02A, EAC02B Category: Code Rejectable Indication Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Grind Repair of Outlet Reinforcing Plate Weld (ORPRHE-lA) on EAC02A and Inlet Reinforcing Plate Weld (IRPRHE-IB) on EACO2B.

Work Description/Remarks: A Section XI Code activity was initiated to repair by metal removal original fabrication weld defects. On RHR Heat Exchanger "A" (EAC02A), the Outlet Reinforcing Plate Weld (ORPRHE-1A) was repaired by metal removal. On RHR Heat Exchanger "B" (EACO2B), the Inlet Reinforcing Plate Weld (IRPRHE-lB) was repaired by metal removal. This activity was controlled by WO # 20400669 & Action Reports 2005-1040 and 2005-1039. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary # R05023. ASME Section XI baseline PT examinations were performed and acceptable. See ISI Summary #'s I169090

& I169270.

53.

ASME Class: 2 System: RHR GORR No.: 31-053 Component: RHU-68 Category: Corrective Action Activity Construction Code: EWR-2512, ASME III NF '74/'95/'96 Work Performed By: 1 Name of Component: Replacement of Spring Can and Base Plate on Component Support RHU-68 Work Description/Remarks: A Replacement activity was initiated to install a new Spring Can and Base Plate on Component Support RHU-68 located on a 10" line. This activity was controlled byWO # 20400108, Action Report 2003-0662 and TE 2005-0018. Construction Code VT examination was performed and acceptable. See NDE Summary # R05035. ASME Section XI VT baseline examination was performed and acceptable. See ISI Summary #

1137800.

22

R. E. GINTNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

54.

ASME Class: 1 System: RCS GORR No.: 31-054 Line: 27.5" Category: Corrective Action Activity Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Repair - Reapplication of Seal Weld associated with TE-404B.

Work Description/Remarks: A Section XI Code Repair activity was initiated to re-apply a Seal Weld associated with TE-404B replacement. This activity was controlled by WO #

20501528, TSR 2005-0032,94-031 & 93-058. Upon completion of a code repair, construction code VT and PT examinations were performed and acceptable. See NDE Summary # R05030.

55.

GORRNo.:

31-055 Cancelled

56.

ASME Class: 1 Svstem: PZR GORR No.: 31-056 Component: TRC01 Category: Code Rejectable Indication Construction Code: ASME III '95/'96 Work Performed BY: 1 Name of Component: Grind Repair of Pressurizer Nozzle to Safe End Weld SLNSE.

Work Description/Remarks: A Section XI Code activity was initiated to repair by metal removal original fabrication weld defects on the Pressurizer Nozzle to Safe End Weld SLNSE. This activity was controlled by WO # 20501863 & Action Report 2005-1405. Upon completion of a code repair, construction code PT examination and UT thickness readings were performed and acceptable. See NDE Summary # R05037. ASME Section XI baseline PT examination was performed and acceptable. See ISI Summary #'s I004350.

57.

ASME Class: 1 System: RCS GORR No.: 31-057 Component: EMSO1A Categorv: Corrective Action Activity Construction Code: ASME III '86 Work Performed By: 1 Name of Component: Steam Generator "A" Primary Manway Stud Replacement.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install two (2) new studs on Steam Generator "A" (EMS0IA) Primary Manway. This activity was controlled by WO # 20400869. ASME Section XI baseline VT examination was performed and acceptable. See Summary # M100080.

23

R. E. GINNA NUCLEAR PONVER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1.

Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISD) or 1992 Edition with 1992 Addenda (IWWE/IWL Containment)

ATTACHMENT II

58.

ASME Class: 2 System: MS GORR No.: 31-058 Component: EMSO1A Category: Corrective Action Activity Construction Code: ASME III '86 Work Performed Bv: 1 Name of Component: Steam Generator "A" Secondary Handhole Stud Replacement.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install one (1) new stud on Steam Generator "A" (EMSO1A) Secondary Handhole. This activity was controlled by WO # 20400636. An Owner Elected ASME Section XI baseline VT examination was performed and acceptable. See Summary # Ml0001 1.

59.

ASME Class: 2 Svstem: MS GORR No.: 31-059 Component: EMSOIA Category: Corrective Action Activity Construction Code: ASME III '86 Work Performed Bv: 1 Name of Component: Steam Generator "A" Secondary Manway Stud Replacement.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install six (6) new studs on Steam Generator "A" (EMSOIA) Secondary Manway. This activity was controlled by WO # 20400636. An Owner Elected ASME Section XI baseline VT examination was performed and acceptable. See Summary # Ml 00009.

60.

ASME Class: 2 System: MS GORR No.: 31-060 Component: EMSOIB Category: Corrective Action Activity Construction Code: ASME III '86 Work Performed By: 1 Name of Component: Steam Generator "B" Secondary Handhole Stud Replacement.

Work Description/Remarks: A Like for Like mechanical replacement activity was initiated to install four (4) new studs on Steam Generator "B" (EMS01 B) Secondary Handhole. This activity was controlled by WO # 20400637. An Owner Elected ASME Section XI baseline VT examination was performed and acceptable. See Summary # M100018.

24

R. E. GINNA NUCLEAR POWHER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (1S) or 1992 Edition with 1992 Addenda (I WE/IWL Containment)

ATTACHMENT II

61.

ASME Class: 2 System: CVCS GORR No.: 31-061 Component: 300B Categorv: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, ASME III '92/'95/'96, ME-318 Work Performed BY: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace 2" x 1" Reducer by Valve 300B Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install two (2) new 2" x 1" reducers by Valve 300B. This activity was controlled by WO #

20400163. Construction Code VT and PT examinations were performed and acceptable.

ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05025.

62.

ASME Class: 2 System: SI GORR No.: 31-062 Component: TSI03B, V838A, V837A Categorv: Code Rejectable Indication Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Grind Repair of Two (2) 2" Nozzle to Pipe Welds off Accumulator "B" to Valves 838A and 837A.

Work Description/Remarks: A Section XI Code activity was initiated to repair by metal removal original fabrication weld defects on Two (2) 2" Nozzle to Pipe Welds off Accumulator "B" (TSI03B) going to Valves 838A and 837A. This activity was controlled by WO # 20501870 & Action Report 2005-1391. Upon completion of a code repair, PT examinations and UT thickness readings were performed and acceptable. See NDE Summary # R05038.

25

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (1WE/IWL Containment)

ATTACHMENT II

63.

ASME Class: 1 System: RHR GORR No.: 31-063 Line: 10" Category: Code Rejectable Indication Construction Code: ASME III '95/'96 Work Performed By: 1 Name of Component: Grind Repair on 10" RHR Weld ASW-1.

Work Description/Remarks: A Section XI Code activity was initiated to repair by metal removal original fabrication 5/16" & 3/16" pores on a 10" RHR line at Weld ASW-l. This activity was controlled by WO # 20501891 & Action Report 2005-1451. Upon completion of a code repair, Construction Code PT examination as well as UT thickness readings were performed and acceptable. See NDE Summary # R05040. ASME Section XI PT baseline examination was performed and acceptable. See ISI Summary # I029100.

64.

ASME Class: 2 System: MS GORR No.: 31-064 Line: 6" Category: Code Rejectable Indication Construction Code: ASME III '92/'95/'96 Work Performed By: I Code Case/Relief Request: Code Case N-416-2 Name of Component: Repair on 6" MS Weld L2BC1A by Valve 3504.

Work Description/Remarks: A Section XI Code Repair was initiated to removal original slag indications on 6" MS Weld L2BC1A by Valve 3504. This activity was controlled by WO #

20501912 & Action Report 2005-1430. Upon completion of a code weld repair, Construction Code MT examination of the cavity was performed and acceptable.

Construction Code VT, MT and RT examinations were performed to the finish weld and acceptable. ASME VT-2 Leakage Examination was performed and acceptable. See NDE Summary # R05042. ASME Section XI PT and RT baseline examinations were performed and acceptable. See ISI Summary # I090300.

26

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. OwnAer: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3. Applicable Edition of Section Xl Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (TSI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

65.

ASME Class: 2 System: MS GORR No.: 31-065 Component: MSU-7 (West)

Category: Corrective Action Activity Construction Code: EWR-2512, ASME III NF '74, MSS SP-58 Work Performed BY: 1 Name of Component: Snubber Replacement on Component Support MSU-7 (West)

Work Description/Remarks: A Like for Like Replacement activity was initiated to install a new Snubber for Component Support MSU-7 (West) located on a 30" MS line. This activity was controlled by WO # 20401666 and Action Report 2005-1573. ASME Section XI VT baseline examination was performed and acceptable. See ISI Summary # I601369.

66.

ASME Class: 2 System: CVCS GORR No.: 31-066 Component: V281L Category: Code Service Induced Rejectable Indication Construction Code: EWR-2512, B31.1 '67/'73, ASME III '92/'95/'96, ME-318 Work Performed BY: 1 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace 1 1/2 " Adaptor by Valve 281L Work Description/Remarks: A Code Replacement (Modification) activity was initiated to install a 1 'A2" adaptor on a 3/4" line by Valve 281L. This activity was controlled by WO #

20502038, Action Report 2005-1770 and DA-ME-2005-03 1. Construction Code VT, PT and RT examinations were performed and acceptable. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05044.

67.

ASME Class: 1 System: CVCS GORR No.: 31-067 Component: V427 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 2 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace Bonnet on Valve 427 Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install a new Bonnet by mechanical means on Valve 427 located on a 2" line. This activity was controlled by WO # 20400157 and Action Report 2005-2082. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05047.

27

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/IWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (IS!) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

68.

ASME Class: 3 System: CCW GORR No.: 31-067 Component: V740A Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '92/'95/'96, ME-318 Work Performed By: 2 Code Case/Relief Request: Code Case N-416-2 Name of Component: Replace Relief Valve 740A Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install a new Relief Valve by mechanical means on a 2" line. This activity was controlled by WO # 20401307 and Action Report 2005-2082. ASME Section XI VT-2 Leakage examination was performed and acceptable. See NDE Summary # R05049.

69.

ASME Class: 3 System: FW GORR No.: 31-069 Component: V4269 Category: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '95/'96, ME-318 Work Performed By: 3 Name of Component: Replace Cage & Plug on Valve 4269 Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install a new Cage and Plug by mechanical means on Valve 4269 located on a 14" line. This activity was controlled by WO # 20302807 and Action Report 2005-2082.

70.

ASME Class: 3 System: AFW GORR No.: 31-070 Component: V4009 Categorv: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B16.34, ASME III '95/'96, ME-318 Work Performed By: 2 Name of Component: Replace Disc on Valve 4009 Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install a new Disc by mechanical means on Valve 4009 located on a 3" line. This activity was controlled by WO # 20402002 and Action Report 2005-2082.

28

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEIIWL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd., Ontario, N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd., Ontario N.Y. 14519

3. Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT II

71.

ASME Class: 3 System: MS GORR No.: 31-071 Component: V3410 Categorv: Corrective Action Activity Construction Code: EWR-2512, B31.1 '67/'73, B 16.34, ASME III '95/'96, ME-318 Work Performed By: 2 Name of Component: Replace Plug on Valve 3410 Work Description/Remarks: A Code Like for Like Replacement activity was initiated to install a new Plug by mechanical means on Valve 3410 located on a 6" line. This activity was controlled by WO # 20404634 and Action Report 2005-2082.

72.

GORR No.:

31-072 Cancelled

73.

GORR No.:

31-073 Cancelled

74.

GORR No.:

31-074 Cancelled 29

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWE/INL

1. Owner: R. E. Ginna Nuclear Power Plant, LLC. 1503 Lake Rd., Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section Xl Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT III Steam Generator Eddv Current Program - Final Report i

VENDOR DOCUMENT REVIE 0 Apprvd. Memnanu Ahd o NotApprvd-Vedor Nofld Approval of ft docnent does not Iakn tiunWlm cmor Z

Approved By, NS&L Revew by (Reqked K pact on accnta a

EDDY CURENT EXAMINATION REPORT FOR STEAM GENERATOR TUBING Constellation Energy Group R.E. Ginna Nuclear Power Station March 2005 Report No: MRS-FSR-1385-RGE NSBU STEAM GENERATOR SERVICES WESTINGHOUSE ELECTRIC COMPANY, LLC Prepared By; Prepared By; Scott H. Taylor - ET LevefiI Labieniec - Project Manager Date:

-3/-

o-Date:

2 2/

Certificate of Conformance Constellation Energy

GINNA STATION WESTINGHOUSE NETWORK NO. 305498 STEAM GENERATOR EDY CURRENT EXAMINATION MARCH 2005 REFUELING OUTAGE

Reference:

CEG Purchase Orders; 05-01081, Steam Generator Services 05-01418, Intial PO for Plugs and Stabilizers 05-01562, Additional for Plugs and Stabilizers Ginna S/G Technical Specification TPFI # 2001-00 Rev 0, as applicable.

Westinghouse Electric Company has completed the subject services. The on-site activities were performed in accordance with Constellation Quality Assurance Program using Constellation and Westinghouse procedures. Documentation attesting to this work is contained within the Final Report and in the Quality Records, data procedures, and personnel certifications.

Westinghouse Quality Systems hereby certifies that the services described herein that were provided in accordance with the Westinghouse Quality Management System, specifically, the supply of certified personnel and equipment, meet the quality requirements of the referenced Purchase Order and technical specifications. Any exceptions to said requirements have been documented and evaluated by properly executed deviation notices.

The ET level III signature certifies that the technical content of the services and in conformance with the supporting procedures including codes, specifications, and standards referenced client and has been independently verified to be accurate.

Westinghouse Lead Alyst / ET Level III tingh se Project Manager stinghouse Field Service Quality

()Westinghouse March 30, 2005 Mr. Mike Shields Constellation Energy Group 89 East Avenue Rochester, NY 14649-0001

Subject:

Constellation Steam generator Eddy Current Examination Transmittal of Preliminary Report, Optical Data Disks, Eddynet Data Management Reports.

Dear Mr. Shields,

This letter transmits the following items; I:

Preliminary Report of the March 2005 Steam generator Eddy Current Inspection.

Included in this report from both Steam generators:

Final report listing of tubes tested Examination plan map of tubes tested Examination plan map for each dataset Separate listings and maps of the following

+PT special interest program Possible loose parts (PLP) and loose part signals (PLS)

Manufacturing murnish marks (MBM)

Dings (DNG) and dents (DNT) with history Tube proximity locations with history Reported sludge (SLG) hotleg and coldleg.

Data Management procedure and appendiecies Tube sheet maps of chronological tube report Tube plugging and installed stabilizers All March, 2005 eddy current results II:

Two copies of the Eddynet optical disks containing raw data and results from both Steam Generator A and Steam Generator B.

III:

A single copy of the data as is was acquired, in ANSER format.

IV:

Items from the ST-MAX and Eddynet data management systems.

Close-out report for S/G-A Close-out report for S/G-B ST-MAX Database loaded onto Constellation Data Management Computer Optical Disk containing the following Eddynet files and directories:

Insp_DB, histDB, APTS, Closeout Checklist, landmarks, CDS sorts, autocal, Eresolution setups, RESETUPS, data segment recall (DSR).

V:

Video Tapes

Steam Generator A Plug verification for both H/L and C/L.

Initial and final bowl scans for H/L and CIL Nozzle dam installation Steam generator B Plug installation for both H/L and CIL Plug verification for both H/L and C/L Initial and final bowl scans for H/L and C/L.

Nozzle dam installation VI:

Quality Control Surveillance Log VII:

Eddy Current Examination Sheets VIII:

Analysis Final Reports, Primary / Secondary Compare Reports IX:

ST-MAX Database files on CD-rom.

X:

Tube plug qualification documentation and certification XI:

Tube plugging and de-plugging procedures.

XII:

Installation and removal procedures for equipment to be used in the S/G.

XIII:

Steam generator independent verification system procedure XIV:

Manipulator check-out, calibration, installation, and removal procedures XV:

Personnel and equipment certification documents XVI:

Certification program document Referencing documentation:

Purchase Order; 05-01081, Steam Generator Services Purchase Order; 05-01418, Intial PO for Plugs and Stabilizers Purchase Order; 05-01562, Additional for Plugs and Stabilizers Ginna S/G Technical Specification TPFI # 2001-00 Rev 0, as applicable Proposal; 01 -OSW-045, Letter; LTR-NSFM-04-263

Note that some of the information cited above was transmitted prior to the outage. Please acknowledge receipt by signing the bottom of this page.

Respectfully Submitted, Westinghouse Electric Company LLC Scott H. Taylor Westinghouse Level III Ginna Lead Data Analyst Received by:

Ax/-

Mike Shields - Constellation Energy Group CC: Henry Labieniec Bruce Allbee

Constellation Energy R.E. Ginna Nuclear Power Plant INSERVICE INSPECTION DATA ROOM

SUMMARY

REPORT FOR STEAM GENERATOR TUBING of the R.E. GINNA ELECTRIC NUCLEAR POWER PLANT 1503 LAKE ROAD ONTARIO, NEW YORK. 14519 Report Submitted By; Scott H. Taylor Westinghouse ET Level III R.E. Ginna, Lead Data Analyst

TABLE OF CONTENTS Page No.

1.0 Introduction 3

2.0 Scope of Examinations 3.4 3.0 Personnel, Procedures and Test Equipment 4-7 3.1 Personnel Qualifications 3.2 Examinations and Analysis Procedures 3.3 Data Evaluation 3.4 Data Quality Requirements 3.5 Equipment and Test Probes 3.6 Calibration Standards 4.0 Summary of Base Scope Examinations 7-9 4.1 Bobbin Coil - Full length (base scope) 4.2 Rotating Coil - Hot Leg Tubesheets (base scope) 4.3 Rotating Coil - RI Ubends (base scope) 4.4 Rotating Coil - Proximity tube locations (base scope) 4.5 Rotating Coil - "Box-in" of low freq. responses (additional scope) 5.0 Eddy Current Examination Results 10-13 5.1 Loose Part Examination and Classification 5.2 Bobbin Coil and Rotating Coil Summary of Signals 5.2.1 Bobbin Coil Specifics 5.2.2 Rotating Coil Specifics 5.3 Rotating Coil Summary 6.0 Tube Plugging Summary 14 6.1 Steam Generator A 6.2 Steam Generator B 7.0 Certified Individuals, Work Locations, and Task Assignment.

14-15 7.1 List of Data Analysis, Data Management, System Admin, Personnel 7.2 List of Data Acquisition Personnel

STEAM GENERATOR TUBE EXAMINATIONS 1.0 Introduction This Summary Report describes the Constellation Energy Group Inservice Inspection (ISI) of the steam generator (S/G) tubing at the R.E. Ginna Electric Generating Station. The ISI was performed during the March 2005 refueling outage.

The steam generator tube ISI inspection was performed in accordance with The American Society of Mechanical Engineers (ASME)Section XI Code "Inservice Inspection of Nuclear Power Plant' Components" prescribed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(g).

Therefore, the ISI is required to meet the 1995 Edition of the ASME Code Section XI with 1996 addenda.

The R.E Ginna plant design contains two (2) re-circulating design steam generators designed and fabricated by Babcock and Wilcox of Cambridge Ontario (Canada). The nomenclature used for fabrication and subsequent in-service inspections is BWI #34 (SG-A) and BWI #35 (SG-B). Each BWI steam generator was is designed to contain 4765 tubes per S/G. One tube in each steam generator was removed from service during fabrication by means of a shop welded I-690 plug. Each S/G therefore contains 4764 inspectable tubes. The tubing material is thermally treated Inconel Alloy 690 having a nominal outer diameter (OD) of 0.750 inch and nominal wall thickness of 0.043 inch. The nominal thickness of the tube sheet is 25.25 inches, with a full depth hydraulic expansion of all the tubes into the tube sheet material.

The examination agency for this S/G inspection was Westinghouse Electric Company, LLC.

2.0 Scope of Examinations A Degradation Assessment (DA) was written prior to the outage by Westinghouse S/G Engineering and with input provided from the Constellation Energy Group. This document identified existing and potential damage mechanism and recommended locations for eddy current examinations. The necessary inspection techniques and areas of applicability were documented by the Constellation Energy Level III.

All techniques were approved for use by the Constellation Energy Level III, and reviewed by the Westinghouse Level III / Qualified Data Analyst (QDA) and also the Independent Qualified Data Analyst (IQDA), contracted by Constellation Energy.

The agreed upon eddy current base scope tube examinations, and any additional inspections required, were approved by the appropriate Westinghouse and Constellation personnel prior to testing. The S/G inspection was performred to meet the intent of EPRI document #1003138 Rev. 6, entitled "Pressurized Water Reactor Steam Generator Examination Guidelines.

The eddy current examination base scope consisted of the following planned examinations in each steam generator.

Bobbin coil - full length from tube-end inlet thru to tube-end outlet.

• All tubes not inspected in the 2002 examination. This was an approximate 50% sample.

• All peripherial tubes(2 tubes deep) including tube lane locations (rows 1,2,3,4)

• Previous signals of interest, MBM, DEP. DNT, DNG, PRS (previous s-codes identified)

Three coil straight body design rotating probe.

• An approximate 25% sample top of tubesheet hotleg at the expansion interface, (TSH +/-3"). All identified over-expansions from the PSI examination were included within this sample as well as one NCR in S/G-B from TSH-TEH.

Single coil ubend design rotating probe.

• 20% sample of row-I and 2 ubend region. (top TSP to top TSP).

Scheduled supplemental testing and those as a result of inspection findings

• Rotating coil of all I-codes identified by bobbin coil.

• Bobbin coil and/or RPC testing of tubes surrounding an potential loose part signal.

• 20% sample of reported dings/dents, >=2vpp digressing from largest voltage 8C-TEH set as priority.

• 20% sample of reported MBM's, >=Svpp digressing from largest voltage, 8C-TEH set as priority area.

3.0 Personnel, Procedures, and Test Equipment 3.1 Personnel Oualifications The personnel who performed the ET acquisition and ET data analysis functions were employed by Westinghouse, NDE Technology, Master-Lee, Anatec, Zetec, TheYoung Group, and INTECH. All were certified in accordance with the requirements of IWA-2300 of ASME Code Section XI and the certification practices of their respective employers. One hundred (100) percent of the ET data analysts were certified as Qualified Data Analysts (QDA's) for the steam generator work performed. A QDA is a Level IIA or III who has passed rigorous testing of his ability to analyze a random selection of expertly-judged indications, from the Electric Power Research Institute's "PWR Steam Generator Examination Guidelines", Appendix G Performance Demonstration Database, for various steam -generator designs and all types of known defects.

Before an ET data analyst could perform any functions they were required to successfully complete a Site Specific Perf6rmance Demonstration (SSPD). A site indoctrination discussed Ginna steam generator design, operating history, and previous ET results. Recent S/G operational experience and industry finding were also discussed. The site specific analysis guidelines, ACTS, ANTS, were reviewed by all. Damage mechanisms that have either been identified and/or have the potential to exist were identified during the training and examination process. Successful completion of the SSPD program required several items.

• A written examination consisting of 30 questions, selected randomly from a database. Each individual required a passing grade of >=80%.

• A practical bobbin coil examination, computer generated from a random database. Each individual required a passing grade where the POD was >=80% with a >=90% CL. Computer Data Screening (CDS) also sucessfully completed the SSPD per the 80/90 criteria above.

• A practical RPC examination, common to all analysts, of pre-determined data sets. Each individual required a passing grade of>=80%.

All incorrect answers on the written examination, as well as all missed signals on the bobbin and RPC practical examinations were provided to the data analyst for review. All re-testing was performed using the same grading and review scheme.

3.2 ET Examination. Data Analvsis, and Data Ouailtv Procedures ET data collection and data analysis were performed in accordance with the following procedures.

• Constellation Energy Group acquisition procedure CEG-400-001, Revision 0.

"Multi-frequency Eddy Current Examination of Non-ferromagnetic Steam generator Tubing".

• WNSD procedure MRS-GEN-1 127, Revision 3.

"Guidelines for Steam Generator Eddy Current Data Quality Requirements".

• Constellation Energy Group data analysis guidelines, Revision 0.

"Data Analysis Guidelines Ginna 2005".

• Westinghouse QA Surveillance Procedure CEG400-002, Revision 0.

3.3 Eddy Current Data Evaluation and Data Management All eddy current data acquired was subjected to two (2) separate independent analyses. The primary, secondary, and resolution analysis functions were all performed at the Ginna Site. Westinghouse served as the primary analysis team and performed manual evaluation of all probe types. Zetec represented the secondary analysis team and utilized Computerized Data Screening (CDS) for bobbin coil data and provided manual data analysis for all rotating coil data. A primary / secondary compare and subsequent resolution of discrepancies was performed by personnel representing both Westinghouse and Zetec. An independent qualified data analyst (IQDA) reviewed all I-codes which were changed to a non-pluggable indication, or were dispositioned to an NDD code. In addition, the IQDA reviewed a sample of NDE tubes in each S/G. A common data analysis platform was utilized for all functions above. This consisted of HP workstations loaded with unix operating system Version I Ii, Revision 1, Patch #14 of the Zetec Eddynet analysis software.

Primary data management was performed by Westinghouse per procedure SGMS 2.2.1 GEN-01 1 Revision 9. Utilizing the Westinghouse ST-MAX system, this PC based windows environment used software Version 1.15.00, appendix 12.3.1, 12.3.2 and 12.3.3. A Ginna specific checklist was used for database close-outs and verification of program completion.

Zetec provided secondary data management using the Zetec EIMS system. The unix based operating software for this inspection was Version I li, Revision 01, Patch #14. The EIMS database also had a standardized checklist used for database close-out and verification of program completion.

Per the request of the Constellation Level III, an automated sludge "SLG" evaluation was performed on both tubesheets from the bobbin coil examination. All measurable accumulation at top of tubesheet

>=0.50" was recorded respectively as either TSH + and TSC +.

3.4 Data Oualit' Requirements All data quality programs (DQM) were initially implemented on the acquisition level per MRS-GEN-1127 Revision 3. The DQV program addressed the requirements outlines in the EPRI document

1. 1003138 Rev. 6, entitled "Pressurized Water Reactor Steam Generator Examination Guidelines. The SGMP Interem Guidance Letter stating exemption from progressive noise measurements was also used.

For those instances where a "false failure" identified by the acquisition program, the station operator had the opportunity to rectify the situation or re-test that particular tube again. If the DQV failure appeared to be a result of program and/or software limitation, the primary and secondary analyst would evaluate the tube as normal. The resolution data analysts could then over-ride the data quality failure provided they also agreed the data was acceptable. Each tube collected was subject to various DQV checks.

Results of all eddy current examinations were recorded on a digital rewritable optical disk and the final resolution data sheets, which are both stored as records. The ET data disks contain the raw ET-data, primary, secondary, and resolution results for each calibration group. Within each calibration group, system calibration (standard runs) as well as each tube collected have the actual time and date verification recorded at the time of collection. All optical disk are numbered such that each steam generator and each calibration group are indicated on the optical disk label. Therefore, all system calibrations, calibration verifications, and raw data for each tube examined can be easily recalled.

3.5 Equipment and Test Probes All examinations were performed using ANSER acquisition software, Version 8.4.1 Revision 232 along with a Zetec MIZ-70 digital multi-frequency tester. The acquisition test instrument and software store and process the ET data in a digital format and have a significantly improved dynamic range and signal-to-noise ratio as compared to analog systems. The test system is capable of being operated at locations remote from the steam generators (e.g., in low radiation areas).

All bobbin coil examinations were performed using inspection frequencies of 550, 280, 140 and 35 kHz in both the differential and absolute modes for each tube. A nominal pull speed of 40 inches per second with a digital sampling rate of 1600 samples per second was used for the majority of all tubes examined.

Acquisition Technique Sheet (ACTS) number RGE-01-105 was the applicable inspection technique.

Additionally, a slower test speed was used to reduce probe snap in tight radius ubends of rows 1 - 4.

This slower pull speed of 24 inches per second used a digital sample rate of 1000 samples per second, as listed on ACTS numbers RGE-02-105, RGE-03-105. Specific information relative to probes, extensions, manufacturers, etc. is contained within each of these ACTS sheets mentioned.

A 3-coil probe (straight body design) was used for all base scope and supplemental RPC examinations within the straight section of the S/G tubing. The 3-coil RPC examination technique was performed using the examination frequencies of 400, 300, 100, and 35kHz for both the + Point coil and also the 0.1 15" mid-range pancake coil. The third coil, a 0.080" shielded high frequency pancake was not

activated for these examinations. A digital sample rate of 1600 samples per second was specified for RGE-04-105. Specific information relative to probes, extensions, manufacturers, etc. is contained within each of these ACTS sheets mentioned.

A single coil Plus Point (u-bend design) probe was utilized for all base scope and supplemental examinations within the u-bend region of the S/G tubing. Various probe extensions were connected to the actual EC probe to inspect higher row (increased radius) u-bend regions of interest. Previously identified tube to tube proximity locations were also part of this inspection scope. The examination frequencies of 400, 300, 100 and 35kHz were used for this application. A digital sample rate of 1600 samples per second was specified for RGE-05-105 and RGE-06-105. Specific information relative to probes, extensions, manufacturers, etc. is contained within each of these ACTS sheets mentioned.

3.6 Calibration Standards Bobbin coil calibration standards contained ASME Code Section XI flaws, and both a stainless and carbon steel support ring. The calibration standard utilized for all rotating coil examinations was an EP5 design guide tube standard containing several ID and OD, notches axially and circumferentially oriented, electro-discharge machined (EDM) notches. Additional calibration standards containing various support structures (simulating S/G support structures) were also utilized. These standards are intended for use with a bobbin coil or a rotating coil probe.-In each case,-simulated defects relive to depth and orientation were present to permit the sizing of indications, if necessary.

4.0 Summary of Base Scope and Special Interest Examinations 4.1 Bobbin Coil - Base Scope All tubes were examined full length from tube end to tube end. The nominal probe diameter attempted for all bobbin examinations was 0.620"beaded probe design. A 0.610" beaded probe design was used on an as-needed basis for restrictions or retests approved for this probe diameter. Both were manufactured by Zetec.

Eddynet EIMS probe code designator is A620MULC/C and A610MULC/C.

ST MAX probe code designator is M/A620-ULC/CS/MR and M/A610-ULC/CS/MR.

S/G Scheduled Completed Obstructed Existing Plugs Exams Exams Tubes A

2713 2713 0

1 (pre-operational)

B 2686 2686 0

1 (pre-operational)

4.2 Rotating Coil. Inlet Tubesheet Region, - Base Scope A 25% sample hotleg top of tubesheet program was scheduled in each steam generator. The minimum test extent identified was continuous data collection from 3" below the top of tubesheet, through the expansion, ending at 3 "above the transition. The nominal probe diameter utilized for all straight section examinations was a 0.610", manufactured by Zetec.

Eddynet EIMS probe code designator is B61011536S80 ST MAX probe code designator is +PT610-MRPC/3C/P1 14A-PP1 lA=SP080B/52PH-664-ZM001 S/G Scheduled Completed Obstructed Pluggable Exams exams Tubes Indications A

1220 1220 0

0 B

1204 1204 0

0 4.3 Rotating Coil, Low Row Ubend Region - Base Scope A 20% sample program of low ubends was scheduled in each steam generator. At 120 columns, this percentage produced a 12 tube sample in row 1 and a 12 tube sample in row 2. This percentage was applicable to each S/G. The test extent identified was from the upper tube support hot leg to the upper tube support cold leg. The nominal probe diameter utilized for all low row ubend examinations was a 0.580", manufactured by Zetec.

S/G Scheduled Completed

-Obstructed-..-

Pluggable Exams Exams Tubes Indications A

24

.24 0

0 B

24 24 0

0 Eddynet EIMS probe code designator is B58036 ST-MAX probe code designator is +PT-580-MRPC/FH/PPI lA/18IN/52PH-664-ZM001 4.4 Rotating Coil, Proximity Tubes in the Ubend Region - Base Scone Previously identified ubend areas, having tube to tube proximity signals, were again scheduled for examination. This test was to verify the proximity values had not changed, as well as screen for any tube to tube wear in this region. The test extent identified was from the upper tube support of either the

.hotleg or the coldleg to a specified fan bar location in the ubend area; The nominal probe diameter utilized for all proximity examinations was a 0.580".

S/G Scheduled Completed Obstructed Pluggable Exams Exams Tubes Indications A

13 13 0

{

0 B

12 12 0

0 Eddynet EIMS probe code designator is B58036 ST-MAX probe code designator is +PT-580-MRPC/FH/PP1 IA/I 8IN/52PH-664-ZMOO1

4.5 Rotating Coil. "box-in" of PLP locations - Special interest Low frequency responses, which could possibly represent be the presence of foreign object, were identified during the base scope bobbin and/or tube sheet examination. Previous results and data evaluations have tracked these signals for multiple inspections with no tube wear detectable. In each case, the surrounding tubes were examined to determine if in fact multiple tube contact was present.

The standard 3-coil probe, mentioned above was used for this supplemental testing.

S/G Additional Exams Completed Exams Obstructed -

Pluggable TSH-lH TSH-1H Damaged Tubes Indications A

22 22 -

0 0

Special interest location was due to loose part successfully retrieved from the S/G secondary side.

S/G Additional Exams Completed Exams Obstructed -

Pluggable TSH-1H TSH-1H Damaged Tubes Indications A

7 0

Special interest location was due to loose part signal reported by bobbin coil in R94 C54.

S/G Additional Exams Completed Exams Obstructed -

Pluggable TSH-IH TSH-1H Damaged Tubes Indications A

3 3

0 0

Special interest location was due to loose part signal reported by rotating coil in R93 C55.

S/G Additional Exams Completed Exams Obstructed -

Pluggable TSC-IC TSC-1C Damaged Tubes Indications I B

15 15 0

0 J

Special interest location was due to loose part signal reported by bobbin coil at R48 C1 14 and R50 C1 14.

5.0 Eddy Current Examination Results The axial location of all signals were recorded in a positive offset relative to the adjacent tube support, baffle plate and/or fan bar. This convention was used throughout the tube bundle, except at support structures, where a plus/minus 2-inch window was used when reporting indications that were at or near the support structure. The tube support plates and baffle plates are numbered consecutively on both the' inlet and outlet side of the steam generator starting at the lowest elevation. The fan-bars are numbered FO 1 through F 10 from' the hot leg to the cold leg side, respectively.

The bobbin coil three letter codes found in the data analysis guidelines and also published in the ANTS sheets, were used reflect the suspected nature of the discontinuity. Signal attributes and previous history were considered when identifying such signals.

All bobbin signals meeting the current reporting criteria were compared to the 1997 inspection results to determine if the signal was in fact present and if so, had it changed in characteristics. This process ensured that defects induced during S/G operation could be identified as such. Previously identified signals, which did not meet the current reporting criteria, were again re-identified with the proper reporting code(s). This was done to maintain database consistency and assist with tube identification. A historical signal comparison was also performed at these tube locations.

5.1 Loose Part Examination and Classification Steam generator - A:

Bobbin coil examination of Row-94 Column-54 identified a low frequency response between the top of tube sheet hot leg and the first support structure (TSH +9.8"). Since the signal characteristics closely resembled the confirmed object in S/G-B, it was classified as a bobbin possible loose part "PLP".

Rotating coil also confirmed a loose part signal which was classified as "PIS". The adjacent tube, Row-93 Column-55 was not inspected with bobbin coil but was classified as a possible Ioose part signal.

"PLS" during the supplemental RPC bounding of these 2 tubes. No tube wear or vibrational type damage was detectable from either probe type. No additional action was taken at either of these tube locations, these tubes will be examined during future inspections.

Historical database for these locations is as follows; TUBE 2005 J

2002 1999 l

1997 l

l 94 - 54 l RPC - PLS I Not Inspected I Bobbin - DEP I NDD I

TUBE l 2005 J

2002 l

1999 l

1997 l

93 - 55 5 RPC-PLS I Bobbin-DEP I

NDD l Not Inspected I These signals were previously classified as a deposit signal (DEP) during pervious inspections and conservatively reported as a loose part signal (Rotating Coil PLS) and/or a possible loose part signal (bobbin PLP) during the 2005 inspection. The signals have not changed only the reporting acronyms.

We will track these in future inspections, most notably for degradation type signals.

Steam generator - B:

Bobbin coil examination identified a low frequency response between the top of tube sheet cold leg and the first support structure (TSC +20"). A secondary side visual inspection confirmed the presence of a foreigrf object at this location. An unsuccessful attempt was made to retrieve the object which appears to

be 'wedged' between two tubes. No tube wear or vibrational type damage was detectable from the bobbin coil and/or the supplemental rotating coil data. Four (4) tubes have being stabilized on the cold leg side, and subsequently removed from service (plugged) as a result of this finding;

• Two (2) loose part contact locations: Row48 Column-i 14 and Row-50 Column-i 14.

• Two (2) adjacent tube locations to those above: Row-47 Column-1 15 and Row-49 Column-i 13.

5.2 Bobbin and Rotatina Coil Summary Steam Generator AI I

I

_t Bobbin TSH +Point Tube Proximity

+Point U-Bend Special Interest Straight Section Special Interest DEP 4

2

'0A<-.--.

0 0

DNG 38 N/A

.NIA3 DNT 18

' ' N/A

,NI*:.7t/A

>L.. t INF 3

0 NIA70 0

INR 7

2 I

I-0 4

MIBC N/A 0

B N/A 2

8 MBM 254

--N/A' NX>NtAZ-T'N

.N/A

'7 NNi Q,-,;

NDF N/A

• N/A <

.ytJiA'7 13 2

PLP N/A

. -IA

,-'N/A-

.N/A' PLS N/A 0

NA-.

0 2.

RES 1

0 0

0 0

PRS N/A N/A:

31

/A.

§<:.N/Q:

.N.A'.

Steam Generator B Bobbin TSH +Point Tube Proximity U-Bend Special Straight Section

+Point Interest Special Interest BLG 6

N/A.

->rm1NIA I

DEP 5

5

-0A' 0

0 DNG 53

'N/A'.P!9, N,,AY,..........-

I... <j;.,/

,A.

N"-

DNT 20 N/A, DSS I

N/A',

NIA'Z

',/A INF 10 0

IN '

1 >:','0

.0 INR 7

4 A..

0 0

MBC N/A 0

A 1

7 MBM 260 I.

N/A"

'-Žq!!JNIA

'5<i.I A

9

. N/A t NDF N/A 1,

N/A o'N/A,

16 2

NQS 1

'-N/A

-s

<N

.A't; ',-' Z 2;,-'/A PLP 4

N/A ' :14/A'

, ;CNTA-- s r NlA PLS N/A' 0

.0NIA,-Ci.

0 2

PRS N/A

. N/A'

22

.N/A-

5.2.1 Bobbin Coil Specifics BLG - Bulges identified within the tube sheet expansion meeting the reporting criteria of 22vpp on the 550kHz absolute channel were identified.

DEP - Low frequency responses indicative of metallic deposits were identified as such. The intent is to track these during future inspections. In the event a previously identified DEP signal was not present in the current inspection, INF was used to address these locations.

DNG, DNT - Tubing deformations were identified as ding in the freespan, and as dent at support structures. The reporting criteria was >=2.5vpp in the freespan area and >=5vpp in the ubend area.

Previous signals identified as a ding or dent, were again identified as such to maintain database consistency. All signals not reported in past inspections, were verified as present in historical data. No active denting was observed. In the event these were misclassified (tangent point or probe snap) or reported at the wrong elevation during a previous outage, INR may have been used to re-address these locations.

DSS - Previous signal identified as a "distorted support plate signal". Historical data comparison was performed and the signal was re-identified as a DSS in 2005 upon finding no change.

INF - Signals identified in previous inspections, not present in-2005 were classified as 'indication not found". A historical tube comparison was performed to ensure.the correct location was tested.

INR - In the event a signal was misclassified (tangent point, probe snap, etc) or was reported at the K

i wrong elevation during a previous outage, INR may have been used to re-address these locations.

INF / INR - SPECIFICS:

In SG-A, 2 bobbin deposits reported in previous outages were reported as indication not reportable because the signal was not present during the 2005 inspection or was insignificant. Three bobbin deposits reported during previous outages were reported as indication not found because the deposit signal was no longer present. Two dings reported in previous outages were mislocated during those outages, and were reported as indication not reportable and the actual ding reported at the correct location. One ding was reported from 08H -2.19" and was reported as indication not reportable and the ding reported this outage at 07C +36.65". One.dent reported in previous outages was probe motion or other parasitic non-anomal6us condition and was reported as indication not reportable. Finally, a manufacturing buff mark reported in previous outages was mislocated during those outages and was reported as INR this inspection and the MBM reported at the correct location.

.In SG-B, one bobbin deposits reported in previous outages were reported as indication not reportable because the signal was not present during the 2005 inspection or was insignificant. Nine bobbin deposits reported during previous outages were reported as indication not found because the deposit signal was no longer present. A distorted support signal reported in the 2002 inspection was reported this outage as.

an indication not reportable because it did not meet the current reporting criteria. Two manufacturing buff marks reported in previous outages were mislocated during those outages and were reported as INR this inspection and the buff marks reported at their correct location. Finally, a ding reported during the 2002 inspection was mislocated during that inspection, reported as indication not found during the current inspection, and the ding reported at the correct location.

MBM - Manufacturing Burnish Mark type signals represented the majority of all signals reported in both steam generators. The reporting criteria used was >=2.5vpp on channel 6 with consideration 'given to a response on the PI mix channel. S/G-A had 254 reported, of these 23 had a response on Ch. P1.

S/G-B had 260 reported, of these 25 had a response on Ch. P1. All signals observed were compared to historical data to look for signal 'change' for possible degradation at these locations. No changes have been noted at these manufacturing anomalies to date.

NQS - A differential bobbin coil response, having been RPC tested in a previous inspection, showing no changes in signal characteristics during this inspection was again classified as NQS.

No flaw-like signals were reported at any structure or any freespan location in any steam generator.

RES - Restricted tube was noted with a 0.620" probe diameter. This is consistent with previous outages where it was also restricted and tested with a 0.610" probe.

PLP - Possible loose part signal as discussed previously in sections 4 and 5.

5.2.2 Rotating Coil Specifics There were no axial or circumferential (crack-like) indications reported in any steam generator. Like-wise no volumetric or wear type signals reported at the locations tested.

DEP - Low frequency responses indicative of metallic deposits were identified-as such. The intent is to track these during future inspections. In the event a previously identified DEP signal was not present in the current inspection, INR was used to address these locations.

INR - Previous deposit signals which were indicative of sludge accumulation.

MBC -Manufacturing Burnish Mark, confirmed by RPC testing. Of the 22 total examined, 18 were classified as MBC tested 4 were classified as NDF.

NDF - 31 total locations were tested for dents and dings, all 31 were classified as NDF. As mentioned above 4 MBM locations were classified as NDF as well.

PLS - Possible loose part signals were observed and summarized within sections 4 and 5.

PRS - Tube to tube proximity has been tracked for subsequent inspections after a manufactures notice

.was issues. The ubend area of 13 tubes in S/G-A, and 12 tubes in S/G-B were inspected to ensure no changes in proximity and/or tube to tube wear was occurring. There were no changes with respect to proximity regions and no wear indications were detected in this area.

Additional information relative to tube examinations and final results are published in the Westinghouse Data Management Report. This is a standard turn over package provided to the utility at the conclusion of the EC inspection.

6.0 Tube Plugging Summary 6.1 Steam Generator A There were no tubes considered degraded or defective through the ET examinations performed.

There were no tubes-removed from service.

6.2 Steam Generator B There were four (4) tube locations removed from service.as specified in section 5.1.

No tubes were considered degraded or defective through the ET examinations performed.

7.0 Eddy Current Examination, Listing of Personnel 7.1 Certified Data Analysis Personnel and Data Managent Crew NAME and LOCATION Taylor, Scott Tobin, Robert Nissley, Raymond Manley, Michael Thompson, Kurt Padgett, Lawrence Calendar, Dominic Hover, Lynn Gomez, Andrew Palmer, Richard Webb, Joel Stocklin, Paul Lamb, Justin Black, Carson Akre, Michael Mau, Ty Dahnke, Donald Case, John Young, John Marlis, Chris Young, John Moslener, Melvin Christopher, Phil Driessen, Nathan Lape, Gary Butcher, Travis Ewald, Michael EC LEVEL Ill Ill Ill Ill IIA Ill IIA Ill IIA Ill IIA IIA IIA Ill Ill

.Ill Ill Ill IIA N/A N/A N/A N/A N/A N/A N/A N/A COMPANY WEST WEST ZETEC ZETEC NDE Master-Lee Young Group Young Group Young Group Young Group Young Group Young Group ZETEC ZETEC ZETEC ZETEC Anatec NDE NDE WEST WEST NDE Anatec ZETEC ZETEC Young Group Young Group FUNCTION.

WEST - Lead / Res.

WEST Resolutions ZETEC - Resolutions ZETEC - Resolutions WEST - Primary WEST-Primary WEST-Primary WEST - Primary WEST - Primary WEST - Primary WEST - Primary WEST - Primary' ZETEC - Secondary ZETEC - Secondary ZETEC - Secondary ZETEC - Secondary INDEPENDENT ODA DATA QUALITY DATA QUALITY WEST - Data Management WEST - Data Management WEST - Data Management WEST - Data Management ZETEC - Data Management ZETEC - Data Management System Administration System Administration

.. -:. I. :-.

. ;' I.Znl._'_..17 '__.

7-1.

7.1 Certified Data Acquisiti6n Personnel NAME and LOCATION Schachte, Donald Smith, Donald Provencher, Colin Douglas, Barry Gallant, Greg Kindt, Kurt Lentz, Paul Ericson, Edward Pessak, Steven EC LEVEL II 11.

If II II 1I 1l COMPANY WEST WEST WEST WEST

-WEST WEST WEST HUDSON Young Group FUNCTION WEST - Acq.

WEST-Acq.

WEST - Acq.

WEST - Acq.

WEST - Acq.

WEST - Acq.

WEST-Acq.

WEST-Acq.

WEST-Acq.

Respectfully Submitted, Scott H. Taylor March 30,2005

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) - ISI First Interval (1997-2008), Second Period, Third Outage (2005) - IWEAIWL

1. Owner: R. E. Ginna Nuclear Power Plant. LLC. 1503 Lake Rd.. Ontario. N.Y. 14519

2.

Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd.. Ontario N.Y. 14519

3.

Applicable Edition of Section XI Utilized for Repair or Replacement Activities:

1995 Edition with 1996 Addenda (ISI) or 1992 Edition with 1992 Addenda (IWE/IWL Containment)

ATTACHMENT IV Erosion/Corrosion (Minwall) Program Examination Results i

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

Attachment IV ErosionlCorrosion Program Summary This section provides Erosion/Corrosion examination details and information corresponding to the items inspected prior to & during the 2005 RFO.

A total of 390 components were examined, the breakdown of this total, by Program type is as follows:

FAC "M-Figures" FAC "S-Figures" Large Bore Small Bore Misc.

Service Water Total 162 139 31 58 390 M-Figures: Erosion Corrosion FAC Program Isometric for Large-Bore Line Comnonents Systems of Examined Components Component thickness measurements were performed on the following systems:

FIGURE Number SYSTEMS Ml A/B FW PUMP DISCHARGE TO 5A151 HEATERS M2 5 A/B FW HEATERS TO FW HEADER M3 HEATER 4A/4B DRAIN TO HTR DRAIN TANK M4A FW CLEANUP TO CONDENSER FROM 5A & 5B FW HTRS M5 HEATERS 4A/4B TO FEED WATER SUCTION M6 FEEDWATER SUCTION TO PUMPS A/B Ml IA MSR IA & 11 2N PASS DRAIN M12A MSR 1A & 1B 2ND PASS TO HEATER & CONDENSER M12B MSR 2A & 2B 2ND PASS TO 5B HEATER & CONDENSER M15A MSR lA 4 TH PASS TO 5A HEATER M1 5B MSR 1 B TO HTR 5A, TO CV M16 MSR IA & lB 4TH PASS TO CONDENSER M17A MSR 2A TO HTR 5B, TO CV M17B MSR 21 4TH PASS TO BB HEATER M18 MSR 2A & 2B 4TH PASS TO CONDENSERS M20 15, 2B. 3B LP HEATER DRAINS TO CONDENSER M21 STEAM EXTRACTION TO PRESEP TANK "B" & 48 LP HTR M22 STEAM EXTRACTION TO PRESEP TANK SAX & 4A LP HTR M31 MSR IA & 1 B TO HEATER DRAIN TANK & CONDENSER M32 MSR 2A & 28 TO HEATER DRAIN TANK M33 MSR IA, 1B, 2A, 2B TO HTR DRAIN TANK M41B 58 HP HEATER DRAIN TO 48 LP HEATER M45 PRESEPARATOR A/B TO HTR DRAIN TK & CONDENSER M46B PRESEPARATOR A/B TO HEATER DRAIN TANK M75 STEAM EXTRACTION TO 5A & 5B HEATERS M81 FEEDWATER DISCHARGE (TURBINE BLDG)

M82 FEEDWATER DISCHARGE (INTERMEDIATE BLDG)

M83 FW DISCHARGE (INTERMEDIATE & FACADE)

M84 FEEDWATER TO S/G 1A M88A S/G BLOWDOWN LINES (INTERMEDIATE BLDG)

M88D S/G BLOWDOWN TO FLASH TANK (TURBINE BLDG)

M90 FEEDWATER CLEANUP (CV-18)

M91 FEEDWATER CLEANUP (CV-19)

M92 MAIN FEEDWATER PUMP RECIRCULATION M93 FEEDWATER BY-PASS LINE Milo HEATER DRAIN TANK TO CONDENSER 1

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

Components:

The following list identifies system(s) of examined components, system component summaries, and component examination result in details.

Component Examination Result in Details The following list provides results in detail on components by drawing number and system description.

The Component Type' classification, specified in the list below, corresponds to the following:

P= Pipe E= Elbow T= Tee R= Reducer B= Bend C= Cap N=Nozzle V= Valve Ml FEEDWATER SUCTION TO PUMPS A/B REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL 1 READING NOMINAL METHOD BOP-UT-05-181 03 P

0.938" 0.603" 0.844"

> 88%

UT BOP-UT-05-216 04 E

0.938" 0.607" 0.885"

> 88%

UT BOP-UT-05-178 05 P

0.938" 0.607" 0.896"

> 88%

UT BOP-UT-05-113 18 E

0.938" 0.607" 0.866"

> 88%

UT BOP-UT-05-114 19 P

0.938" 0.604" 0.897"

> 88%

UT BOP-UT.05-230 26 E

0.938" 0.607" 0.881"

> 88%

UT BOP-UT-05-229 27 P

0.938" 0.604" 0.875"

> 88%

UT M2 5 AIB FW HEATERS TO FW HEADER REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-141 13 E

0.938""

0.602" 0.858""

> 88%

UT BOP-UT-05-142 13A N

0.938" 0.602" 0.844"

>88%

UT BOP-UT-05-111 22 E

0.938" 0.602" 0.893"

> 88%

UT BOP-UT-05-112 26 P

1.281" 0.858" 1.246"

> 88%

UT BOP-UT-05-185 37 E

1.281" 0.859" 1.284"

>88%

UT M3 HEATER 4A/4B DRAIN TO HEATER DRAIN TANK REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT.05-149 01 P

0.688" 0.346" 0.552" 80%

UT BOP-UT-05-150 0IA N

0.688" 0.346" 0.608"

> 88%

UT BOP-UT-05-143 14A P

0.688" 0.346" 0.672"

> 88%

UT M5 HEATERS 4A14B TO FEEDWATER SUCTION REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT.05-125 01 E

0.375" 0.210" 0.327" 87%

UT BOP-UT-05-118 CIA N

0.375" 0.210" 0.325" 87%

UT BOP-UT-05-131 13 E

0.375" 0.210" 0.341"

> 88%

UT BOP-UT-05-124 13A N

0.375" 0.210" 0.314" 83%

UT BOP-UT-05-103 28 P

0.375" 0.251" 0.333"

> 88%

UT BOP-UT-05-214 36 P

0.375" 0.250" 0.352"

> 88%

UT 2

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M6 FEEDWATER SUCTION TO PUMPS A1B REPORT#

COMP. TYPE ID NOMINAL WALL 1 0.375" 0.375" 0.375" T-MIN.

0.247" 0.250" 0.245" MINIMUM READING 0.309" 0.379" 0.341" PERCENT NOMINAL 83%

> 88%

> 88%

NDE METHOD UT UT UT BOP.UT-05-102 BOP-UT-05-101 BOP-UT-05-104 27B 28 29 P

E P

M11A MSRIA& lB2ND PASS DRAIN REPORT #

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-UT-05-078 BOP-UT-05-077 BOP-UT-05-086 BOP-UT-05-080 BOP-UT-05-085 BOP-UT-05-079 BOP-UT-05-084 41 41A 41B 41C 42 43 73B N

E P

R E

P P

1.500"/ 0.500" 0.432" 0.432" 0.500"1 0.432" 0.432" 0.432" 0.432" 0.303" 0.265" 0.264" 0.323" 0.265" 0.264" 0.264" 0.478" 0.345" 0.424" 0.453" 0.372" 0.415" 0.401"

> 88%

79%

> 88%

> 88%

86%

> 88%

> 88%

UT UT UT UT UT UT UT M12A MSR IA & 1B 2nd PASS TO HEATER & CONDENSER REPORT#

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-UT-05-115 BOP-UT-05-096 BOP-UT-05-156 BOP-UT-05-094 BOP-UT-05-095 BOP-UT-05-100 BOP-UT-05-098 40A 90 91 104C 105 106 106A N

P p

P E

P R

0.594" 0.594" 1.031" 0.432" 0.432" 0.432" 0.432"I 0.594" 0.216" 0.297" 0.516" 0.216" 0.226" 0.223" 0.221"10.302" 0.537" 0.608" 0.995" 0.418" 0.321" 0.271" 0.411"

> 88%

> 88%

> 88%

> 88%

74%

62%

> 88%

UT UT UT UT UT UT UT M1 2B MSR 2A & 2B 2nd PASS TO 5B HEATER & CONDENSER REPORT #

COMP. TYPE NUMBER ID NOMINAL WALL 1 0.432" 0.594" T-MIN.

0.266" 0.216" MINIMUM READING 0.460" 0.550" PERCENT NOMINAL

> 88%

> 88%

NDE METHOD UT UT BOP-UT-05-1 80 BOP-UT-05-119 63 72 R

N M15A MSR 1A, 4TH PASS TO 5A HEATER REPORT#

COMP. TYPE ID NOMINAL WALL 1 T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-342 BOP-RT-05-343 BOP-RT-05.344 BOP-RT-05-352 BOP-RT-05-353 BOP-RT-05-354 BOP-RT-05-349 BOP-RT-05-350 BOP-RT-05-351 35 35A 35B 36A 36B 37 39 40 41 P

R P

R R

P P

E P

0.300" 0.300" 10.179" 0.179" 0.300" 10.179" 0.337" 1 0.218" 0.337" 0.337" 0.337" 0.337" 0.177" 0.136"10.090" 0.090" 0.136"/0.090" 0.169"10.109" 0.169" 0.169" 0.169" 0.169" 0.302" 0.324" 0.184" 0.210" 0.210" 0.345" 0.335" 0.302" 0.328"

> 88%

>88%

> 88%

70%

> 88%

> 88%

>88%

> 88%

> 88%

RT RT RT RT RT RT RT RT RT 3

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M15B MSR IA 4TH PASS TO 5A HEATER REPORT#

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-345 BOP-RT-05-346 BOP-RT-05-347 87 87A 87B P

R P

0.300" 0.300" 1 0.179" 0.179" 0.177" 0.136"10.090" 0.090" 0.303" 0.291" 0.184"

> 88%

> 88%

> 88%

RT RT RT M16 MSR IA & 1B, 4TH PASS TO CONDENSER REPORT #

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-340 BOP.RT.05-348 BOP-RT-05-358 12 17 17A V-2405 E

P VALVE APPEARS TO BE NOT CLOSED COMPLETELY, WARM TO TOUCH.

0.300" 0.164" 0.290"

> 88%

0.300" 0.164" 0.311"

> 88%

RT RT RT M17A MSR 2A TO HTR 58, TO CV REPORT #

COMP. TYPE ID NOMINAL WALL 1 T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-355 BOP-RT-05-356 BOP-RT-05-357 36 36A 36B P

R P

0.337" 0.300" 10.179" 0.179" 0.176" 0.136" 10.090" 0.090" 0.290" 0.303" 0.168" 86%

> 88%

> 88%

RT RT RT M17B MSR 2B, 4TH PASS TO 5B HEATER REPORT#

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-UT-05-220 BOP-UT-05-222 BOP-UT-05-221 BOP-UT-05-242 BOP-UT-05-243 BOP-UT-05-244 BOP-UT-05-245 BOP-RT-05-359 BOP-RT-05-360 BOP RT-05-361 51 52 52A 63 64 55 57 87 87A 87B P

E P

TANK P

E E

P R

P 0.432" 0.432" 0.432" 1.000" 0.300" 0.300" 0.300" 0.300" 0.300" I 0.179" 0.179" 0.264" 0.264" 0.264" 0.755" 0.164" 0.165" 0.165" 0.176" 0.136"10.090" 0.090" 0.413" 0.389" 0.841" 0.941" 0.283" 0.262" 0.294" 0.257" 0.281" 0.178"

> 88%

> 88%

> 88%

> 88%

> 88%

87%

> 88%

86%

> 88%

> 88%

UT UT UT UT UT UT UT RT RT RT M18 MSR 2A & 28 4h PASS TO CONDENSER A

n

=--------

REPORT #

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-341 BOP-RT-05-362 BOP-RT-05-363 BOP-RT-05-364 39 45 45A 45B V-2429 P

R P

NOTE: VALVE IS APPARENTLY CLOSED & COOL TO THE TOUCH.

0.300" 0.164" 0.278"

> 88%

0.300"10.179" 0.164"/ 0.090" 0.164" 0.179" 0.093" 0.155"

> 88%

RT RT RT RT 4

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M20 IB, 28, 3B LP HEATER DRAINS TO CONDENSER REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT.05-215 27 P

0.500" 0.250" 0.431" 86%

UT BOP-UT-05-228 28 E

0.500" 0.250" 0.445"

>88%

UT BOP-UT-05-227 29 P

0.500" 0.250" 0.424" 84%

UT M21 STEAM EXTRACTION TO PRESEP TANK "B" & 4B LP HEATER REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP.UT-05-179 36D P

0.375" 0.193" 0.309" 82%

UT BOP-UT-05-110 40 E

0.375" 0.201" 0.277" 72%

UT BOP-UT-05-183 40 E

0.375" 0.201" 0.273" 72%

UT BOP-UT-05-109 41 P

0.375" 0.195" 0.218" 57%

UT BOP.UT-05-182 41 P

0.375" 0.195" 0.217" 57%

UT BOP-UT-05-108 41A N

0.375" 0.200" 0.270" 72%

UT M22 STEAM EXTRACTION TO PRESEP TANK "A" & 4A LP HEATER REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-213 15A NIP 0.843" 0.425" 0.741" 87%

UT NOTE: INLET NOZZLE "X" OF THE 1A PRESEPARATOR.

BOP-UT.05-212 26A NIP 0.843" 0.425" 0.679" 80%

UT NOTE: INLET NOZZLE "W" OF THE 1A PRESEPARATOR.

BOP-UT-05-204 37A P

0.375" 0.199" 0.198" 52%

UT NOTE: ACTION REPORT 2005-1444.

BOP-UT-05-231 37B P

0.375" 0.193" 0.302" 80%

UT BOP-UT.05-249 42 P

0.375" 0.188" 0.329" 87%

UT M31 MSR 1A & I B TO HEATER DRAIN TANK & CONDENSER REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-099 35 E

0.594" 0.297" 0.584"

> 88%

UT BOP-UT-05-106 36 P

0.594" 0.297" 0.591"

> 88%

UT BOP-RT-05-408 44 P

0.432" 0.219" 0.410"

> 88%

RT BOP.RT-05-407 45 E

0.432" 0.219" 0.250" 58%

RT M32 MSR 2A & 2B TO HEATER DRAIN TANK REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-097 22 E

0.594" 0.297" 0.564"

> 88%

UT 5

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M33 MSR 1A, IB, 2A, 2B TO HTR DRAIN TANK REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-130 33 E

0.432" 0.220" 0.378" 87%

UT BOP-UT-05-129 34 P

0.432" 0.220" 0.401"

>88%

UT BOP-UT-05-120 35 E

0.432" 0.220" 0.402"

> 88%

UT BOP-UT-05-128 36 E

0.432" 0.220" 0.395"

> 88%

UT M418 SB HP HEATER DRAIN TO 4B LP HEATER REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-140 41 E

0.432" 0.221" 0.407"

> 88%

UT BOP-UT-05-087 65 P

0.594" 0.298" 0.538"

> 88%

UT BOP.UT-05-088 65A N

0.594" 0.300" 0.408" 68%

UT M45 PRESEPARATOR AIB TO HTR DRAIN TK & CONDENSER REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-123 21 E

0.432" 0.218" 0.378" 87%

UT BOP-UT-05-122 22 P

0.432" 0.217" 0.365" 84%

UT BOP-UT-05-121 23 E

0.432" 0.218" 0.390"

> 88%

UT M46B PRESEPARATOR AiB TO HEATER DRAIN TANK REPORT#

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL 1 READING NOMINAL METHOD BOP-UT-05-132 01A P

0.432" 0.217" 0.410"

> 88%

UT BOP-UT-05-144 06A P

0.432" 0.173" 0.419"

> 88%

UT BOP-UT.05-145 08 P

0.432" 0.173" 0.421"

> 88%

UT BOP-UT-05-187 11A R

0.432" 10.337" 0.302"10.236" 0.301"

> 88%

UT BOP-UT-05-146 61A P

0.432" 0.173" 0.423"

> 88%

UT BOP-UT-05-147 63 P

0.432" 0.173" 0.421"

> 88%

UT BOP-UT.05-186 66A R

0.432" /0.337" 0.302"10.236" 0.354" 87%

UT M75 STEAM EXTRACTION TO 5A & 5B HEATERS REPORT #

COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE ID WALL I READING NOMINAL METHOD BOP-UT-05-226 05A P

0.375" 0.228" 0.296" 78%

UT BOP-UT.05-191 10 P

0.375" 0.222" 0.259" 69%

UT BOP.UT-05-202 12A P

0.375" 0.277" 0.349"

> 88%

UT BOP-UT-05-117 15B P

0.375" 0.229" 0.316" 84%

UT BOP-UT-05-116 15C N

0.375" 0.229" 0.318" 84%

UT BOP-UT-05-081 23A P

0.375" 0.219" 0.274" 73%

UT BOP-UT-05-256 23A P

0.375" 0.219" 0.355"

> 88%

UT BOP-UT-05-083 24 E

0.375" 0.236" 0.320"

> 88%

UT BOP-UT.05-255 24 E

0.375" 0.236" 0.350"

> 88%

UT BOP.UT-05-082 25 P

0.375" 0.237" 0.305" 81%

UT BOP-UT-05-254 25A P

0.375" 0.219" 0.361"

> 88%

UT BOP.UT-05-253 25B P

0.375" 0.219" 0.354"

> 88%

UT BOP.UT-05-252 29 P

0.375" 0.237" 0.326" 87%

UT BOP-UT.05-248 29A P

0.375" 0.271" 0.288" 76%

UT 6

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M81 FEEDWATER DISCHARGE (TURBINE BLDG)

REPORT #

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-UT-05-138 BOP-UT-05-026 BOP-UT-05-033 BOP-UT-05-137 BOP-UT05-139 BOP-UT-05-192 06 06 06A 06A 19 29 R

R P

P R

E 0.938"! 0.844" 0.938" 10.844" 0.938" 0.938" 0.938" 10.844" 0.938" 0.695"10.633" 0.695"/0.633" 0.697" 0.697" 0.601"10.548" 0.602" 0.809"! 0.732" 1.071"1 0.806" 0.762" 0.755" 0.850"10.827" 0.843" 86%

> 88%

81%

80%

> 88%

>88%

UT UT UT UT UT UT M82 FEEDWATER DISCHARGE (INTERMEDIATE BLDG)

REPORT#

COMP.

ID BOP-UT-05-092 04A BOP-UT-05-105 04B BOP-UT-05-093 04C TYPE P

P P

NOMINAL WALL 1 0.938" 0.938" 0.938" T-MIN.

0.601" 0.601" 0.601" MINIMUM READING 0.906" 0.906" 0.874" PERCENT NOMINAL

> 88%

> 88%

> 88%

NDE METHOD UT UT UT M83 FEEDWATER DISCHARGE (INTERMEDIATE BLDG & FACADE)

REPORT #

COMP. TYPE ID BOP-UT-05-090 03A P

BOP-UT-05-091 03B P

BOP-UT-05-089 03C P

BOP.UT-05-184 07A P

BOP.UT-05-206 09 E

BOP-UT-05-207 10 P

BOP-UT-05-208 11 E

BOP.UT-05-209 12 P

NOMINAL WALL 1 0.938" 0.938" 0.938" 0.938" 0.938" 0.938" 0.938" 0.938" T-MIN.

0.601" 0.601" 0.601" 0.603" 0.602" 0.602" 0.602" 0.602" MINIMUM READING 0.924" 0.938" 0.861" 0.864" 0.856" 0.841" 0.899" 0.890" PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

NDE METHOD UT UT UT UT UT UT UT UT M84 FEEDWATER TO SIG 1A (INSIDE CVNT)

REPORT #

COMP. TYPE ID NOMINAL WALL 1 0.938" T-MIN.

0.602" MINIMUM READING 0.821" PERCENT NDE NOMINAL METHOD BOP-UT-05-224 11 E

87%

UT M88A SIG BLOWDOWN LINES (INTERMEDIATE BLDG.)

REPORT #

COMP. TYPE ID BOP-RT-05-409 20 E

BOP-RT-05-410 73 E

BOP-RT-05-411 75 E

BOP-RT.05-412 76 E

NOMINAL WALL 1 0.300" 0.300" 0.300" 0.300" T-MIN.

0.168" 0.168" 0.168" 0.167" MINIMUM READING 0.281" 0.268" 0.307" 0.301" PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

NDE METHOD RT RT RT RT 7

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

M88D REPORT#

BOP-RT-05-413 BOP-RT-05-365 BOP-RT-05-366 BOP-UT-05-367 BOP-UT-05-368 M90 REPORT #

BOP-UT-0S-239 BOP-UT-05-241 BOP-UT-05-240 M91 COMP. TYPE ID 17 E

19 E

20 P

21 E

26 E

S/G BLOWDOWN TO FLASH TANK (TURBINE BLDG.)

NOMINAL T-MIN.

MINIMUM WALL I READING 0.300" 0.168" 0.286" 0.300" 0.167" 0.289" 0.300" 0.166" 0.319" 0.300" 0.167" 0.276" 0.300" 0.168" 0.284" FEEDWATER CLEAN UP (CV-18)

NOMINAL T-MIN.

MINIMUM WALL I READING 0.432" 0.264" OA21" 0.432" 0.221" 0.384" 0.432" 0.219" 0.421" FEEDWATER CLEAN UP (CV-19)

PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

> 88%

NDE METHOD RT RT RT UT UT NDE METHOD UT UT UT COMP. TYPE ID 30 P

31 E

32 P

PERCENT NOMINAL

> 88%

> 88%

> 88%

REPORT #

COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-UT-05-232 BOP-UT405-233 BOP-UT-05-234 BOP-UT-05-148 BOP-UT-05-151 BOP-UT-05-152 BOP-UT-05-153 BOP-UT-05-154 BOP-UT-05-155 M92 REPORT#

BOP-UT-05-126 BOP-UT-05-127 33 34 35 36 37 38 39 40 41 R

E P

E P

E P

R P

0.432"1 0.337" 0.221"10.173" 0.343" 0.432" 0.222" 0.414" 0.432" 0.222" 0.428" 0.432" 0.173" 0.389" 0.432" 0.173" 0.418" 0.432" 0.173" 0.395" 0.432" 0.173" 0.416" 0.432" 10.337" 0.173"10.135" 0.386" 0.337" 0.135" 0.317" MAIN FEEDWATER PUMP RECIRCULATION NOMINAL T-MIN.

MINIMUM WALL 1 READING 0.594" 0.370" 0.567" 0.594" 0.370" 1.714"

> 88%

> 88%

> 88%

>88%

>88%

> 88%

> 88%

> 88%

> 88%

UT UT UT UT UT UT UT UT UT COMP. TYPE ID 71 P

72 P

PERCENT PERCENT NOMINAL

> 88%

> 88%

NDE METHOD UT UT M93 REPORT#

BOP-UT-05-133 BOP-UT-05-134 BOP-UT-05-135 BOP-UT-05-136 M110 REPORT#

BOP-UT-05-107 COMP. TYPE ID 27 E

28 P

33 E

34 P

FEEDWATER BYPASS NOMINAL WALL 1 0.337" 0.337":

0.337" 0.337" HEATER DRAIN TANK NOMINAL WALL 1 0.688" I 0.500" LINE T-MIN.

0.241 "

0.232" 0.232" 0.232" TO CONDENSER T-MIN.

0.344"/0.250" MINIMUM READING 0.312" 0.325" 0.285" 0.265" PERCENT NOMINAL

> 88%

> 88%

84%

78%

NDE METHOD UT UT UT UT NDE METHOD UT COMP. TYPE ID 18 R

MINIMUM READING 0.499" PERCENT NOMINAL

>88%

8

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S-Figures: Erosion Corrosion ISI Program Isometric for Small-Bore Line Components Systems of Examined Components Component thickness measurements were performed on the following systems:

S-FIGURE SYSTEMS S-1 MS TURBINE SHELL HEAT FLANGE (NORTH) HOT S-3 MS TURBINE SHELL HEAT FLANGE (NORTH) DRAIN VALVE %" 2912 S-4 MS DRAINS FROM MSR 1A & 1B TO CONDENSER S-7 TURBINE SHELL HEAT FLANGE (SOUTH) DRAINS S-13 MS VALVE 3675 TO CONDENSER "A" S-16 MS - FROM 30" THROUGH V3521 TO "A" CONDENSER DRAIN HEADER & V3605 S-21 MS - 30" THROUGH V3520 TO "A" CONDENSER DRAIN HEADER S-23 MS 12" - THROUGH V3850 PAST V2918 TO HP TURBINE S-24 MS - FROM 12" LINE THROUGH V3845 PAST V2520 TO HP TURBINE S-25 MS - FROM 12" LINE THROUGH V3860 S-26 MS 12" LINE THROUGH V3855 PAST V3856A TO HP TURBINE S-27 GLAND STEAM - "A" & "B" CONDENSERS THROUGH LGS01, LGS02, LGS03, LGS04 S-31 MSR-FROM "2B" THROUGH V2487 & LMS14, LMS13, V2495 BACK TO MSR-2B S-36 FW HEATER VENTS - FROM 3A & 3B HTRS TO "A" & "B" CONDENSERS S-37 EXTRACTION STEAM 14" - FROM V1906 & V1907 TO MAIN CONDENSER "A" THRU V1973 &V1972 S-41 EXTRACTION STEAM - FROM 12" LINE THRU V5697, V5650 & V5653 TO MAIN CONDENSER "A" S-42 EXTRACTION STEAM - FROM 12" LINE THRU V5696, V5645 & V5648 TO MAIN CONDENSER "A" S48 GLAND STEAM FROM 6" LINE THROUGH V2936, 2925, 2927 TO MAIN CONDENSER "A" HOTWELL S-53 MAIN STEAM FROM 24" LINE THROUGH V3870, 3837B, 3545A & 3545.

S-56 MS FROM 24" LINE THROUGH V8511, 3599, 3601 TO MAIN CONDENSER "A".

S-57 GLAND STEAM FROM HP TURBINE THROUGH LGS05 & LGS08 TO 12" LINE V3881 & 3834.

S-59 GLAND STEAM FROM 31" LINE THROUGH V3558, 3554 TOWARDS GLAND STEAM CONDENSER.

S-64 MOISTURE SEPARATOR REHEATER -WARM BYPASS TO V3425 S-65 MOISTURE SEPARATOR REHEATER - FROM 8" MS THROUGH V8506, 8507, 8508, 8509 TO CONDENSER "A" S-66 FW HTR VENTS-FROM 4A & 4B LP HTRS TO CONDENSER "B" THROUGH V4427, 4425, 4428, 4426 S-67 FW HTR VENTS-FROM 5A & 5B LP HTRS TO CONDENSER "B" THROUGH V 4411,4413, 4412,4414 S-69 MS - FROM V 3544 THROUGH V 7786 TO MAIN CONDENSER "A" S-70 MS - FROM V8517, V3584 & V3422 TO SMS11, SMS12, SMS13, SMS14 S-71 MS DRAIN -FROM AFTERCOOLER (ECD07B) THRU V3235 TO MAIN CONDENSER "B" S-73 EXTRACTION STEAM - %" LINE NEAR V5722 THROUGH ZGS07 TO 12" HEADER TO CONDNESER "A" S-79 MSR - FROM RELIEF VALVE HEADER THROUGH V3664, 3663, 3662 TO 8" LINE TO CONDENSER "B" S-80 CONDENSATE - FROM 12" LINE THRU V4151 & V4100 TO HEATER DRAIN TANK (TFW01)

S-1 MS TURBINE SHELL HEAT FLANGE (NORTH) HOT REPORT COMP TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL READING NOMINAL METHOD BOP-RT-05-240 01 P

0.154" 0.077" 0.155"

> 88%

RT BOP-RT-05-241 2909 V

0.154" 0.077" 0.257"

> 88%

RT BOP-RT-05-242 02 P

0.154" 0.077" 0.164"

> 88%

RT BOP-RT-05-243 03 E

0.154" 0.077" 0.252"

> 88%

RT BOP-RT-05-244 04 P

0.154" 0.077" 0.199"

> 88%

RT BOP-RT-05-245 05 E

0.154" 0.077" 0.327"

> 88%

RT BOP-RT-05-246 06 P

0.154" 0.077" 0.190"

> 88%

RT 9

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S3 MS TURBINE SHELL HEAT FLANGE (NORTH) DRAIN VALVE %" 2912 REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT-05-247 57 E

0.154" 0.077" 0.250"

> 88%

RT BOP-RT-05-248 58 P

0.154" 0.077" 0.110" 71%

RT NOTE: ACTION REPORT 204-3292, REPLACED DURING RFO2005. WO # 20404638.

BOP.RT.05-249 59 E

0.154" 0.077" 0.248"

> 88%

RT BOP-RT-05-250 60 P

0.154" 0.077" 0.083" 53%

RT NOTE: ACTION REPORT 204-3292, REPLACED DURING RFO2005. WO # 20404638.

BOP-RT-05-251 61 E

0.154" 0.077" 0.245"

>88%

RT BOP-RT-05-252 62 P

0.154" 0.077" 0.173"

> 88%

RT S4 REPORT NUMBER BOP-RT-05-253 BOP-RT-05-254 BOP-RT-05-255 COMP.

ID 01 02 03 MS DRAINS FROM MSR 1A & IB TO CONDENSER TYPE NOMINAL T-MIN.

MINIMUM WALL I READING P

0.154" 0.077" 0153" E

0.154" 0.077" 0.255" P

0.154" 0.077" 0.153" S7 REPORT NUMBER BOP-RT-05-256 BOP-RT-05-257 BOP-RT-05-258 BOP-RT-05-259 BOP-RT.05-260 COMP.

ID 03 04 05 06 07 TURBINE SHELL HEAT FLANGE (SOUTH) DRAINS TYPE NOMINAL T-MIN.

MINIMUM WALL 1 READING P

0.154" 0.077" 0.168" E

0.154" 0.077" 0.341" P

0.154" 0.077" 0.147" V

0.154" 0.077" 0.241" P

0.154" 0.077" 0.142" PERCENT NOMINAL

> 88%

> 88%

> 88%

PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

> 88%

NDE METHOD RT RT RT NDE METHOD RT RT RT RT RT S13 REPORT NUMBER BOP-RT-05-261 BOP-RT-05-262 BOP-RT-05-263 S16 REPORT NUMBER BOP-RT-05-264 BOP-RT-05-265 BOP-RT-05-266 COMP.

ID 11 12 13 MS VALVE 3675 TO CONDENSER "A" TYPE NOMINAL T-MIN.

WALL I P

0.179" 0.090" E

0.179" 0.090" P

0.179" 0.090" MS - FROM 30" THROUGH V3521 TO "A" TYPE NOMINAL T-MIN.

WALL I P

0.154" 0.077" E

0.154" 0.077" P

0.1 54" 0.077" MINIMUM READING 0.214" 0.295" 0.183" CONDENSER MINIMUM READING 0.147" 0.237" 0.152" PERCENT NOMINAL

> 88%

> 88%

> 88%

DRAIN HEADER &

PERCENT NOMINAL

> 88%

>88%

> 88%

NDE METHOD RT RT RT V3605 NDE METHOD RT RT RT COMP.

ID 73 74 75 10

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S21 MS - 30" THROUGH V3520 TO "A" CONDENSER DRAIN HEADER REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-RT-05-267 BOP-RT-05-268 BOP-RT-05-280 BOP-RT-05-281 BOP-RT-05-282 42 P

0.154" 43 U

0.154" 44 P

0.154" 45 E

0.154" 46 P

0.154" 0.077" 0.077" 0.077" 0.077" 0.077" 0.146" 0.212" 0.159" 0.217" 0.133"

> 88%

> 88%

> 88%

> 88%

86%

RT RT RT RT RT S23 MS 12" - THROUGH V3850 PAST V2918 TO HP TURBINE REPORT NUMBER COMP. TYPE ID NOMINAL WALL 1 T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-209 BOP-RT-05-203 BOP-RT-05-204 BOP-RT-05-205 BOP.RT-05-206 BOP-RT-05-207 BOP-RT-05.208 24 E

0.200" 25 E

0.200" 26 P

NIA 27 P

0.200" 30 P

0.179" 31 E

0.179" 32 P

0.179"

• 0.101" 0.101" NIA 0.101" 0.090",

0.090",

0.090",

0.149" 0.149" NIA 0.173" 0.132" 0.150" 0.186" 74%

74%

N/A 86%

73%

> 88%

> 88%

RT RT RT RT RT RT RT S24 MS - FROM 12" LINE THROUGH V3845 PAST V2520 TO HP TURBINE REPORT NUMBER COMP. TYPE NOMINAL ID WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-198 22 BOP-RT-05-199 23 BOP-RT-05-200 24 BOP-RT-05-201 25 BOP-RT-05-202 27 BOP-RT-05-179 28 NOTE: ACTION REPORT 2004-2458, BOP-RT-05-180 29 BOP-RT-05-181 30 E

0.200" 0.101" E

0.200" 0.101" P

N/A N/A P

0.200" 0.101" P

0.200" 0.101" P

0.179" 0.090" REPLACED DURING RFO 2005 WO# 20403834.

E 0.179" 0.090" P

0.179" 0.090" 0.162" 0.162" NIA 0.144" 0.195" 0.083" 81%

81%

N/A 72%

> 88%

41%

RT RT RT RT RT RT RT RT 0.174" 0.174"

> 88%

> 88%

S25 MS - FROM 12" LINE THROUGH V3860 REPORT NUMBER COMP. TYPE NOMINAL ID WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-318 BOP-RT-05-317 BOP-RT-05-325 BOP-RT-05-326 02 E

0.200" 03 P

0.200" 04 E

0.200" 05 P

0.200" 0.101" 0.101" 0.101" 0.101" 0.265" 0.164" 0.289" 0.167n

> 88%

82%

> 88%

82%

RT RT RT RT 11

S2 RE NU BO BO R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) 7 GLAND STEAM - "A" & "B" CONDENSERS THROUGH LGS01, LGS02, LGS03, LGS04 PORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE MBER ID WALL I READING NOMINAL ME1 P-RT-05-225 18 P

0.179" 0.090" 0.172"

> 88%

RT P-RT.05-226 19 P

0,179" 0.090" 0.172"

> 88%

RT

.HOD S31 REP NUM BOP-BOP.

BOP.

BOP-BOP.

MSR-FROM "2B" THROUGH V2487 & LMS14, LMS13, V2495 BACK TO MSR-2B ORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE IBER ID WALL I READING NOMINAL ME'

-RT-05-283 14 P

0.200" 0.101" 0.221"

> 88%

RT

-RT-05-284 15 P

0.200" 0.101" 0.200"

> 88%

RT

-RT-05-285 16 P

0.200" 0.101" 0.204"

> 88%

RT

-RT-05-286 17 T

0.200" 0.101" 0.283"

> 88%

RT

.RT-05-287 22 P

0.200" 0.101" 0.221"

> 88%

RT rHOD S36 REPORT NUMBER BOP-RT-05-222 BOP-RT-05-223 BOP-RT-05-224 FW HEATER VENTS - FROM 3A & 3B HTRS TO "A" & "B" CONDENSERS COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT ID WALL I READING NOMINAL 08 E

0.200" 0.100" 0.243"

> 88%

09 P

0.200" 0.100" 0.196"

> 88%

10 T

0.200" 0.100" 0.313"

> 88%

S37 REF NW BOP BOF BOP BOP BOP EXTRACTION STEAM 14" - FROM VI 906 & VI 907 TO MAIN CONDENSER "A" THRU VI 973 8

'ORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT ABER ID WALL I READING NOMINAL

'-RT-05-288 42 P

0.200" 0.100" 0.188"

> 88%

'-RT-05-289 43 T

0.200" 0.100" 0.266"

> 88%

'-RT-05-290 48 P

0.200" 0.100" 0.191"

> 88%

'-RT.05-291 49 E

0.200" 0.100" 0.150" 75%

'-RT-05-292 50 P

0.200" 0.100" 0.127" 63%

NDE METHOD RT RT RT

,VI972 NDE METHOD RT RT RT RT RT S41 EXTRACTION STEAM - FROM 12" LINE THRU V5697, V5650 & V5653 TO MAIN CONDENSER "A" REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT-05-227 29 P

0.200" 0.100" 0.181"

> 88%

RT BOP-RT-05-228 30 E

0.200" 0.100" 0.195"

> 88%

RT BOP-RT-05-229 31 P

0.200" 0.100" 0.146" 74%

RT 12

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S42 EXTRACTION STEAM - FROM 12" LINE THRU V5696, V5645 & V5648 TO MAIN CONDENSER "A" REPORT NUMBER COMP. TYPE NOMINAL ID WALL I T-MIN.

BOP-RT-05-233 18 E

0.200" 0.100" BOP-RT-05-234 19 P

0.200" 0.100" NOTE: ACTION REPORT 2004-2503, REPLACED DURING RFO 2005, WO# 20403869.

BOP-RT-05-230 29 P

0.200" 0.100" BOP-RT-05-231 30 E

0.200" 0.100" BOP-RT-05-232 31 P

0.200" 0.100" NOTE: ACTION REPORT 2004-2502, REPLACED DURING RFO2005, WO# 20403869.

MINIMUM READING 0.269"

0. 098" 0.212" 0.250" 0.085" PERCENT NOMINAL

> 88%

49%

> 88%

> 88%

43%

NDE METHOD RT RT RT RT RT S48 GLAND STEAM FROM 6" LINE THROUGH V2936, 2925, 2927 TO MAIN CONDENSER "A" HOTWELL REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-1 82 BOP-RT-05-1 83 BOP-RT-05-1 84 68 P

0.154" 69 E

0.154" 70 P

0.154" 0.077" 0.077" 0.077" 0.148" 0.229" 0.157"

> 88%

> 88%

> 88%

RT RT RT S53 MS FROM 24" LINE THROUGH V3870, 3837B, 3545A & 3545.

REPORT NUMBER COMP. TYPE NOMINAL ID WALL I BOP-RT-05-327 BOP-RT-05-331 BOP-RT-05-332 BOP-RT-05-333 BOP-RT-05-328 BOP-RT-05-329 BOP-RT-05-330 01 E

0.400" 02 P

0.200" 03 V

0.200" 04 P

0.200" 05 P

0.200" 06 E

0.200" 07 P

0.200" T-MIN.

0.200" 0.101" 0.101 "

0.101" 0.101" 0.101" 0.101" MINIMUM READING 0.435" 0.203" 0.339" 0.418" 0.218" 0.236" 0.214" PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

NDE METHOD RT RT RT RT RT RT RT S56 MS FROM 24" LINE THROUGH V8511, 3599, 3601 TO MAIN CONDENSER "A".

REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-1 93 BOP-RT-05-1 94 BOP-RT-05-195 84 P

0.154" 85 E

0.154" 86 P

0.154" 0.077" 0.077" 0.077" 0.162" 0.300" 0.143"

> 88%

> 88%

> 88%

RT RT RT S57 GLAND STEAM FROM HP TURBINE THROUGH LGS05 & LGS08 TO 12" LINE V3881 & 3834 REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-RT-05-293 BOP-RT-05-294 BOP-RT-05-295 BOP-RT-05-296 BOP-RT-05-297 26 P

0.179" 27 E

0.179" 28 P

0.179" 29 E

0.179" 30 P

0.179" 0.090",

0.090",

0.090",

0.090" 0.090" 0.185" 0.268" 0.190" 0.292" 0.181"

> 88%

> 88%

> 88%

> 88%

> 88%

RT RT RT RT RT 13

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S-59 REP(

NUM BOP-BOP-I BOP-I BOP-BOP-BOP.

GLAND STEAM FROM 31" LINE -V3558, 3554 TOWARDS GLAND STEAM CONDENSER.

ORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE BER ID WALL I READING NOMINAL MEl RT-05-339 14B P

0.300" 0.150" 0.246" 82%

RT RT-05-334 28 P

0.200" 0.100" 0.219"

> 88%

RT RT-05-335 29 P

0.200" 0.100" 0.272"

> 88%

RT RT-05-336 30 P

0.200" 0.100" 0.205"

> 88%

RT RT-05-337 30A E

0.200" 0.100" 0.371"

>88%

RT RT-05-338 30B P

0.200" 0.100" 0.237"

> 88%

RT THOD S-64 REPORT NUMBER BOP-RT-05-298 BOP-RT-05-299 BOP-RT-05-300 S-65 REPORT NUMBER BOP-RT-05-301 BOP-RT-05-302 BOP-RT-05-303 BOP-RT-05-475 MOISTURE SEPARATOR REHEATER - WARM BYPASS TO V3425 COMP. TYPE NOMINAL T-MIN.

MINIMUM ID WALL I READING 14 P

0.218" 0.116" 0.197" 15 E

0.218" 0.116" 0.306" 16 P

0.218" 0.116" 0.207" PERCENT NOMINAL

> 88%

> 88%

> 88%

NDE METHOD RT RT RT NDE METHOD RT RT RT RT MSR-FROM 8" MS THROUGH V8506, 8507, 8508, 8509 TO CONDENSER "A" COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT ID WALL I READING NOMINAL 23 P

0.218" 0.116" 0.215"

> 88%

24 E

0.218" 0.116" 0.294"

> 88%

25 P

0.218" 0.116" 0.211"

> 88%

BC P

0.276" 0.145" 0.204" 74%

S-66 FW HTR VENTS-FR 4A & 4B LP HTRS TO CONDENSER "B", V4427, 4425,4428, 4426 REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT-05-220 11 E

0.179" 0.090" 0.159"

> 88%

RT BOP-RT-05-221 12 P

0.179" 0.090" 0.089" 50%

RT NOTE: ACTION REPORT 2004-2494, REPLACED DURING RF02005, WO# 20403867.

BOP-RT-05-235 63 P

0.179" 0.090" 0.123" 69%

RT BOP-RT-05-236 64 E

0.179" 0.090" 0.179"

> 88%

RT BOP-RT.05-237 67 P

0.179" 0.090" 0.137" 77%

RT BOP-RT-05-238 68 E

0.179" 0.090" 0.156" 87%

RT S-67 FW HTR VENTS-FR 5A & 5B LP HTRS TO CONDENSER "B", V 4411,4413,4412,4414 REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT.05-196 13 T

0.179" 0.090",

0.260"

> 88%

RT BOP-RT-05-197 25 T

0.179" 0.090" 0.231"

> 88%

RT 14

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S-69 REPORT NUMBER BOP-RT-05-189 BOP-RT-05-190 BOP-RT-05-191 BOP-RT-05-192 S-70 REPORT NUMBER BOP-RT-OS-219 BOP-RT-05-218 MS - FROM V 3544 THROUGH V 7786 TO MAIN CONDENSER "A" COMP. TYPE NOMINAL T-MIN.

MINIMUM ID WALL I READING 37 E

0.200" 0.101" 0.264" 38 P

0.200" 0.101" 0.187" 39 E

0.200" 0.101 "

0.257" 40 P

0.200" 0.101" 0.215" PERCENT NOMINAL

> 88%

> 88%

> 88%

> 88%

NDE METHOD RT RT RT RT NDE METHOD RT RT MS - FROM V8517, V3584 & V3422 TO SMS1I, SMS12, SMS13, SMS14 COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT ID WALL I READING NOMINAL 01 T

0.200" 0.101 "

0.164" 82%

31 T

0.179" 0.090" 0.212"

> 88%

S-71 MS DRAIN -FROM AFTERCOOLER (ECD07B) THRU V3235 TO MAIN CONDENSER "B" REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT-05-305 52 P

0.179" 0.090" 0.162"

> 88%

RT BOP.RT-05-306 53 E

0.179" 0.090" 0.221"

>88%

RT BOP-RT-05-307 54 P

0.179"

-0.090" 0.162"

> 88%

RT S-73 REP(

NUM BOP-BOP-BOP-BOP-EXTRACTION STEAM - %" LINE NEAR V5722, ZGS07 TO 12" HEADER TO CONDNESER "A"

)RT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE BER ID WALL I READING NOMINAL MEl RT-05-185 15 E

0.154" 0.077" 0.284"

> 88%

RT RT-05-186 16 P

0.154" 0.077" 0.147"

> 88%

RT RT-05-187 17 E

0.154" 0.077" 0.154"

> 88%

RT RT-05-188 18 P

0.154" 0.077" 0.150"

> 88%

RT

.HOD S-79 MSR - FROM RELIEF VALVE HEADER, V3664, 3663, 3662 TO 8" LINE TO CONDENSER "B" REPORT COMP. TYPE NOMINAL T-MIN.

MINIMUM PERCENT NDE NUMBER ID WALL I READING NOMINAL METHOD BOP-RT-05-308 40 P

0.191" 0.096" 0.212"

> 88%

RT BOP-RT-05-309 41 V

0.191" 0.096" 0.128" 67%

RT NOTE: ACTION REPORT 2004-3302, V-3666, ENGINEERING EVALUATION - ACCEPT.

BOP-RT-05-310 42 P

0.191" 0.096" 0.216"

> 88%

RT BOP-RT-05-311 43 V

0.191" 0.096" 0.328"

> 88%

RT BOP-RT-05-312 44 P

0.191" 0.096" 0.227"

>88%

RT BOP-RT-05-313 45 E

0.191" 0.096" 0.269"

>88%

RT BOP-RT-05-314 46 P

0.191" 0.096" 0.222"

> 88%

RT 15

R. E. Ginna Nuclear Power Plant In-Service Inspection (lSI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

S80 CONDENSATE - FROM 12" LINE THRU V4151 & V4100 TO HEATER DRAIN TANK (TFW01)

REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-RT-05-210 BOP-RT-05-21 1 BOP-RT-OS-212 BOP.RT-05-213 BOP-RT-05-214 BOP-RT-0S-215 BOP-RT-05-216 BOP-RT-05-217 26 R

0.218" 27 P

0.179" 28 P

0.179" 36 P

0.179" 37 P

0.179" 38 R

0.218" 41 P

0.218" 42 E

0.218" 0.109" 0.090" 0.090" 0.090" 0.090" 0.109" 0.109" 0.109' 0.306" TOO THICK 0.165" 0.171" TOO THICK 0.310" 0.218" 0.287"

> 88%

N/A

> 88%

> 88%

NIA

> 88%

> 88%

> 88%

RT RT RT RT RT RT RT RT 3301 3-1 904 EXTRACTION STEAM REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-RT-05-093 BOP-RT-05-094 BOP-RT-05-095 3301 3-1 271 V3827 V3827 V3827 P

0.280 E

0.280 E

0.280 0.140 0.140 0.140 0.268 0.282 0.295

> 88%

>88%

> 88%

RT RT RT RAD WASTE PROCESSING - PRIMARY DI ROOM REPORT NUMBER COMP. TYPE NOMINAL ID WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-RT-05-396 BOP-RT-05-398 BOP-RT-05-399 BOP-RT-05-400 BOP-RT-05401 BOP-RT-05-402 BOP-RT-05 403 BOP-RT-05-390 BOP-RT-05-391 BOP.RT-05.392 BOP-RT-05-393 BOP-RT-05-394 BOP-RT-05-395 I

V18 2

V18 3

V18 4

V18 S

V18 6

V18 7

V18 1

P 2

P 3

P 4

P 5

P 6

P 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.109 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.063 0.127 0.123 0.121 0.118 0.119 0.115 0.119 0.158 0.120 0.171 0.103 0.159 0.150

>88%

> 88%

>88%

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

> 88%

>88%

> 88%

> 88%

RT RT RT RT RT RT RT RT RT RT RT RT RT 3301 3-1 273 RAD WASTE PROCESSING - "A" & "B" WASTE GAS COMPRESSOR REPORT NUMBER COMP. TYPE NOMINAL ID WALL I T-MIN.

MINIMUM READING PERCENT NOMINAL NDE METHOD BOP-RT-05-397 BOP-RT-05-404 BOP-RT.05405 BOP-RT-05406 U/S P

0.140 DJS P

0.140 U/S P

0.140 D/S P

0.140 0.063 0.063 0.063 0.063 0.120 0.106 0.159 0.111

> 88%

> 88%

> 88%

> 88%

RT RT RT RT 16

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005) 33013-1911 WATER TREATMENT-CONDENSATE POLISHING SYSTEM REPORT NUMBER COMP. TYPE ID NOMINAL WALL I T-MIN.

MINIMUM READING PERCENT NDE NOMINAL METHOD BOP-UT-05-056 BOP-UT-05-057 BOP-UT-05-058 BOP-UT-05-059 BOP-UT-05-060 BOP-UT-05-061 BOP4UT-05-074 BOP-UT-05-075 BOP-UT-05-076 BOP-UT-05-159 BOP-UT-05-160 01 E

0.375 02 E

0.375 03 P

0.375 04 R

0.375 05 E

0.375 06 E

0.375 01 E

0.365 02 E

0.365 03 E

0.365 04 P

0.365 05 P

0.365 0.281 0.274 0.281 0.281 0.281 0.281 0.274 0.274 0.274 0.229 0.229 0.325 0.282

• 0.306 0.372 0.381 0.394 0.272 0.279 0.267 0.281 0.297 86%

75%

81%

> 88%

> 88%

> 88%

72%

73%

71%

75%

81%

UT UT UT UT UT UT UT UT UT UT UT Service Water In addition to the Erosion/Corrosion Program, Service Water components were examined from plant drawings.

Drawinq #

Plant System C-381-358 Sheet 02:

C-381-358 Sheet 03:

C-381-358 Sheet 04:

C-381-358 Sheet 05 C-381-358 Sheet 06:

C-381-358 Sheet 07:

C-381-358 Sheet 09:

C-381-358 Sheet 10:

C-381-358 Sheet 11:

C-381-358 Sheet 12:

C-381-358 Sheet 13:

C-381-358 Sheet 14:

C-381-358 Sheet 15:

C-381-358 Sheet 16:

C-381-358 Sheet 17:

C-381-358 Sheet 26:

C-381-358 Sheet 29:

C-381-358 Sheet 34:

C-381-024-1:

C-381-024-3:

SW-from Component Cooling HTX. To Anchor at Column "L".

SW-Return from Component Cooling Hx. To Column "Q".

SW-Supply Header to Distribution Manifold.

SW-Return from Spent Fuel Pit Heat Exchanger.

SW-Return from Spent Fuel Pit Heat Exchanger.

SW-Return from Penetration Cooling Coil Plenum.

SW-Int. Bldg. Above El.253'-6" from Pen. 308,315 & 323 to Col. 7 SW-Int. Bldg. Above 253"-6" fr Column 7 to Chiller IA & I B.

SW-Int. Bldg. Above 253'-6" fr Valve 4624C to 14" HDR.

SW-Int. Bldg. above El. 253' 6" from Pen. # 209 & # 201 to 14" Header.

SW-Int. Bldg. above 253'-6" from Hdr. to Pen. # 312, 316, 319, & 320.

SW-Int. Bldg. above 253'-6" - 16" & 20" Headers SW-Int. Bldg. above 253'-6" from 14" HDR to Chillers IA & I B.

SW-Int. Bldg. from 14" Header to PEN 201 & 209.

SW-From Main 20" Header to M.D. Aux. FW pumps IA & I B SW to Containment Recirculation Cooling units (la & Ib) Motors Station Service Water from Pen. 209 to Reactor Cavity Cooler.

"A" & "B" Service Water Pumps in Screen House.

Service Water Suction line Loop B to Aux F.W. Pump Service Water Suction line Loop B to Aux F.W. Pump 17

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

Service Water Result Details The following list provides examination result in details on Service Water components, by drawing number and system description.

The component type classification specified in the list below corresponds to the following:

P = Pipe E = Elbow R = ReducerlExpander T = Tee C=Cap N = Nozzle F = Flange C-381-358 Sheet 2 SW - from Component Cooling HTX to Anchor "L" Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT-05-035 1420-1430 E

0.375" 0.200".

0.313" 83%

UT BOP-UT-05-176 V4538 E

0.365" 0.186" 0.304" 81%

UT BOP-UT-05-175 V4538 R

0.365" 0.186" 0.206" 56%

UT BOP-UT-05-036 2120-2140 E& P 0.375" 0.219" 0.308" 82%

UT C-381-358 Sheet 3 SW - return from Component Cooling HTX, V-4619, 4620, 8689 Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT.05-157 1580 P

0.375" 0.219" 0.283" 75%

UT BOP-UT-05-027 1105 F

0.365" 0.247" 0.484"

>88%

UT BOP-UT-05-034 1105-1110 P

0.375" 0.247" 0.40"

> 88%

UT BOP-UT-05-028 1110 R

0.365" 0.247" 0.330"

>88%

UT BOP-UT-05-031 1120 E

0.365" 0.247" 0.339"

>88%

UT BOP-UT-05-032 1130 P

0.365" 0.247" 0.362"

>88%

UT BOP-UT-05-170 1105 F

0.365" 0.247" 0.488"

>88%

UT BOP-UT-05-169 1110 R

0.365" 0.247" 0.333"

>88%

UT BOP-UT-05-171 1120 E

0.365" 0.247" 0.340"

>88%

UT BOP-UT-05-172 1130 P

0.365" 0.247" 0.361"

>88%

UT BOP-UT-05-070 2640 P

0.365" 0.231" 0.233" 62%

UT BOP-UT-05-069 2650 E

0.365" 0.231" 0.301" 80%

UT BOP-UT-05-068 2660 P

0.365" 0.231" 0.325" 86%

UT BOP-UT-05-038 2690 R

0.375" 0.247" 0.40"

>88%

UT BOP-UT-05-066 2690 R

0.375" 0.247" 0.319" 85%

UT BOP-UT-05-037 2690-2680 E

0.375" 0.247".

0.127" 33%

UT BOP-UT-05-067 2690-2680 E

0.375" 0.247" 0.425"

> 88%

UT C-381-358 Sheet 4 SW-Supply Header to Distribution Manifold.

Typ Nomna T-Min...................Minimum...................Percent................

Report Number Component ID (NODE)

Type Nominal Wall P

0.216" T-Min. Minimum Value Reading 0.101" 0.173" Percent Nominal 80%

NDE Method BOP-RT-05-115 530-550 RT 18

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

C-381-358 Sheet 5 SW-Return from Spent Fuel Pit Heat Exchanger.

Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT-05-045 2410-2420 E

0.280" 0.137" 0.216" 77%

UT C-381-358 Sheet 6 SW-Return from Spent Fuel Pit Heat Exchanger.

Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-163 500-510 P

0.280" 0.137" 0.208" 74%

RT BOP-RT-05-164 510-520 E

0.280" 0.137" 0.225" 80%

RT BOP-RT-05-165 520-540 E

0.280" 0.137" 0.247" 88%

RT BOP-RT-05-166 540-550 N

0.280" 0.137" 0.224" 80%

RT C-381-358 Sheet 7 SW-Return from Penetration Cooling Coil Plenum.

Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP.RT-05-117 1380-1400 T

0.216" 0.101" 0.182" 84%

RT C-381-358 Sheet 9 SW-Intermediate Bldg. AboveEl.253'-6" from Pen. 308,315 & 323 to Col. 7 Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT-05-188 380 P

0.375" 0.200" 0.269" 72%

UT BOP-UT-05-177 1830-1860 P

0.322" 0.161" 0.257" 80%

UT C-381 -358 Sheet 10 SW-Int Bldg. Above 253"-6" fr Column 7 to Chiller IA & I B.

Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT-05-039 1130-1140 E

0.237" 0.113" 0.162" 68%

UT C-381-358 Sheet 11 SW-Int. Bldg. Above 253'-6" fr Valve 4624C to 14" HDR.

ReotCmoet TpDNmnl TMn iiu

Perce, NDE Report Component Number ID (NODE)

BOP-RT-05-119 V4655 Type Nominal T-Min.

Minimum Perce Wall Value Reading Nomih P

0.113" 0.064" 0.069" 61%

nt

,ial NDE Method RT 19

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

C-381-358 Sheet 12 SW - Int. Bldg. above El. 253' 6" from Pen. 209& 201 to 14" Header Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-113 PEN201 4070 E

0.154" 0.072" 0.146" 88%

RT BOP-RT-05-114 PEN209 3870 E

0.154" 0.072" 0.134" 87%

RT C-381-358 Sheet 13 Report Component Number ID (NODE)

BOP-UT-05-161 PEN316 3000 BOP-UT-05-162 PEN316 3020 UT SW-Intermediate Bldg. Above 253'-6" from Header to Pen. # 312, 316, 319, & 320.

Type Nominal T-Min. Minimum Percent NDE Wall Value Reading Nominal Method E

0.322" 0.161" 0.301" 93%

UT P

0.322" 0.161" 0.242" 75%

C-381-358 Sheet 14 SW-Int. Bldg. above 253'-6" - 16" & 20" Headers Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-384 4510-4520 P

0.237" 0.142" 0.218" 92%

UT C-381-358 Sheet 15 SW-Int. Bldg. above 253'-6" from 14" HDR to Chillers 1A & lB.

Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-118 1830-1870 P

0.216" 0.101" 0.111" 51%

RT C-381-358 Sheet 16 SW-Int. Bldg. from 14" Header to PEN 201 & 209 Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-112 PEN201 2570 E

0.154" 0.072" 0.148"

> 88%

RT BOP-RT-05-111 PEN209 2370 E

0.154" 0.072" 0.133"

> 88%

RT C-381-358 Sheet 17 SW-From Main 20" Header to M.D. Aux. FW pumps 1A & I B Report Component Number ID (NODE)

BOP-RT-05-378 275 DIS BOP-RT-05-379 500 UIS BOP-RT-05-380 495490 BOP-RT-05-381 500-505 BOP-RT-05-382 505-515 BOP-RT-05-383 485-480 Type Nominal T-Min.

Minimum Percent Wall Value Reading Nominal E

0.237" 0.142" 0.225"

> 88%

P 0.237" 0.142" 0.25"

> 88%

P 0.237" 0.142" 0.23"

> 88%

P 0.237" 0.142" 0.239"

> 88%

P 0.237" 0.142" 0.241"

> 88%

P 0.237" 0.142" 0.232"

> 88%

NDE Method RT RT RT RT RT RT 20

R. E. Ginna Nuclear Power Plant In-Service Inspection (ISI) Report Fourth Interval (2000-2009), Second Period, Second Outage (2005)

C-381-358 Sheet 26 SW to Containment Recirculation Cooling Units (1A & 1B) Motors Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-471 1950-2300 P

0.154" 0.072" 0.174"

> 88%

RT C-381-358 Sheet 29 Station Service Water from Pen. 209 to Reactor Cavity Cooler Report Component Type Nominal T-Min. Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-472 10-20 P

0.203" 0.094" 0.132" 65%

RT BOP-RT-05-472 20-30 P

0.203" 0.094" 0.182"

> 88%

RT BOP-RT-05-472 30-40 P

0.203" 0.094" 0.177" 87%

RT BOP-RT-05-472 40-50 P

0.203" 0.094" 0.189"

> 88%

RT BOP-RT-05-472 50-80 P

0.203" 0.094" 0.183"

> 88%

RT C-381-358 Sheet 34 "A" & "B" Service Water Pumps in Screen House Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-UT-05-055 2580-2590 E

0.375" 0.200" 0.310" 83%

UT BOP-UT-05-056 2060-2080 E

0.375" 0.161" 0.270" 72%

UT C-381-024 Sheet I SW-SUCTION LINE LOOP B TO AUX FW PUMP Report Component Type Nominal T-Min.

Minimum Percent NDE Number ID (NODE)

Wall Value Reading Nominal Method BOP-RT-05-116 60-90 E

0.237" 0.113" 0.130" 55%

UT C-381-024 Sheet 3 SW-SUCTION LINE LOOP B TO AUX FW PUMP Report Number Component ID (NODE)

Type Nominal Wall T-Min.

Minimum Value Reading Percent Nominal NDE Method BOP-RT-05-120 960-2960 E

0.237" 0.113" 0.205"

> 88%

UT 21