NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval

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Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval
ML030570113
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/25/2003
From: Dacimo F
Entergy Nuclear Indian Point 2, Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-03-026
Download: ML030570113 (26)
v • d • e


Text

AM___ Entergy Nuclear Northeast Entergy Nuclear Operations, Inc Entergy Nuclear Indian Point 2, LLC

-ErntffyP 0Box 249 Buchanan, NY 10511 February 25, 2003 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-03-026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555-0001

Subject:

2002 Refueling Outage Inservice Inspection (ISI) Program Summary Report Third Outage, Second Period, Third Interval.

Reference:

1) Con Edison Letter to NRC dated April 2, 2001 Pursuant to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 1989 Edition without Addenda, Entergy Nuclear Operations, Inc. (ENO) hereby submits the 2002 Refueling Outage Inservice Inspection (ISI)

Program Summary Report. In accordance with IWA-6230, this report is provided within 90 days of completion of the inspections. Pursuant to Indian Point Unit No. 2 Technical Specification Section 4.2.2, inspections of the primary and secondary side components were performed by ENO during the 2002 refueling outage. A report of previous inspections (2000 refueling outage) was provided by Reference 1.

The following report contents are provided as attachments to this letter:

"* Non-Destructive Examination Report and Form NIS-I Owner's Report for Inservice Inspections

"* Form NIS-2 Owner's Report for Repair and Replacement

"* Inservice Inspection Program Summary - Snubbers

"* Inservice Inspection Program Summary - Pressure Tests Detailed information pertaining to these reports is available at IP-2 for review.

No new regulatory commitments are being made by ENO in this correspondence.

NL-03-026 Page 2 of 2 Should you or your staff have any concerns regarding this matter, please contact Mr. John McCann at 914-734-5074.

ours TSincere]

Fred Dacimo Vice President Indian Point Energy Center Attachments:

1. Non-Destructive Examination Report and Form NIS-1 Owner's Report for Inservice Inspections
2. Form NIS-2 Owner's Report for Repair and Replacement
3. Inservice Inspection Program Summary - Snubbers
4. Inservice Inspection Program Summary - Pressure Tests C: Mr. Hubert J. Miller Regional Administrator-Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555 Senior Resident Inspector U.S. Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511

ATTACHMENT 1 TO NL-03-026 Non-Destructive Examination Report and Form NIS-1 Owner's Report for Inservice Inspections Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL-03-026 Attachment 1 Page 1 of 4 Indian Point Unit No. 2 Third Outage, Second Period, Third Interval Non-Destructive Examination Report Introduction Inservice inspections were performed between October 2002 and November 2002 at Indian Point Unit No. 2 during the 2002 refueling outage.

Examinations were performed in accordance with the requirements of:

1. The Entergy Nuclear Operations, Inc. (ENO) Third Ten Year Inservice Inspection Program
2. Technical Specifications
3. ASME Boiler & Pressure Vessel Code,Section XI, 1989 Edition without Addenda The following items were examined:
1. Reactor Coolant Pump 23 main flange nuts
2. Class 2 piping and integral attachments The examinations performed are summarized on the attached Form NIS-1.

Prior to these examinations, certification documents relative to personnel, equipment, and materials were reviewed and determined to be satisfactory.

Personnel from the Hartford Steam Boiler of Connecticut, and ENO conducted surveillances of and witnessed examinations and related activities.

There were no recordable indications noted during the inspection program.

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner Entergy Nuclear Operations, Inc., 295 Broadway, Suite 1, Buchanan, New York 10511-0249 (Name and Address) 10511-0249
2. Plant Indian Point Energy Center, Buchanan, New York (Name and Address) 2 4. Owner Certificate of Authorization (if required) NA
3. Plant Unit 07/01/1974 6. National Board Number for Unit NA
5. Commercial Service Date
7. Components Inspected Component or Manufacturer or Manufacturer or State or Province National Board Appurtenance I Installer Installer Serial No. No. No.

See Attached Inservice Inspection Report 4- + t

.1- + -I- I 4- 4 + I

.1- 4 + I F -t I I F I f F t t F F 1-

FORM NIS-1 (Back) 10/21/2002 to 10/29/2002

8. Examination Dates
9. Inspection Period Identification November 1, 1997 to December 5, 2002
10. Inspection Interval Identification July 1, 1994 to April 5, 2006 1989 Addenda None
11. Applicable Edition of Section XI January 19, 1994 Rev. 0
12. Date/Revision of 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 NIS-1 Examinations. attached.

14. Abstract of Results of Examinations and Tests.

All Items accented.

15. Abstract of Corrective Measures.

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

Certificate of Authorization No. (if applicable) None Expiration Date N/A .

Date FA `'"' I ,2003 Signed , -- 7 by Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by HSBCT of Hartford, CT have inspected the components described in this Owner's Report during the period January 3, 2001 to November 27, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in the 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 aig from or connected with this inspection.

Commissions WV'* /&ýO// "

Insneetor's Sianature National Board, State, Province, and Endorsements Date //'-01 -, 2003

NL-03-026 Attachment 1 Page 4 of 4 Inservice Inspection Report lti~m Catevnrv Svstem Comn ID Descrintion ISO No. Method Results Class 1 B6 200 B-G-1 RCS RCPN 23-17 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-18 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-19 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-20 F NUTS 206923 VT NRI B6.200 B-G-1 RCS RCPN 23-21 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-22 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-23 F NUTS 206923 VT NRI B6 200 B-G-1 RCS RCPN 23-24 F NUTS 206923 VT NRI Class 2 C3.20 C-C MS 3S 1W MSR 26 206660 MT NRI C5 11N C-F-1 SIS 15 16 CIRC WELD 206677 PT, UT NRI C5 11N C-F-i SIS 15 17 CIRO WELD 206677 PT, UT NRI C5 11N C-F-i SIS 15 26 CIRC WELD 206677 PT, UT NRI C5 11N C-F-1 SIS 15 27 CIRC WELD 206677 PT, UT NRI C5.1IN C-F-1 SIS 15 28 CIRC WELD 206677 PT UT NRI C5 11N C-F-1 SIS 15 29 CIRC WELD 206677 PT, UT NRI C5 11N C-F-1 SIS 15 30 CIRO WELD 206677 PT, UT NRI C5 11N C-F-1 SIS 15 31 CIRC WELD 206677 PT, UT NRI C5 11N C-F-1 SIS 51 16 CIRC WELD 206694 PT, UT NRI C5.11N C-F-1 SIS 51 18 CIRC WELD 206694 PT, UT NRI C5 11N C-F-1 SIS 51 29 CIRC WELD 206694 PT, UT NRI C5 11N C-F-i SIS 51 30 CIRC WELD 206694 PT, UT NRI C530 C-F-1 HIS 56 37 SOCKET WELD 206702 PT NRI C5 11N C-F-1 SIS 57 5 CIRC WELD 206703 PT NRI

ATTACHMENT 2 TO NL-03-026 Form NIS-2 Owner's Report for Repair and Replacement Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL-03-026 Attachment 2 Page I of 4 Indian Point Unit No. 2 Third Outage, Second Period, Third Interval Repair/Replacement Report Introduction Repair/replacement work was performed at Indian Point Unit No. 2 during the time period from December 2000 through November 2002.

Work was performed in accordance with the requirements of:

1. Maintenance Administrative Directive (MAD) 36
2. ASME Boiler & Pressure Vessel Code,Section XI, 1989 Edition without Addenda The following items were replaced on 18 different components:
1. Valves, valve bolting, pipe and elbow, valve bonnet, weld neck flanges, pipe tee and canopy seal clamp assemblies The following item was repaired on 1 component:
1. 2" butt weld The work performed is summarized on the attached Form NIS-2.

Personnel from the Hartford Steam Boiler of Connecticut and Entergy Nuclear Operations were given proper notifications so they could choose whether or not to conduct surveillances of and witness examinations.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Entergy Nuclear Operations, Inc. Date February 13, 2003

1. Owner Name 295 Broadway, Suite 1, Buchanan, New York 10511-0249 Sheet N/A of N/A Address 2
2. Plant Indian Point Nuclear Generating Station Unit Name 295 Broadway, Suite 1, Buchanan, New York 10511-0249 None Address Repair Organization P.O. No., Job No., etc.

Owner Type Code Symbol Stamp None

3. Work Performed by Authorization No. None Name 295 Broadway, Suite 1, Buchanan, New York 10511-0249 Expiration Date N/A Address
4. Identification of Systems AFW. CCW. CVCS. FW. MS. RCS. SIS. SW
5. (a) Applicable Construction Code: As identified in the plant Operating Equipment (OE) history (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989, No Addenda
6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer National Other Year Repaired, ASME Code Component Manufacturer Serial No. Board Identification Built Replaced, or Stamped No. I Replacement (Yes or No)

See Attached 2001-2002 Repair and Replacement List

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

-i FORM NIS-2 (Back) of

9. Remarks No ASME Section III or Section VIII components were repaired or replaced this outage. A listing Applicable Manufacturer's Data Reports to be attached Additional non ASME III or VIII components which are included in the Section XI Code Repair & Replacement Program is contained in the attached NIS-2 table.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and these repairs/replacements conform to the rules of the ASME Code,Section XI.

None Type Code Symbol Stamp

o. None Expiration Date N/A Certificate o0 Athorization Signed .:_..*l  ; iy* ..- Date / J, 2003

- V{wn~r or 4bwner's Desigee, 'fItle I /

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by HSBCT of Hartford. CT have inspected the components described in this Owner's Report during the period January 3. 2001 to November 272002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in the 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 X4's/CX9A // '%/A National Board, State, Province, and Endorsements

2001-2002 Repair and Replacement List WORK ORDER # 'CODE TAG # CORRECTIVE ACTION ' WORK DESCRIPTION " COMP DATE SYS IP2-02-25690 A 21 RV REPLACEMENT CANOPY SEAL CLAMP ASSY. 18-Nov-02 RCS IP2-02-41202 A 897D REPLACEMENT 2 STUDS AND NUTS 19-Nov-02 RCS IP2-00-15613 B 326 REPLACEMENT VALVE BONNET 10-Nov-02 CVCS IP2-01-23583 B 218 REPLACEMENT VALVE 08-Nov-02 CVCS IP2-01-24563 B 236 REPLACEMENT VALVE BONNET 15-Oct-02 CVCS IP2-98-04855 B 310 REPLACEMENT 2 TEE 31-Aug-01 CVCS IP2-00-16085 B BFD-641 REPLACEMENT STEM AND BONNET 05-Nov-02 FW IP2-01-23396 B MS-2A REPLACEMENT 1 STUD AND NUT 02-Nov-02 MS IP2-97-93691 B MS-1-22 REPLACEMENT STUDS AND NUTS 19-Nov-02 MS IP2-00-18799 B 1863 REPLACEMENT VALVE 06-Nov-02 SIS IP2-02-61859 C PSUPSR-480 REPLACEMENT RESTRAINT REMOVED 20-Nov-02 AFW IP2-02-61859 C PSUPSR-481 REPLACEMENT RESTRAINT REMOVED 20-Nov-02 AFW IP2-02-02441 C 774D REPLACEMENT VALVE AND PIPE 16-Nov-02 CCW IP2-00-16620 C 22MBDE REPLACEMENT STUDS AND NUTS 04-Jun-01 CVCS IP2-01-211239 C 1299 REPLACEMENT BOLTS AND NUTS 23-Apr-01 CVCS IP2-01-23584 C MS-52 REPLACEMENT VALVE 12-Nov-02 MS IP2-01-24386 C MST-65 REPLACEMENT NUTS 31-Oct-01 MS iP2-00-17302 C 21SWPS REPLACEMENT STUDS AND NUTS 03-Aug-01 SW IP2-01-22771 C SWN-62-1 REPLACEMENT STUDS 03-Nov-02 SW IP2-01-23619 C SWN-42-1 REPLACEMENT VALVE 03-Nov-01 SW IP2-01-23620 C SWN-42-2 REPLACEMENT VALVE 17-Nov-02 SW IP2-01-23621 C SWN-42-3 REPLACEMENT VALVE 12-Nov-02 SW IP2-01-23622 C SWN-42-4 REPLACEMENT VALVE 12-Nov-02 SW IP2-01-24337 C 22CRFMC REPLACEMENT PIPE AND ELBOW 31-Oct-01 SW IP2-02-00629 C SWN-66 REPLACEMENT NUTS AND BOLTS 24-Jul-02 SW IP2-99-06789 C SWN-4 REPLACEMENT NUTS AND BOLTS 04-Nov-02 SW IP2-02-59907 C* LINE1lC REPLACEMENT 2" WELD NECK FLANGE 08-Nov-02 SW IP2-02-60010 C* LINE11A REPLACEMENT 2" WELD NECK FLANGE 08-Nov-02 SW IP2-02-60011 C* LINE11B REPLACEMENT 2" WELD NECK FLANGE 13-Nov-02 SW IP2-02-54555 C SWN-41-5A REPAIR 2" FILLET WELD 17-Nov-02 SW

ATTFACHMENT 3 TO NL-03-026 Inservice Inspection Program Summary - Snubbers Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL-03-026 Attachment 3 Page 1 of 8 Indian Point Unit No. 2 Third Outage, Second Period, Third Interval Snubber Inspection Report Inservice inspections were performed between October 2002 and November 2002 at Indian Point Unit No. 2 during the 2002 refueling outage.

Examinations were performed to satisfy the requirements of:

1. Indian Point No. 2 Surveillance Test Procedures PI-V1A and PI-VIB
2. Indian Point No. 2 Shock Suppressor Initial Functional Test PT-R34
3. Indian Point No. 2 Steam Generator Shock Suppressor Functional Test PT-R34A
4. Technical Specifications Section 4.12.A and Section 3.12
5. ASME Boiler & Pressure Vessel Code,Section XI, 1989 Edition without Addenda.

The following items were examined:

1. 5 pipe support hydraulic shock arrestors from Quality Group "A" (small bore)
2. 6 component support hydraulic shock arrestors from Quality Group "A" (large bore S/G)
3. 10 pipe support hydraulic shock arrestors from Quality Group "B" (small bore)
4. 19 non-Section XI pipe support hydraulic shock arrestors (small bore)

Certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory prior to the start of examinations.

Visual examinations of the "as-found" and "as-left' conditions of the hydraulic shock arrestors were conducted by certified personnel from the Wyle Laboratories, under contract to ENO and certified personnel from ENO's "in house" Quality Control Department.

The work performed is summarized on the attached Form NIS-2.

Personnel from the Hartford Steam Boiler of Connecticut and ENO were given proper notifications to allow them the option of conducting surveillances or witnessing examinations.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Entergy Nuclear Operations, Inc. Date February 18,2003

1. Owner Name 295 Broadway, Suite 1, Buchanan, New York 10511-0249 Sheet N/A of N/A Address 2
2. Plant Indian Point Nuclear Generating Station Unit Name None 295 Broadway, Suite 1, Buchanan, New York 10511-0249 Address Repair Organization P.O. No., Job No., etc.

None Owner Stamp

3. Work Performed by Type Code Symbol Authorization No. None Name 295 Broadway, Suite 1, Buchanan, New York 10511-0249 Expiration Date N/A Address oybt*mn.

ACS. CVCS. MS. RCS. RHR. SGBD. SIS

4. Identification 01ul OYSLems
5. (a) Applicable Construction Code: As identified in the plant Operating Equipment (OE) history (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989, No Addenda
6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer National Other Year Repaired, ASME Code Component Manufacturer Serial No. Board Identification Built Replaced, or Stamped No. Replacement (Yes or No)

See Attached 2002 Snubber Repair and Replacement List

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

FORM NIS-2 (Back)

9. Remarks This NIS-2 covers the repair and replacement of snubbers during the 2R15 refueling outage.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and these repairs/replacements conform to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp None Certificate of-Authdrization No. Expiration Date N/A Signedx04 3 /7" -

,6 wner or Owner's Designee, Title Date 1'2 6 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New York and employed by HSBCT of Hartford, CT have inspected the components described in this Owner's Report during the period January 3,2001 to November 27,2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in the 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 ,,./A/l"e hQ /// W Inspector's Signature National Board, State, Province, and Endorsements Date Z / ____, 2003

NL-03-026 Attachment 3 Page 4 of 8 2002 REFUELING OUTAGE INSERVICE INSPECTION PROGRAM

SUMMARY

- SNUBBERS AREA AND EXTENT OF EXAMINATIONS IWB-2500 EXAMINATION REFERENCE PROCEDURE QUALITY GROUP A PIPE SUPPORTS BFI.10 Line 43 SR-1024A Visual-Note 1 Line 44 SR-1072 Line 62 62-SR-2 Line 79 SR-902 Line 351 PWR-127 QUALITY GROUP A COMPONENT SUPPORTS BF1.40 21 Steam Generator Visual-Note 1 SG-21-1, SG-21-3 23 Steam Generator SG-23-1, SG-23-3 24 Steam Generator SG-24-1, SG-24-3 QUALITY GROUP B PIPE SUPPORTS BF1.20 Line 2 SR-M3A, SR-Ml, SR-M2 Visual-Note 1 Line 4 SR-M10A, SR-M9 Line 9 SR-55 Line 60 SR-703-1, SR-746B Line 356 SR-720 Line V-3 SR-M29 Note 1: Visual examination of snubbers was performed per plant Technical Specification 4.12.A. The visual inspection was performed in accordance with surveillance test procedure PI-VIA and PI-VIB.

NL-03-026 Attachment 3 Page 5 of 8 FOR INFORMATION ONLY The following NON-SECTION XI snubbers were visually inspected in accordance with surveillance test procedure PI-VIA and PI-V1B.

Line 38 38-SR-21 Line 70 70-SR-3, RCS-5 Line MS-3 MS-SR-129 Line V-3 SR-M33 Line V-4 SR-M52 Line V-5 SR-M34, SR-M37, SR-M39 Line 4 SR-M55 Line 8 SR-B5 Line 46 46-SR-30 Line 353 SR-737A Line MS-3 SR-499 Line 14 14-SR-1 Line 14A SR-1001, SR-1076 Line MS-3 SR-501 Line 361 361-SR-10 EXAMINATION INDICATIONS & DISPOSITION ISI INDICATIONS- QUALITY GROUP A PIPE SUPPORT 62-SR-2 Pipe clamp was found out of alignment with the snubber. The misalignment between the pipe clamp and the snubber was more than the design allowable of + or 5 degrees. The clamp has been realigned.

ISI INDICATIONS- QUALITY GROUP A COMPONENT SUPPORTS 21 Steam Generator SG-21-1 There was a trace of fluid on the isolation screw and reservoir. Also one ear of the isolation screw was broken. This snubber was replaced due to its service life. The snubber was removed and a replacement snubber was installed. An as-left was performed to ensure all the requirements of the procedure are satisfied.

SG-21-3 Two top anchor bolts to the steam generator snubber base plate were found loose. The bolts are still fully engaged with no gap between the nut and base plate (nut is in full contact with the base plate). In addition there was some fluid on the reservoir. The snubber was removed and a replacement snubber was installed. The snubber was

functionally tested. An as-left was performed to ensure all the requirements of the procedure are satisfied.

23 Steam Generator SG-23-1 There was a trace of fluid on the isolation screw and reservoir. Also one ear of the isolation screw was broken. This snubber was replaced due to its service life. The snubber was removed and a replacement snubber was installed. An as-left was performed to ensure all the requirements of the procedure are satisfied.

SG-23-3 Three of four anchor bolts to the base plate, bolts were found loose.

Applied Loctite to the bolts and nuts to prevent loosening of the joints. This snubber was replaced due to its service life. The snubber was removed and a replacement snubber was installed. The snubber was functionally tested. An as-left was performed to ensure all the requirements of the procedure are satisfied.

24 Steam Generator SG-24-1 This snubber was replaced due to its service life. The snubber was removed and a replacement snubber was installed. An as-left was performed to ensure all the requirements of the procedure are satisfied.

SG-24-3 The lower left anchor bolt to the base plate was found loose. Applied Loctite to the bolts and nuts to prevent loosening of the joints. This snubber was replaced due to its service life. The snubber was removed and a replacement snubber was installed. An as-left was performed to ensure all the requirements of the procedure are satisfied.

ISI INDICATIONS- QUALITY GROUP B PIPE SUPPORTS SR-M2 There was debris on the piston rod. The snubber has been replaced with a spare so there is no adverse condition in the field. There was no indication of leakage; this snubber was replaced due to its service.

SR-M10A The piston rod appears scored. The snubber has been replaced with a spare. Snubber SR-M10A has been functionally tested in accordance with the testing program. The results of PT-R34 were successful for this snubber; therefore the snubber was operable for past service life. The score or indication had no impact on the operability of the snubber.

SR-55 A lack of thread engagement on one end of the turnbuckle of restraint. The snubber was replaced but the condition still exists. Approximately one thread is not engaged. This restraint will perform its design function in the as-found condition.

SR-M29 The spherical bearing in paddle to pipe clamp is bound up. The snubber was subsequently removed for service life considerations and a replacement snubber was installed. The condition still exists in the as-left inspection.

SR-M3A Could not see bottom clam bolt due to insulation but clamp was tight. Condition was evaluated by Engineering and found acceptable.

SR-M9 Insufficient thread engagement. Condition evaluated by Engineering and found to meet design requirements in the as-installed configuration.

Reference:

Test Procedure No. TP-SQ-1 1035, Revision 5

NL-03-026 2002 Snubber Repair/Replacement List Attachment 3 1

Removed Replacement Replacement Snubber Id. Sys. Line # IWB-2500 Serial # Mfg. Serial # Mfg.

SR-1024A CVCS 43 F1.10 2500-3-940 Bergen Patt 2500-3-855 Bergen Patt.

SR-1 072 CVCS 44 F1.10 G15198-1 Bergen Patt 2500-3-860 Bergen Patt.

SR-902 CVCS 79 F1.10 2500-3-1209 Bergen Patt 2500-3-966 Bergen Patt.

62-SR-2 RCS 62 F1.10 2500-3-830 Bergen Patt. 2500-3-1029 Bergen Patt PWR-127 SIS 351 F1.10 2500-10-1279 Bergen Patt 2500-10-930 Bergen Patt SG-21 -1 MS 21 SG F1.40 2500-250-6 Bergen Patt. 2500-250-16 Bergen Patt SG-21-3 MS 21 SG F1.40 2500-250-21 Bergen Patt. 2500-250-10 Bergen Patt SG-23-1 MS 23SG F1.40 2500-250-5 Bergen Patt. 2500-250-9 Bergen Patt SG-23-3 MS 23SG F1.40 2500-250-15 Bergen Patt 2500-250-13 Bergen Patt SG-24-1 MS 24SG F1.40 2500-250-14 Bergen Patt 2500-250-7 Bergen Palt.

SG-24-3 MS 24SG F1.40 2500-250-24 Bergen Patt 2500-250-3 Bergen Patt.

SR-M29 MS V-3 F1.20 2500-3-1252 Bergen Patt 2500-10-1210 Bergen Patt SR-Mi MS 2 F1.20 2500-10-1277 Bergen Patt. 2500-10-219 Bergen Patt.

SR-M10A MS 4 F1.20 G43864-01-1 Bergen Patt. 2500-30-308 Bergen Patt.

SR-M2 MS 2 F1.20 2500-10-1276 Bergen Patt. 2500-10-218 Bergen Patt SR-M3A MS 2 F1.20 2500-50-253 Bergen Palt 2500-50-92 Bergen Patt.

SR-M9 MS 4 F1.20 2500-10-1283 Bergen Patt. 2500-10-928 Bergen Patt.

SR-55 RHR 9 F1.20 2500-10-1285 Bergen Patt 2500-10-921 Bergen Palt.

SR-703-1 SIS 60 F1.20 G43861-05-6 Bergen Patt 2500-3-866 Bergen Palt.

SR-720 SIS 356 F1.20 G20966-1-40 Bergen Patt. 2500-3-868 Bergen Patt.

SR-746B SIS 60 F1.20 2500-3-878 Bergen Patt 2500-3-871 Bergen Patt.

46-SR-30 SGBD 46 N/A 2500-3-1373 Bergen Patt. 2500-3-309 Bergen Pall SR-499 MS MS-3 N/A 2500-3-1245 Bergen Patt 2500-3-889 Bergen Palt.

SR-737A MS 353 N/A 2500-3-1229 Bergen Patt 2500-3-827 Bergen Patt 14-SR-1 ACS 14 N/A 2500-3-991 Bergen Patt 2500-3-843 Bergen Pall.

SR-1 001 ACS 14A N/A G39776-5A Bergen Palt 2500-3-921 Bergen Palt.

SR-1076 ACS 14A N/A G20966-1-23 Bergen Patt 2500-3-922 Bergen Patt SR-501 MS MS-3 N/A 2500-3-1248 Bergen Patt. 2500-3-310 Bergen Patt.

SR-B5 FW 8 N/A 2500-20-701 Bergen Pall. 2500-20-485 Bergen Patt 38-SR-21 CVCS 38 N/A G20966-1-189 Bergen Patt. 2500-3-926 Bergen Patt MS-SR-129 MS MS-3 N/A G43861-03-27 Bergen Patt 2500-3-1010 Bergen Patt SR-M33 MS V-3 N/A 2500-3-1237 Bergen Patt 2500-3-892 Bergen Patt SR-M34 MS V-5 N/A 2500-3-1242 Bergen Patt 2500-3-909 Bergen Patt.

SR-M37 MS V-5 N/A 2500-3-1234 Bergen Patt. 2500-3-906 Bergen Patt.

SR-M39 MS V-5 N/A 2500-3-1243 Bergen Patt 2500-3-920 Bergen Palt SR-M52 MS V-4 N/A 2500-3-1214 Bergen Patt. 2500-3-904 Bergen Patt SR-M55 MS 4 N/A 2500-10-1273 Bergen Patt. 2500-10-914 Bergen Patt 70-SR-3 RCS 70 N/A 39935R-1 BA Bergen Patt. 2500-3-877 Bergen Patt.

RCS-5 RCS 70 N/A 2500-10-1278 Bergen Palt 2500-10-918 Bergen Palt 361-SR-10 RHR 361 N/A 2500-3-1226 Bergen Patt 2500-3-842 Bergen Patt.

ATTACHMENT 4 TO NL-03-026 Inservice Inspection Program Summary - Pressure Tests Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL-03-026 Attachment 4 Page 1 of 4 Summary of Inservice Inspection Pressure Tests Performed on Quality Group A and B (ASME Section XI Classes 1 and 2) Pressure Retaining Components Inservice system pressure tests of Quality Groups A and B systems and components were conducted at the Indian Point Unit No. 2 Nuclear Power Plant in order to meet ASME Section XI requirements for the interval. This testing was completed to conclude the pressure testing requirements for the second period of the ten-year interval and coincident with the completion of refueling outage No. 15 in November 2002. The Quality Group A and B systems and components were inspected using procedures updated to the current program requirements.

This program utilized visual examination methods in accordance with the requirements of:

1. ASME B&PV Code,Section XI, 1989 Edition
2. Technical Specifications, and
3. IP-2 Ten Year Inservice Inspection Program including relief requests The areas tested and indications reported are summarized in Tables 1 and 2 of this attachment.

The Quality Group A examinations revealed seven indications at fittings and flanges (mechanical pressure boundary) and three indications at valve packing (mechanical non-pressure boundary).

Four of the indications were immediately repaired. Six indications were deferred to the next available system depressurization. Of these six, two were leaks in valve internal stem pressure bellows where the leakage was stopped by valve back-seating in one case and a temporary alteration of a leak-off line in the other case. The remaining four deferrals were for minor packing or instrument line fitting weepage.

The Quality Group B examinations revealed thirteen indications. Seven of these were repaired and six were deferred to future repair availability. Of these six, five were valve packing indications and one was a threaded connection at a pump casing vent line.

NL-03-026 Attachment 4 Page 2 of 4 TABLE I AREAS TESTED TEST NO. TITLE QUALITY GROUP DRAWINGS PT-R75 RCS INTEGRITY INSPECTION A 9321-F-2738, 9321-F-2745, 208168 PI-3Y17 CVCS BORIC ACID MAKEUP ISI B 9321-F-2736 PI-3Y17A EMERGENCY BORATION LINE ISI B 9321-F-2736 PI-3Y18 PW TO CVCS MAKEUP ISI B 9321-F-2736 PI-3Y25 CONTAINMENT SPRAY PUMPS ISI B 9321-F-2735 PI-3Y26 CONTAINMENT SPRAY DISCHARGE ISI B 9321-F-2735 235296 PI-3Y28 RECIRCULATION PUMPS ISI B 235296 PI-3Y38 MAIN STEAM TRAPS ISI B 9321-F-2041 PI-3Y40 SAFETY INJECTION PUMPS ISI B 9321-F-2735 PI-3Y41 SAFETY INJECTION DISCHARGE ISI B 9321-F-2735 235296 PI-3Y41A 21 ACCUMULATOR TANK ISI B 235296 PI-3Y41B 22 ACCUMULATOR TANK ISI B 235296 PI-3Y41C 23 ACCUMULATOR TANK ISI B 235296 PI-3Y41D 24 ACCUMULATOR TANK ISI B 235296 PI-3Y41E SAFETY INJECTION TOPPING PUMP ISI B 9321-F-2735 PI-3Y45 RHR PUMPS SUCTION VALVE 882 ISI B 9321-F-2735 PI-3Y46 REFUELING WATER STORAGE TANK ISI B 9321-F-2735 PI-3Y48 SEAL RETURN OUTSIDE CONTAINMENT ISI B 9321-F-2736 PI-3Y48A SEAL RETURN INSIDE CONTAINMENT ISI B 208168 PI-3Y49 LETDOWN OUTSIDE CONTAINMENT ISI B 9321-F-2736

NL-03-026 Attachment 4 Page 3 of 4 PI-3Y50 VCT BYPASS LINE ISI B 9321-F-2736 PI-3Y51 LETDOWN INSIDE CONTAINMENT ISI B 208168 P13Y57 CHARGING OUTSIDE CONTAINMENT ISI B 9321-F-2736 P13Y57A CHARGING INTSIDE CONTAINMENT ISI B 208168 PI-3Y58 PURIFICATION BOOSTER PUMP ISI B 208168 PI-3Y13 RECICULATION PUMP SAMPLE TEST B 235296 PT-R12 RHR SYSTEM INSERVICE HYDRO B 251783 235296 9321-F-2745 9321-F-2735 9321-F-2720

NL-03-026 Attachment 4 Page 4 of 4 TABLE 2

SUMMARY

OF REPORTED INDICATIONS QUALITY GROUP A AND B PRESSURE RETAINING COMPONENTS QUALITY GROUP A PRESSURE RETAINING COMPONENTS LEAKAGE TYPE # FOUND # REPAIRED # DEFERRED THROUGH WALL 0 0 0 MECHANICAL PRESSURE BOUNDARY 7 3 4 MECHANICAL NON-PRESSURE BOUNDARY 3 1 2 TOTAL ITEMS BY STATUS 10 4 6*

Includes those locations where corrective measures were implemented; however, a permanent repair was deferred.

QUALITY GROUP B PRESSURE RETAINING COMPONENTS LEAKAGE TYPE # FOUND # REPAIRED # DEFERRED THROUGH WALL 0 0 0 MECHANICAL PRESSURE BOUNDARY 1 0 1 MECHANICAL NON-PRESSURE BOUNDARY 12 7 5 TOTAL ITEMS BY STATUS 13 7 6

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