NL-07-069, Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval

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Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval
ML071710461
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 06/13/2007
From: Jones T
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-069 IP-RPT-07-00058, Rev 0
Download: ML071710461 (17)
v • d • e


Text

Enteraqv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB gP.O. Box 249 Buchanan, NY 10511-0249 T.R. Jones Licensing Manager Tel 914 734 6670 June 13, 2007 Re: Indian Point Unit 3 Docket No. 50-286 NL-07-069 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Subject:

Inservice Inspection (ISI) Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval

Dear Sir:

This letter submits the Indian Point Nuclear Generating Unit No. 3 (IP3) Owners Activity Report, IP-RPT-07-00058, Rev. 0 (Enclosure 1) which contains ISI results and repair/replacement activities performed during the First Outage of the 3rd Period of the Third 10-Year ISI Interval.

All work performed met the requirements of 1989 Edition, No Addenda, of the ASME Section XI Code with approved relief requests.

Entergy will use NRC-approved ASME Section XI Code Case N-532-1 for submitting inspection results completed for IP3. This Code Case was approved for use through Regulatory Guide 1.147, Revision 13. Code Case N-532-1 provides alternatives for the documentation requirements for repair and replacement activities, and allows the use of Form NIS-2A in lieu of Form NIS-2. Enclosure 1 was prepared in accordance with the requirements of Code Case N-532-1 as approved.

There are no new commitments being made in this submittal.

If you have any questions or require additional information, please contact Mr. T.R. Jones, Manager, Licensing at (914) 734-6670.

Sincerely T.R. ones Licensing Manager Indian Point Energy Center

NL-07-069 Docket 50-286 Page 2 of 2

Enclosure:

1. 1P3 Owners Activity Report, IP-RPT-07-00058, Rev. 0
  • Attachment 1 - Abstract of Examinations and Tests
  • Attachment 2 - Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service
  • Attachment 3 - Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service cc: Mr. John Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector Office, IPEC Mr. Paul Eddy, New York State Dept. of Public Service

ENCLOSURE 1 TO NL-07-069 IP3 ISI OWNERS ACTIVITY REPORT (OAR)

THIRD PERIOD, THIRD INTERVAL (Report No. IP-RPT-07-00058, Rev. 0) - Abstract of Examinations and Tests - Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service - Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

TID r)nqr 0'7 [)0nCQ En~gJineing epon XT LI. oXjUIF-IFI1/-U. J..)O Rev. 0 Page 1 of 14

Entergy Indian Point 3 ENTERGY NUCLEAR NORTHEAST Engineering Report

Title:

IP3 ISI Owners Activity Report (OAR)

Third Period, Third Interval Engineering Report Type:

New [X] Revision [] Cancelled [] Superceded []

Applicable Site(s)

IPI[] IP2[] IP3 [X I JAF [ ] PNPS [ ] VY [ ]

Quality-Related: [X] Yes [ No

,anskv A , I.A*a Ro hert Prepared by:

Al -

-L F Date: *7/0 7

....... Responsible En4 me

..... t..

  • mith/ /A ate: 3._- /9* e7 Reviewed by: Atiiro S .. . D

... .. S .....i.th- /

m Programs-Engineefif Review Date:

  • Reviewed by: Allan Schiaffino /I Af1 Authorized NuclerIn-Seyice Inspector (ANII)

Approved by: Glen Smith Glen Smith

/

___ - F - Date:*tM/ 7 Superviso6'/rograms Engineering Multiple Site Review Site Design Verifier/Reviewer Supervisor Date 4 -I- +

4 4 +

FORM OAR-1 OWNERS ACTIVITY REPORT Report Number IP-RPT-07-00058 Rev.0 Owner Entergy Nuclear Operations, Inc.. 295 Broadway. Suite 1. Buchanan. New York 10511-0249 (Name and Address of Owner)

Plant Indian Point Ener2y Center. Buchanan, New York 10511-0249 (Name and Address of Plant)

Plant Unit 3 Commercial Service Date 08/30/1976 Refueling Outage Number 14 Current Inspection Interval 3 rd (1st, 2nd, 3rd, 4th, Other)

Current Inspection Period 3rd (1st, 2nd, 3rd)

Edition and Addenda of Section Xl applicable to the Inspection Plan 1989 Edition, No/ .ddenda Date and Revision of Inspection Plan: ISI Program Plan, Rev. 3 No. IP3-RPT-UNSPEC-03247 Edition and Addenda of ASME Section Xl applicable to Repairs and Replacements, if different than the Inspection Plan N/A CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owners Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations and corrective measures represented by this report conform to the requirements of Section Xl.

Certificate of Authorization No. N/A Expiration Date N/A (If applicable)

Signed _ __ _ __I_ _ _'

_ Date 05/.

0/ `7

)DwnerorOw-'Ow*e*-1 ldesignee, Title 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_ HSB-CT of Hartford, Connecticut have inspected the components described in this Owners Report during the period April 2005 to March 2007 , and state that to the best of my knowledge and belief, the Owner has performed all the activities described in the Repair/Replacement Plan in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the activities described in the Repair/Replacement Plan. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

(V ?-e-ý ý Commissions oV&*/*// .27e.00-,

Inspector's Signature National Board, State, Province, and Endorsements Date Page 2 of 14

Attachment 1 Page 3 of 14 Table 1 ABSTRACT OF EXAMINATIONS AND TESTS IP3 ISI Owners Activity Report (OAR)

Third Period, Third Interval

3R14 Refueling Outage IP3 Owner Activity Report Third Period All 6 Meriodonal Welds examined to the extent possible. Reactor Vessel head to flange weld examination B-A 28 0 0% 25% limited to the volume with a previously identified indication. Reactor Vessel Closure Head (Dollar Plate) weld inaccessible. RR 3-19 defers the RV Shell to Flange Weld to the 3rd period.

B-B 5 0 0% 60%

B-D 30 4 13% 47% Code Case N-521 allows deferral of 83.90 and B3.100. RR 3-16 allows deferral of B3.120 B-E 113 0 0% 00 Deferral permissible per Table IWB-2500-1.

Components within this category are part of an Augmented Risk-Informed Inspection Program per RR 3-28.

Extent and Frequency is in accordance with this Program. See new exam category R-A below.

B-F 0 0 0% 0%

B-G-1 265 0 0% 62%

Total in Total Examinations Required column is based on 1 Pressurizer manway, 2 manways for 1 S/G, 2 B-G-2 15 1 7% 80% flanges for piping, 1 RCP flange, 4 valves and 5 CRD housings (examined only when disassembled). All 5 CRD housings disassembled and inspected during CETNA mod installation. Credit taken for all 5 CRD housings because they will not be disassembled in the future as a result of CETNA mod installation.

B-H 0 0 01% 0%. Not Applicable to IP3 Components within this category are part of an Augmented Risk-Informed Inspection Program per RR 3-28.

B-J 0 0 0% 0% Extent and Frequency is in accordance with this Program. See new exam category R-A below.

Page 4 of 14 5/22/2007 OAR-1

3R14 Refueling Outage IP3 Owner Activity Report Third Period Total in Total Examinations Required column is based on 1 Pressurizer integrally welded attachment, 1 pipe 3100% integrally welded support, and 1pump integrally welded support. Examinations conducted in accordance with Code Case N-509" Alternate Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments,Section XI Division 1".

B-L-1 13 3 100 1% J' Defferal Permissible. Exams are limited to at least one pump in each group of pumps performing similar

_functions in the system per Code Case N-481.

Exam required only when a pump is disassembled for maintenance, repair, or volumetric exam. Exams are B-L-2 1 0 0% 100% limited to at least one pump in each group of pumps performing similar functions in the system per Code Case N-481. Pump disassembled and inspected in 1st period.

B-M-1 0 0 0% 0% Not applicable to 1P3(Valves do not have valve body welds)

B-M-2 5 0 0% 40% Exam required only when a valve is disassembled for maintenance, repair, or volumetric exam.

B-N-1 3 0 0% 66% Inspections performed each period B-N-2 1 0 0% 0% Deferred to end of interval as allowed by Table IWB-2500-1 B-N-3 1 0 0% 0% Deferred to end of interval as allowed by Table IWB-2500-1 B-O 4 4 100% 100% Inspected in 3rd Period as allowed by Table IWB-2500-1 B-P 36 6 17% 67% Code Case N-498-1 applied where applicable.

_______ 6:* . 7 . RiSKINFORMED:.;

Risk Informed selection contains 64 items from Categories B-F & B-J. Risk Informed inspections per relief R-A 64 6 9% 73% request 3-28.

Page 5 of 14 5/22/2007 OAR-11

3R14 Refueling Outage IP3 Owner Activity Report Third Period C-A 9 3 3378%

Aug (C-A) 4 0 0  % 0% Augmented inspection of Non-Regenerative Heat Exchanger C-B 11 4 36  % 82%

C-C 16 5 31 1% 949%.

C-F-1 60 29 48% 100  %

Aug (C-F-i) 6 3 50% 100% Augmented inspection of Containment Spray piping.

C-F-2 28 9 32% 93% Per Table IWC-2500-1, C-F-2, Note 2, a minimum of 28 welds are required to be inspected.

C-H 16 0 0% 50% Pressure test for each period of interval.

_______ _________CLASS 3 D-A 20 9 45  % 100% Code Case N-509 applies.

Pressure tests. System hydrostatic tests are counted as a required exam even though they are not D-A 12 0 0% 50% performed as allowed by Code Case N-498-1.

_______ _________ _______.I.WF Component Supports Class 1(F1.10) 31 12 39% 100% Exams performed in accordance with Code Case N-491-2 Class 2(F1.20) 52 19 37% 100% Exams performed in accordance with Code Case N-491-2 Class 3(F1.30) 69 28 41% 100% Exams performed in accordance with Code Case N-491-2 Supports other Exams performed in accordance with Code Case N-491-2 than Piping Supports 17 6 35% 100%

(F1.40)

Aug 1 0 0% 0% Augmented inspection of Non-Regenerative Heat Exchanger F-A 170 65 38% 100% Totals Page 6 of 14 5/22/2007 OAR-11

3R14 Refueling Outage IP3 Owner Activity Report Third Period E-A 1001% Per Period 0 0%6% General Visual examinations. 100%ý'

inspections completed for 1st and 2nd periods.

L-A N/A 0 66 %0% General Visual examinations. 100% concrete inspection completed twice to date in this interval.

Page 7 of 14 5/22/2007 OAR-1

Attachment 2 Page 8 of 14 Table 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE IP3 ISI Owners Activity Report (OAR)

Third Period, Third Interval

3R1 4 Refueling Outage IP3 Owner Activity Report Third Period

""TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination SchedulIed Section XI Examination or Test Category >lterin Number ~ Item Descrltlo n Flaw Characterizatios (lWA-330O), (Yes or No)

B-A B1.40 Reactor Vessel Head to Flange Weld Previously identified flaw (first found in 3R12) re-examined and Yes (volume with previously identified unchanged. This indication was still bounded by the previously flaw) performed (3R12) evaluation.

C-A C1.10 Steam Generator Shell CR-IP3-2007-1456 - 3 relevant indications were detected in weld Yes Circumferential Weld / Weld 32-6 32-6. All three relevant indications were evaluated and were acceptable per IWC-3500.

F-A F1.10 Multi Directional Restraint / SI-H&R- CR-IP3-2007-0961 - The support floor baseplate was missing Yes 843-5C approximately 1/2" of grout under the plate on 3 sides.

Engineering evaluated the condition and the indication was accepted as is.

F-A F1.10 Supports That Allow Thermal CR-IP3-2007-1008 - There was no indicator scale on the spring Yes Movement / SI-H-16A-12 support. Engineering examined the support and determined that it was in its working range with accomodation for thermal movement. Engineering evaluated the condition and the indication was accepted as is.

F-A F1.20 Supports That Allow Thermal CR-1P3-2007-0880 - The indicator scale on the spring can was Yes Movement / AC-H-210 painted over. Engineering examined the support and determined that it was in its working range with accomodation for thermal movement. Engineering evaluated the condition and the indication was accepted as is.

F-A F1.20 Multi Directional Restraint / SI-H&R- CR-IP3-2007-1009 - Minor cracking of the grout at the support Yes 846-8B-U baseplate was found. Engineering evaluated the condition and the indication was accepted as is.

F-A F1.30 Multi Directional Restraint / SW-H&R- CR-IP3-2007-1010 - A 3/8" gap was found between the locknut Yes 12C-17 and jam nut on one of 4 pipe clamp bolts. Engineering evaluated the condition and indication was accepted as is.

F-A F1.30 Multi Directional Restraint / CT-H- CR-IP3-2007-0276- Approximately 25% of the weld on the Yes 1071-4 attachment to the pipe was missing. Engineering evaluated the condition and the indication was accepted as is.

F-A F1.30 Multi Directional Restraint / CT-H- CR-1P3-2007-0280 - The sliding surface of the support was Yes 1071-7 painted. Engineering evaluated the condition and the indication was accepted as is F-A F1.30 Multi Directional Restraint / CT-H&R- CR-IP3-2007-0281 - The U-bolt nut configuration was not in Yes 1076-3A accordance with the drawing. Engineering evaluated the condition and the indication was accepted as is.

F-A F1.40 Supports Other Than Piping / 32 Aux CR-IP3-2007-0275 - Moderate corrosion was found on the inside Yes Feedwater Pump Support surface of the pump supports. Engineering evaluated the condition and the indication was accepted as is.

Paae 9 of 14 C Ifln~I, f-,

Ul/ce./I"UU 1-Jk \R-1

Attachment 3 Page 10 of 14 Table 3 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE IP3 ISI Owners Activity Report (OAR)

Third Period, Third Interval

3R14 Refueling Outage IP3 Owner Activity Report Third Period TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE CODE epai Flaw or Relevant Quality ~,Replacment or C -1 odto on R/R Item No. Group I Corrective Item Description and Description of Work Ye/N During Scheduled Date Completed Work Ordier Number Class ~

Meaur .~~~Examination or Test~

,(Yes/No) 734 3 Replacement Replace 18" line-407 piping down stream of valve SWN-34-2 y- N 1/23/2007 13-01 01 94900 958 3 Replacement Replace bolting on 32 Fan Cooler Unit N N 12/8/2005 02-19297 962 3 Replacement Replace 32 Service Water Pump N N 5/27/2005 02-19719 983 2 Replacement Replace 31 Recirc Pump N N 3/26/2007 04-1 6757 985 2 Replacement Replace 32 Recirc Pump N IN 3/26/2007 05-11251 05-3-20 3 Replacement Replace valve SWN-TCV-1 310 N N 11/10/2005 04-18010 05-3-21 3 Repair Repair SWN-1 -3 internals N N 1/27/2006 03-11106 05-3-22734 3

__3__ Replacement Replacement__ Replace valvein-0 iigdonsra 1 SWN-TCV-131 f av W-42 N N 11/10/2005

/320 04-20515 Palcge 1-0119490 1 05-3-23 2 Replacement Replace the support angle on SI-R-56-11-G N Y 8/30/2005 05-1 3913 05-3-24 2 Replaceme nt Install shim on support SI-R-56-1A-G N Y 8/29/2005 05-13915 05-3-25 3 Replacement Replace support SWN-H&R-1 084-3-R N Y 11/13/2006 04-14367 05-3-27 3 Replacement Replace valve SWN-TCV-1 312 N N 2/8/2006 04-20671 05-3-28 3 Replacement Replace valve SWN-63-1 N N 11/21/2005 04-14372 05-3-29 3 Replacement Replace valve SWN-TC V-i1313 N N 2/18/2006 04-20675 05-3-32 3 Repair Repair weld on valve SWN-35-2 Y N 11/10/2005 05-00512 5/22/2007 OAR-1

3R14 Refueling Outage IP3 Owner Activity Report Third Period TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE A. CODE ~Repairi F law or Relevant R/R Item Quality, Replacment or CC N416 ConditionlFound No ru orcieIem Description and Description of Work Ye/o During Scheduled ~Date Completed Work Order Number Class Measure xamnaton 05-3-33 3 Replacement Replace 31 Service Water pump and motor N N 12/7/2006 02-19107 05-3-34 3 Repair Repair support SWN-H&R-1086-3-R N Y 6/7/2006 05-00030 Repair through wall leak on 14" line-1 086 off 36 Service 05-3-36 3 Repair Water pump Y N 3/13/2006 05-21802 05-3-37 3 Repair Repair (weld build up on) valve SWN-1-2 internal tabs Y N 11/9/2005 03-11105 05-3-38 3 Repair Repair support SWN-H&R-1083-3-R N N 10/2/2006 05-20383 05-3-40 3 Replacement Replace flange bolting on 31 Fan Cooler Unit N N 12/3/2005 02-19322 05-3-41 3 Replacement Replace brazed joint on 32 Central Control Room AC Unit N N 12/7/2005 05-24740 06-3-47 3 Replacement Replace front cover on 32 Central Control Room AC Unit N N 2/9/2006 05-13958 Replace 31 Central Control Room AC Unit heat exchanger 06-3-49 3 Replacement heads N N 6/22/2006 05-18793 Replace 31 Central Control Room AC Unit outlet valve SWN-06-3-50 3 Replacement TCV-1 311 N N 10/13/2006 05-24149 06-3-53 3 Repair Repair (weld build up on) valve SWN-1 -3 hinge bracket tabs N N 10/4/2006 06-10932 06-3-54 1 Replacement Replace flange bolting on valve PCV-464 N N 3/26/2007 05-16315 06-3-55 1 Replacement Replace flange bolting on valve PCV-466 N N 3/26/2007 05-16316 06-3-56 1 Replacement Replace flange bolting on valve PCV-468 N N 3/26/2007 05-16317 Replace 32 Central Control Room AC Unit outlet control 06-3-57 3 Replacement valve SWN-TCV-1310 N N 10/13/2006 05-24148 Page 12 of 14 5/22/2007 OAR-1

3R14 Refueling Outage IP3 Owner Activity Report Third Period 06-3-58 3 Replacement Replace SWN-9-3 vacuum breaker N N 12/28/2006 06-10917 06-3-60 3 Repair Repair (weld build up on) valve SWN-1-5 hinge bracket tabs N Y 10/30/2006 03-17270 06-3-65 3 Replacement Replace valve AC-755A bonnet cap screws N N 3/24/2007 03-24337 Replace 32 CCW heat exchanger inlet piping and 3/4' valve SWN-06-3-66 3 Replacement 217 Y N 1/23/2007 13-010194900 Replace 35 Fan Cooler Unit motor cooler heat exchanger flex hose 06-3-69 3 Replacement flange and degraded bolting N N 11/28/2006 06-24321 06-3-70. 3 Replacement Replace SWN-9-1 vacuum breaker and bolting N N 12/7/2006 05-23183 06-3-71 3 Replacement Replace SWN-9-4 vacuum breaker and bolting N N 2/2/2007 06-12561 06-3-72 3 Replacement Replace 31 Service Water Pump expansion joint and bolting N N 12/7/2006 02-19107 Repair 31 CCW heat exchanger weld leak up stream of valve SWN-06-3-74 3 Repair 34-1 Y N 2/7/2007 06-01417 07-3-01 1 Replacement Replace 33 Reactor Coolant Pump rotating element assembly N N 3/27/2007 05-16481 Install hydro test connection between valves SI-MOV-885A and SI-07-3-03 . 2 Replacement MOV-885B N N 3/11/2006 06-21396 07-3-04 . 2 Replacement Install re-designed support base on support SI-H-293-3-S N N 3/26/2007 06-24230 07-3-05 2 Replacement Install re-designed support base on support SI-H&R-293-2-G N N 3/26/2007 06-24230 07-3-06 -2 Replacement Replace 2" line-92 piping Y N 3/26/2007 06-24230 07-3-07 2 Replacement Install new support SI-R-92-3-R N N 3/26/2007 06-24230

___Page 13 of 14 5/22/2007 OAR-1

3R14 Refueling Outage IP3 Owner Activity Report Third Period TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE CODE ReparFaw or Relevant <

R/R Item, Quality Replacment or4 CCN46 Cndto on No. Group I Corrective IeDscription and Description of Work YeJo During ScheduledI Date Completed Work Order Number Examination or Test Class Measure 07-3-08 2 Replacement Install three new lifting lugs to support beam SI-H-293-3-S N N 3/26/2007 06-24230 07-3-09 2 Replacement Replace missing collar on support pin N N 3/20/2007 07-14521 07-3-10 3 Replacement Replace valve CD-1 22 Y N 3/23/2007 07-14988 07-3-11 2 Replacement Install helicoil in 31 Steam Generator hand hole 'A'bolt hole #2 N N 3/16/2007 07-15441 07-3-12 2 Replacement Replace one damaged bonnet stud and nut on valve MS-1-33 N N 3/20/2007 03-24561 Replace valve and pipe flange bolting on valve AC-819B on 31 07-3-13 3 Replacement RHR heat exchanger N N 3/17/2007 05-18272 Replace one stud and nut on 32 Steam Generator secondary 07-3-14 2 Replacement manway N N 3/23/2007 06-10158 07-3-15 2 Replacement Replace bonnet studs and nuts on 4" valve MS-42 N N 3/20/2007 03-14218 07-3-16 3 Replacement Replace bolting on 18" valve SWN-40-1 N N 3/25/2007 03-11111 07-3-17 3 Replacement Replace bolting on 18" valve SWN-40-2 N N 3/25/2007 03-11112 07-3-18 1 Replacement Replace #9 and #10 Hot Leg manway studs N Y 3/25/2007 07-17030 07-3-19 3 Repair Repair through wall leak on pipe down stream of SWN-38 Y N 3/28/2007 07-17850 Machine thermal barrier gasket seating surface on 33 Reactor 07-3-20 1 Repair Coolant Pump N N 3/27/2007 05-16481 Page 14 of 14 5/22/2007 OAR-1

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