ML030700530

Annual Operating Report

ML030700530
Person / Time
Site:	Cook
Issue date:	02/28/2003
From:	Greenlee S Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:3691-01
Download: ML030700530 (13)

Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1373 INDIANA MICHIGAN POWER February 28, 2003 AEP.NRC:3691-01 Docket Nos: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN" Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 2002 ANNUAL OPERATING REPORT Technical Specifications 6.9.1.4 and 6.9.1.5 of Appendix A to the Donald C.

Cook Nuclear Plant Unit 1 and Unit 2 Operating Licenses require that an annual report be submitted to address personnel exposure, steam generator in-service inspection results, challenges to power-operated relief and safety valves, and information regarding any instances when the 1-131 specific activity limit was exceeded. Consistent with these requirements, a copy of the 2002 annual operating report is attached There are no new commitments in this submittal. Should you have any questions, please contact Mr. Brian A. McIntyre, Manager of Regulatory Affairs, at (269) 697-5806.

Sincerely, SA.Greenlee Director of Nuclear Technical Services DB/rdw Attachment Aoo(

U.S. Nuclear Regulatory Commission AEP:NRC. 3691-01 Page 2 c: K. D. Curry, Ft. Wayne AEP, w/o attachment J. E. Dyer, NRC Region III J. T. King, MPSC, w/o attachment MDEQ - DW & RPD, w/o attachment NRC Resident Inspector J. F. Stang, JR, NRC Washington, DC

U.S. Nuclear Regulatory Commission AEP:NRC:3691-01 Page 3 be: A. C. Bakken III, w/o attachment M. J. Finissi, w/o attachment S. A. Greenlee D. W. Jenkins, w/o attachment J. A. Kobyra, w/o attachment B. A. McIntyre, w/o attachment J. E. Newmiller J. E. Pollock, w/o attachment D. J. Poupard M. K. Scarpello, w/o attachment T. K. Woods, w/o attachment

ATTACHMENT TO AEP:NRC:3691-01 2002 Annual Operating Report

1.0 INTRODUCTION

Plant Description Indiana Michigan Power Company is the licensee for Donald C. Cook Nuclear Plant. The plant is located north of Bridgman, Michigan. The plant consists of two nuclear units employing a Westinghouse pressurized water reactor nuclear steam supply system. Each reactor unit employs an ice condenser reactor containment system. The American Electric Power Service Corporation is the architect-engineer and constructor.

Unit 1 and 2 reactor licensed power levels are 3304 Mwt and 3411 Mwt, respectively.

The main condenser cooling method is open cycle using Lake Michigan water as the cooling source for each unit.

2.0 PERSONNEL RADIATION EXPOSURE

SUMMARY

Page 2 of this attachment provides the number of station, utility, and contractor/other personnel receiving exposures greater than 100 millirem (mrem) in 2002. This estimated dose is based on electronic dosimetry and reported in the format specified by Regulatory Guide 1.16.

The values shown in the individual categories (routine maintenance, etc.) represent the number of people who received greater than 100 mrem in that particular category. The grand total figure represents the total number of people who received 100 mrem, whether in one of the categories or multiple categories. A specific person could receive dose in two or more categories, but they would be counted only once in the grand total. Also, a specific person could receive less than 100 mrem in several categories, but have a total dose greater than 100 mrem As a result, the sum of the individual category totals does not necessarily equal the grand total.

Attachment to AEP:NRC:3691-01 Page 2 Reg Guide 1.16 Report INDIANA MICHIGAN POWER / COOK NUCLEAR PLANT Prepared for Year 2002 Number of Personnel and Person-Rem By Work and Job Function Number of Personnel > 100 mrem Total Person-Rem Station Utility Contractors Station Utility Contractors Employees Employees and Others Employees Employees and Others Reactor Operation & Surveillance

-Maintenance 11 6 1 2952 1 279 1.085

-Operations 2 0 0 2 502 0.000 0 314

-Health Physics 0 0 0 0139 0001 0.012

-Supervisory 0 0 0 0010 0000 0.012

-Engineering 1 0 2 0 468 0 006 0.381 Routine Maintenance

-Maintenance 1 0 1 2 306 0 043 1.269

-Operations 0 0 0 1.083 0 002 0 083

-Health Physics 9 0 0 3 004 0 006 0 278

-Supervisory 0 0 0 0 020 0.000 0 007

-Engineering 0 0 0 0 227 0 003 0.183 Inservice Inspection

-Maintenance 3 0 103 1 276 0.000 34.565

-Operations 3 0 3 1.399 0000 1.696

-Health Physics 9 0 8 3.271 0045 4.105

-Supervisory 0 0 2 0000 0000 1.112

-Engineering 0 0 46 0.097 0.000 24 751 Special Maintenance

-Maintenance 5 0 27 1.822 0.000 12069

-Operations 0 0 0 0.107 0.000 0046

-Health Physics 2 0 2 0.491 0.000 0.342

-Supervisory 0 0 0 0.002 0.000 0 016

-Engineering 1 0 0 0.176 0.000 0 304 Waste Processing

-Maintenance 0 0 0 0.092 0.006 0 217

-Operations 0 0 1 0.108 0.000 0 198

-Health Physics 3 0 1 1.509 0.000 0 435

-Supervisory 0 0 0 0 009 0 000 0 000

-Engineering 0 0 0 0030 0001 0 002 Refueling

-Maintenance 61 1 310 15674 0478 105.795

-Operations 37 0 22 13.547 0 009 7.419

-Health Physics 30 0 59 14,147 0040 23.138

-Supervisory 4 0 2 0 987 0.000 0.666

-Engineering 9 0 5 3 068 0 019 2.063 Totals

-Maintenance 82 7 436 24.123 1.808 155002

-Operations 56 0 26 18.746 0.011 9756

-Health Physics 41 0 65 22.560 0.093 28 309

-Supervisory 4 0 4 1.028 0.000 1.813

-Engineering 11 0 52 4.066 0.029 27.684 Grand Totals 194 7 583 70.523 1.941 222.563

Attachment to AEP:NRC: 3691-01 Page 3 3.0 STEAM GENERATOR INSPECTIONS Acronym Listing TW Thru-Wall 07H, 04C Support Plate Location corresponding to 7h hot leg support, 4th cold leg support, etc.

BLG Bulge EPRI Electric Power Research Institute FSH Free Span History INR Indication Not Reportable MBH Manufacturing Burnish Mark History MBI Manufacturing Burnish Mark Indication MBM Manufacturing Burnish Mark NDF No Degradation Found NHE No Hydraulic Expansion PLP Possible Loose Part PSI Preservice Inspection PVN Permeability Variation Rxx/Cyy Tube location coordinate corresponding to Row xx and Column yy SG Steam Generator 3.1. Unit 1 Inspection Scope Eddy current inspection of Unit 1 SGs was performed during May 2002. This was the first in-service examination of the SGs since replacement in December 2000. The inspection scope consisted of a 100 percent full-length bobbin coil examination of the tubes in each of the four SGs. In addition, special examinations were performed in areas of interest using rotating probes to better characterize select bobbin coil signals. The following tables provide a breakdown of the inspections performed.

Base Examination SG 11 SG 12 SG 13 SG 14 Tubes Tubes Tubes Tubes Examined Examined Examined Examined Bobbin -iFull Length 3496 3496 3496 3496

Attachment to AEP:NRC:3691-01 Page 4 Special Interest - SG 11 SG 12 SG 13 SG 14 Rotating Coil Tubes/Locations Tubes/Locations Tubes/Locations Tubes/Locations Examined Examined Examined Examined Bobbin Signal Diagnostics 2/3 0/0 1/11 1/1 (MBI)

Ding/Dent 0/0 0/0 0/0 1/1 20 percent MBH 12/12 10/10 29/36 14/20 PLP & Bounding 0 0 9/92 0 Expansion I I

1. Rotating coil examination of this indication was waived based upon similarity to other MBI bobbin coil signals and the decision to administratively plug all the affected tubes.

2. Bobbin PLP indication and surround tubes examined from the hot leg tubesheet top to the first hot leg support 3.1.1 Inspection Results The following table and associated discussion summarizes the reported indications found during the inspection.

Indication Test SG11 SG 12 SG13 SG14 Ding Bobbin 0 1 0 4 Dent Bobbin 0 0 1 0 MBH Bobbin 56 48 176 88 MBI Bobbin 3 0 1 1 MBM Rotating 9 7 30 16 PLP Rotating 0 0 1 0 Less than 20 percent TW Bobbin 0 0 0 1 Greater than or equal to Bobbin 0 0 0 0 20 percent TW Ding/Dent A combined total of one dent (tubing diameter less than nominal at a support) and five dings (tubing diameter less than nominal in the freespan tubing) were reported using a two volt criteria during the bobbin coil examination. A sample of the reported locations was examined with a rotating coil with NDF.

Attachment to AEP:NRC:3691-01 Page 5 Manufacturing Burnish Marks (MBM/MBI/MBH)

A small population of MBH indications was found in each SG as noted in the above table.

Samples of the MBH indications reported during the bobbin coil examination were examined with a rotating coil The results of this examination revealed the presence of either NDF or MBM at the examined location. No degradation was found to be associated with any of the reported MBH indications.

Four tubes (five indications) were reported as MBIs during the bobbin coil examination.

Note that the difference between an MBI and an MBH is that an MBH is present during the original baseline examination and basically exhibits little to no change in signal characteristics.

An MBI is either not present in the original baseline examination or is present but exhibits significant change in signal characteristics. During the in-service bobbin coil examination the subject indications were found to have changed in amplitude anywhere from 1.0 to 2.5 volts.

Rotating coil examination revealed no material loss and no identifiable form of degradation in the area of interest. The four impacted tubes were preventatively plugged due to the unexplained signal change. Subsequent review of the indications by EPRI noted that they were characteristic of benign signals originating from tube buffing operations following thermal treatment during the original manufacturing process.

Possible Loose Part Tube R3/C23 in SG 13 was reported as having a possible loose part indication located approximately 6.62 inches above the hot leg top of tubesheet. The indication was reported during the bobbin coil examination with subsequent rotating coil exams being performed for indication confirmation. This tube and eight additional tubes in the surrounding area were examined with a rotating coil The results of the rotating exam were more indicative of a sludge deposit/scaling than a loose part. Neither the eddy current nor subsequent secondary side inspections identified any loose parts or degradation in any of the tubes.

Tube Wear (less than 20 percent)

Tube R53/C53 in SG 14 had confirmed wear at the fan bar 5 plus 0.61 inches support location. The bobbin coil TW depth measurement for this indication measured 8 percent TW.

As the wear depth was well below the Technical Specification repair limit of 40 percent TW, the tube was left in service. There were no additional wear indications reported in any SG.

Attachment to AEP:NRC:3691-01 Page 6 3.1.2 Plugged Tubes As discussed in Section 3.1.1 above, four tubes were preventatively plugged due to unexplained signal changes. The impacted tube and associated indication information is provided in the table below.

SG Tube ID Indication SG 11 R16/C40 MBI @ 5h cold leg support plus 37.06 inches MBI @ 6th cold leg support plus 34.48 inches SG 11 R13/C85 MBI @ tube sheet cold plus 14.97 inches SG 13 R19/C61 MBI @ 6th cold leg support plus 19.45 inches SG 14 R69/C45 MBI @ 1"cold leg support plus 12.06 inches 3.2. Unit 2 Inspection Scope An eddy current inspection of the Unit 2 SGs was performed in January - February of 2002.

The base inspection scope consisted of a 50 percent full-length bobbin coil examination of the tubes in each of the four SGs Ubends (07H-07C) of Rows 1 and 2 were not examined with the standard 720 bobbin coil probe due to potential difficulty in transversing across the low row ubends A smaller diameter bobbin coil probe could not be used in this application as such a probe has insufficient fill factor to be qualified for that area of the tubing. As a result, a sample inspection using rotating coils was performed on 100 percent of the Row 1 and 2 in-service tubes in one SG.

In addition, special interest examinations were performed in areas of interest using rotating probes to better characterize select bobbin coil signals. Rotating inspections were also performed in areas of interest (e.g. hot leg top of tubesheet and in service Row 1 and 2 tubes in select SGs). The following tables provide a breakdown of the inspections performed.

Base Examination SG 21 SG 22 SG 23 SG 24 Tubes Tubes Tubes Tubes Examined Examined Examined Examined Bobbin - Full Length 1796 1796 1796 1796

Attachment to AEP:NRC:3691-01 Page 7 Special Interest - SG 21 SG 22 SG 23 SG 24 Rotating Coil Tubes/Locations Tubes/Locations Tubes/Locations Tubes/Locations Examined Examined Examined Examined Bobbin Signal 17/22 13/13 8/11 22/23 Diagnostics (MBH, MBM, Ding, Dent, Bobbin - NHE 0/0 2/2 2/2 0/0 Rotating Examination SG 21 SG 22 SG 23 SG 24 Tubes Tubes Tubes Tubes Examined Examined Examined Examined 20 percent Hot Leg 720 0 0 0 Top of Tubesheet (plus/minus 3")

PLP & Bounding 15 0 0 0 Expansion (various)

In-service Low Row 0 0 190 0 Ubends - (07H-07C) 3.2.1 Inspection Results The following table and associated discussion summarizes the reported indications found during the inspection.

Indication Test SG21 SG22 SG23 SG24 BLG Bobbin 1 0 0 2 Ding Bobbin 72 30 19 61 Dent Bobbin 4 12 21 2 FSH Bobbin 0 1 0 0 MBH Bobbin 18 11 10 23 MBI* Bobbin 0 0 1 4 MBM Rotating 0 0 1 4 NHE Bobbin 0 2 2 0

Attachment to AEP:NRC:3691-01 Page 8 Indication Test SG 21 SG 22 SG 23 SG 24 PLP Rotating 5 0 0 0 PVN Bobbin 1 0 0 1 Less than 20 percent TW Bobbin 1 0 0 0 Greater than or equal to 20 Bobbin 0 0 0 0 percent TW I I I I_ I

• All MBI indications were examined with a rotating coil and confirmed as MBMs.

Dent/Ding A combined total of 39 dents and 182 dings were reported using a 2-volt criterion during the bobbin coil examination. A 20 percent sample of the reported dent/ding locations was examined with a rotating coil. No degradation was detected at any of the dent/ding locations.

No Hydraulic Expansion A total of four tubes were reported as not having a hydraulically expanded tubesheet region.

SG 22 had two tubes not fully expanded in the cold leg tubesheet while SG 23 had two tubes not fully expanded in the hot leg tubesheet. All four tubes were examined for the full length of the tubesheet with a rotating coil. No degradation was detected in any of the non-expanded areas of these tubes. Following consultation with the SG manufacturer and review by Design Engineering, the tubes were left in service.

Free Span History/Manufacturing Burnishing Marks (FSH/MBH/MBL/MBM)

A small population of freespan indications was noted during the bobbin coil examination.

Indications were compared with original baseline date and those found to have experienced insignificant change were reported as FSH or MBH. Indications that could not be reviewed in the original baseline or exhibited significant change were called MBI. SG 23 had one MBI indication and SG 24 had four MBI indications All of the MBI indications were subsequently examined with a rotating coil and the results of the examination revealed the presence of MBMs at the examined location. No degradation was found to be associated with any of these indications.

In addition, a 20 percent sample of the reported MBH and FSH indications were examined using a rotating coil. No degradation was noted during these enhanced examinations.

Attachment to AEP:NRC:3691-01 Page 9 Possible Loose Parts A total of five tubes were reported as having PLP indications above the hot leg top of tubesheet in SG 21. Three of the reported indications (R22/C50, R23/C50, & R42/C50) were detected during the planned rotating coil examination of the top of the tubesheet. The other two indications (R41/C51 & R42/C51) were found during a 15-tube expansion program Visual inspection of tubes R22/C50 and R23/C50 revealed a sludge rock affixed to the tubes. The visual inspection performed on tubes R42/C50, R41/C51, and R42/C51 revealed a loose part in the vicinity of these tubes. The sludge rock was left in place because it is softer than the tubes and cannot cause any damage, while the loose part was removed.

There was no degradation detected in any of the tubes with the reported PLP indications.

Tube Wear (less than 20 percent)

Tube R6/C53 in SG 21 had confirmed wear at the 6h hot leg support minus 0.60 inches location. The bobbin coil TW depth measurement for this indication measured 9 percent TW.

The indication was also examined with a rotating coil, which confirmed wear at the edge of the support less than 10 percent. This indication was previously reported and confirmed as less than 10 percent wear during the last (1997) inspection. As the indicated depth was well below the Technical Specification repair limit of 40 percent TW, the tube was left in service.

Three other previously reported (1997) and confirmed low level (less than 10 percent) support plate wear indications were initially reported as INR during this outage due to the small amplitude and indiscernible signal response observed during the bobbin coil examination performed on the tubes. These indications were all located in SG 21 at the designated support locations: R6/C53 (5H) and R5/C54 (5H & 4H). The indications were ultimately reported as 0 percent TW to allow for ease of identification for future examination.

3.2.2 Plugged Tubes No tubes were plugged in any of the four SGs during the 2002 Unit 2 inspection 4.0 CHALLENGES TO PRESSURIZER POWER OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES There were no challenges to the pressurizer PORVs or the pressurizer safety valves on either Unit 1 or Unit 2.

Attachment to AEP:NRC:3691-01 Page 10 5.0 REACTOR COOLANT SPECIFIC ACTIVITY There were no instances in which the reactor coolant dose equivalent 1-131 specific activity exceeded the limits of Technical Specification 3.4.8 (greater than or equal to 1 tCi/g) in either Unit 1 or Unit 2. Compliance was determined by routine gamma spectrometry analysis of reactor coolant.