SVP-17-048, Owner'S Activity Report Submittal, Fifth 10-Year Interval 2017 Refueling Outage Activities

Owner'S Activity Report Submittal, Fifth 10-Year Interval 2017 Refueling Outage Activities

ML17186A028
Person / Time
Site:	Quad Cities
Issue date:	07/05/2017
From:	Ohr K Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-17-048
Download: ML17186A028 (10)

Text

xelo Gen ration SVP-17-048 July 5, 2017 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 NRC Docket No. 50-254

Subject:

Owner's Activity Report Submittal Fifth 10-Year Interval 2017 Refueling Outage Activities

Reference:

Letter from T. Tate (USNRC) to M. Pacilio (Exelon), "Quad Cities Nuclear Power Station, Units 1 and 2 -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval lnservice Inspection Program," dated September 30, 2013. This letter submits the Owner's Activity Report (i.e., Form OAR-1) and lnvessel Visual Inspection (IVVI) Report for the Quad Cities Nuclear Power Station (QCNPS) Unit 1 refueling outage (Q1 R24) which began on March 27, 2017, and was completed on April 14, 2017. This is the first refueling outage conducted in the Second (2nd) Inspection Period of the fifth (5 1 h) 10-year Interval lnservice Inspection (ISi) Program for QCNPS Unit 1. A copy of the Owner's Activity Report and IVVI Report are provided as attachments to this letter. Also, items that were not included in the Q2R22, Q1 R23, or Q2R23 90-day Summary Report are provided as attachments as well. This Owner's Activity Report is submitted in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission," and the referenced NRC Safety Evaluation, which authorized use of Code Case N-532-4 at QCNPS (i.e., Relief Request 15R-09). Code Case N-532-4 requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Code Case N-532-4, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage. The IVVI results are provided to report completed vessel internal inspections and to document B-N-1 and B-N-2 relief request exam completion.

Additionally, no welds were reclassified or changed status within the lntergranular Stress Corrosion Cracking (IGSCC) program this outage.

SVP-17-048 U.S. Nuclear Regulatory Commission Page 2 of 2 Should you have any questions concerning this letter, please contact Mr. Wally Beck, Regulatory Assurance Manager, at (309) 227-2800.

Res:;;t Kenneth S. Ohr Site Vice President Quad Cities Nuclear Power Station Attachments:

1. Owner's Activity Report, Form OAR-1 2. lnvessel Visual Inspection (IVVI) Report 3. Owner's Activity Report, Form OAR-1 {These are items that were not included in Q2R22, Q1 R23, or Q2R23 90-day Summary Report) cc: Regional Administrator

-Region Ill NRC Senior Resident Inspector, Quad Cities Station Report Number Plant Unit No. 1 (if applicable)

Current Inspection Interval Current Inspection Period Attachment 1 Owner's Activity Report, Form OAR-1 FORM OAR*1 OWNER'S ACTIVITY REPORT Refueling Outage Q1R24 OAR-1 Quad Cities Nuclear Power Station, 22710 206 111 Ave. North, Cordova, IL 61242 Commercial Service Date ____

___ Refueling Outage Number

__ 5th Inspection Interval (ISI), 2n<1 Inspection Interval (Containment) (l't, 2'"', 3**, 4'", olher) 2st Inspection Period (ISI), 3 00 Inspection Period (Containment)

(1", 2"', 3"' J Edition and Addenda of Section XI applicable to the Inspection Plans 2007 Edition with 2000 Addenda (!SI), 2001 Edition with 2003 Addenda (Containment)

Date / Revision of Inspection Plans 3/19/16 / Revision 2 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-532-4 N-613-1, N-649 N-789 CERTIFICATE Of CONFORMANCE I 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) the repair/replacement activities and evaluations supporting the completion of Q1R24 conform to the requirements of Section XI Signed , ISI Coordinator (OWner or Owner's deslgnee.

Title) Date CERTIFICATE OF INSERVICE INSPECTION (refueling outage number) 06/15/2017 I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or The Hartford Steam Boiler Province of Illinois and employed by Inspection and Insurance of Hartford, Connecticut Company (HSB) have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report 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 repair/ replacement activities and evaluation described in this 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 IL 2211; NB13175 A, N, I (111S!iector's Signature)

National Board, State, Province, and Endorsements Examination Category and Item Number F-A & Fl.30 F-A & Fl.10 -------

---

Attachment 1 Owner's Activity Report, Form OAR-1 Page 2 of 4 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Item Description Evaluation Description 1001B-W-301.1 (1 VARIABLE SPRING CAN) IR 03995910, EC 619057 0200-W-119 A&B (2 SWAY BRACE SPRING CANS) IR 03993050 ------------------------------------------------

Code Class 1 2 3 MC 3 3 3 3 3 3 3 3 Attachment 1 Owner's Activity Report, Form OAR-1 Page 3 of 4 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Description Of Work Completed NEW CRD HOUSING BOLTING EXHIBITS DAMAGE (IR WO 01849793 -UNIT 1 CRDM REPLACEMENT 04/01/2017 03993859)

ISI 1-0203-2C MSIV DAMAGED THREADS ON 2 WO 01082330 -CONTINGENCY AO 1-0203-2C OVERHAUL 04/09/2017 STUDS/NUTS (IR 03995729)

WO 04621864 -PUMPS TO FAR OUT OF ALIGNMENT TO MAKE ADJUSTMENTS PSU Q1R24 1D RHRSW PUMP OUT OF ALIGNMENT (IR 04/07/2017 03993611) (SPRING CAN SUPPORT 1001B-W-301.1 (DETAIL DWG M-994D-603)

TO BE ADJUSTED UNDER WO 4624069 IN 01R25) DRYWELL HEAD BOLTING DAMAGED DURING WO 01849774 -RX DISASSEMBLY

& REASSEMBLY 04/03/2017 DISASSEMBLY

<IR 04017802)

VISUAL INTERNAL INSPECTION OF 1A HP RHRSW ELBOW WO 01772450 -1A RHRSW HIGH PRESSURE ELBOW EOC 10/26/2015 (IR 02384605)

INSPECTION VISUAL INTERNAL INSPECTION OF 1B HP RHRSW ELBOW WO 01772437 -1B RHRSW HIGH PRESSURE ELBOW EOC 04/29/2015 (IR 02492905)

INSPECTION VISUAL INTERNAL INSPECTION OF 1C HP RHRSW ELBOW WO 01772366 -1C RHRSW HIGH PRESSURE ELBOW EOC 08/20/2015 (IR 02544407)

INSPECTION VISUAL INTERNAL INSPECTION OF 1D RHRSW HP ELBOW WO 01772394 -1D RHRSW HIGH PRESSURE ELBOW EOC 08/04/2015 (IR 02537964)

INSPECTION 1C RHRSW SUCTION AND DISCHARGE VALVES NOT WO 01763590 -1C RHRSW SUCTION VALVE NOT 04/13/2017 ISOLATING (IR 01694057)

ISOLATING:

1-1001-lC NEED WO TO REPLACE N-789 REPAIRED AREA (IR 02548993)

WO 01858165 -REPLACE REPAIRED SECTION OF 1-3960-04/14/2017

& 4" CODE CASE N-789 04/13/2017 IEMA ID WATER ON FLOOR BAY 12/13 Ul RX BLDG BSMT (IR 02649481)

RHRSW VALVES FAIL TO ISOLATE SYSTEM WO 00784562-RHRSW VALVES FAIL TO ISOLATE 04/17/2017 (IR 00300886)

SYSTEM WATER ON FLOOR BAY 14 Ul RX BLDG BSMT (IR WO 01854438 -WATER ON FLOOR BAY 14 Ul RX BLDG 08/27/2015 02542834)

BSMT Repair/ Replacement Plan Number 16-067 16-079 17-015 17-046 17-067 16-070 15-055 15-037 15-058 15-081 16-031 16-069 16-074 17-041 15-098 Code Class 2 3 3 3 3 ----Attachment 1 Owner's Activity Report, Form OAR-1 Page 4 of 4 TABLE 2 (cont'd) ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Description Of Work Completed WRONG LINE WAS CUT DURING PERFORMANCE OF WO WO 01877257 -Ul HPCI CONDENSATE PUMP MOTOR 11/20/2015 1341322-01 (IR 01120271)

OVERLOAD UNIT 1A RHRSW VAULT COOLER UT RESULTS (IR WO 01661073 -REPAIR 1A RHRSW VAULT COOLER DUE 01/27/2016 01541334)

TO UT RESULTS IEMA ID WATER ON FLOOR BAY 12/13 Ul RX BLDG BSMT WO 01912871 -IEMA ID WATER ON FLOOR BAY 12/13 Ul 04/25/2016 (IR 02649481)

RX BLDG BSMT 1D RHRSW ROOM COOLER RO AND FE UT WO 01788407-1D RHRSW ROOM COOLER: REPLACE 11/16/2016 MEASUREMENTS (IR 02416825)

RESTRICTING ORIFICE PIPING UNIT 1D RHRSW CUBICLE COOLER UT RESULTS (IR WO 01684268 -REPLACE HEADERS ON 1D RHRSW 11/16/2016 01576837)

CUBICLE COOLER DUE TO UT RESULT ------------Repair/ Replacement Plan Number 15-145 15-146 16-024 16-071 16-072 ----

Attachment 2 In-Vessel Visual Inspection (IVVI) Report Page 1 of 2 The ASME Section XI inspections credited during Q1R24 IWI activities include the period B-N-1 inspection of the reactor vessel interior and B-N-2 inspections of reactor vessel interior attachments.

Credit is being taken for the BWRVIP examinations in place of the B-N-1 and B-N-2 examinations in accordance with Quad Cities Station Relief Request ISR-06, "Request for Relief for the Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Vessel Internals and Components Inspection In Accordance with 10CFR50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety". To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE-Hitachi (GEH) was contracted to perform the In-Vessel Visual Inspections (IWI). The following B-N-1 and B-N-2 components and assemblies were visually examined:

• Two (2) Core Shroud welded support structure/attachment welds HS and H9

• Five (5) Jet Pump Attachment welds RB-1

• Eight (8) Feedwater Sparger Attachment welds

• Reactor Pressure Vessel (RPV) interior surfaces in areas near BWRVIP exams in accordance with Relief Request ISR-06. Multiple indications (gouges and rub marks) were identified on all four of the Steam Dryer wall support lugs. These indications were previously observed in Q1R23. A comparison of the inspection results from Q1R23 to Q1R24 found no significant change to the previous indications and no new indications were identified.

These indications are documented in IR 3992081 and evaluated for continued service under EC 618731. Quad Cities will continue to monitor these conditions in accordance with the Reactor Internals Program. To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE-Hitachi (GEH) was contacted to perform the In-Vessel Visual Inspections (IWI). The following components and assemblies were examined:

• Sixty-nine (69) welds and components on jet pump assemblies via visual exam in accordance with the BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines."

• One hundred and nineteen (119) welds on jet pump assemblies via volumetric ultrasonic testing (UT) exam in accordance with the BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines."

• One (1) core spray piping repair clamp via visual exam in accordance with the BWRVIP-18 Revision 2 (-A), "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines."

• Four (4) core shroud repair mechanical hardware locations (i.e. Shroud tie rods) in accordance with BWRVIP-76 Revision 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines."

Attachment 2 In-Vessel Visual Inspection (IVVI) Report Page 2 of 2

• Four (4) core plate repair mechanical hardware locations (i.e. core plate wedges) in accordance with BWRVIP-25, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines."

• Top guide rim weld at twelve (12) unflawed cell locations in accordance with BWRVIP-26-A, "BWR Core Plate Inspection and Flaw Evaluation Guidelines."

• Nine (9) top guide grid cells via visual exam in accordance with the BWRVIP-183, "Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines."

• Four ( 4) top guide aligner assemblies in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".

• Steam dryer examinations of the two (2) tee to cap doubler welds, general visual examination top banks and sides, and VT examination of seventy two (72) welds. Dryer inspections were performed in accordance with BWRVIP-139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines".

In addition to the BWRVIP inspection guidance, the following augmented visual examinations were also performed as part of the Q1R24 IWI activities:

• Five (5) Nuclear Instrument Dry Tubes for cracking in accordance with GEH Services Information Letter (SIL) 409-Rev 5

• Ten (10) Nuclear Instrument Dry Tubes for upper plunger engagement in accordance with GEH SIL 409-Rev 5 and per programmatic requirements.

• Re-inspection of eight (8) end bracket and pin locations on four ( 4) feedwater spargers per Industry OPEX and ongoing wear

• Re-inspection of mechanical damage at four ( 4) steam dryer support lug locations per programmatic requirements.

• Twenty-four (24) steam separator support ring gussets and fourteen (14) steam separator peripheral standpipes including tie bar welds per programmatic requirements.

Examination Category and Item Number F-A & Fl.10 F-A & Fl.20 F-A & Fl.10 F-A & Fl.30 F-A & Fl.30 -----------------Attachment 3 Owner's Activity Report, Form OAR-1 Page 1 of 2 (These are items that were not included in the Q2R22, 01 R23, or Q2R23 90-Day Summary Report) TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDMONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Item Description Evaluation Description ISi POINT 1012A-M-105 . BOLT HEAD GAPS NOTED IN EXAM IR 02466233 SPRING CAN FOUND OUTSIDE TOLERANCE DURING VT-3 ON RHR IR 01641773 SUPPORT RI DURING VT-3 INSPECTION ON PIPE SUPPORT 0200-W-124A&B IR 01645312 UNIT 2 RHRSW PIPE SUPPORT M-3545A-21 RECORDABLE INDICATION IR 01647647 UNIT 2 RHRSW PIPE SUPPORT M-3545A-10 RECORDABLE INDICATION IR 01647666 ----------------------------------

Code Class MC 1 1 2 2 2 1 --------------Attachment 3 Owner's Activity Report, Form OAR-1 Page 2 of 2 (These are items that were not included in the Q2R22, Q 1 R23, or Q2R23 90-Day Summary Report) TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Item Description Date Description Of Work Completed PSU LOOSE BOLTING ON MC SUPPORTS WO 01730553 -LOOSE BOLTING ON U2 ACAD PIPING 04/22/2014 (IR 01647627)

SUPPORTS PSU -INDICATIONS ON RPV HEAD CLOSURE WASHERS WO 01585834 -RX DISASSEMBLY

& REASSEMBLY 04/25/2014 (IR 01647850)

PSU LOOSE NUT ON 2B RECIRC PUMP CONSTANT WO 01731184 -PSU LOOSE NUT ON 2B RECIRC PUMP 04/24/2014 SUPPORT (IR 01648346)

CONSTANT SUPPORT PSU RECORDABLE INDICATION ON Ul SBLC PIPE (IR WO 01812373 -RECORDABLE INDICATION ON Ul SBLC 03/07/2015 02463835)

PIPE REACTOR HEAD VENT PIPING INDICATION WO 01636433 -UPGRADE Ul HEAD VENT LINE SOCKET 03/11/2015 (IR 02464920)

WELDS TO EPRI 2: 1 LEG WELDS PIPING FLANGE INDICATIONS REACTOR HEAD WO 01636433 -UPGRADE Ul HEAD VENT LINE SOCKET 03/11/2015 INSTRUMENT PIPING (IR 02465139)

WELDS TO EPRI 2: 1 LEG WELDS NEW CRD STUD HAS A REJECTABLE VT-1 INDICATION (IR WO 01908610 -PSU CRD 26-15 LEAKING WATER FROM 03/28/2016 02645376)

FLANGE UNDER VESSEL ------------------------------------------Repair/ Replacement Plan Number 14-029 13-082 14-028 15-029 15-033 15-033 16-013 --------------