RNP-RA/15-0081, Submittal of Ninety-Day Inservice Inspection Summary Report

Submittal of Ninety-Day Inservice Inspection Summary Report

ML15260A543
Person / Time
Site:	Robinson
Issue date:	09/17/2015
From:	Glover R Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/15-0081
Download: ML15260A543 (9)

Text

R. Michael Glover H B Robmson Steam Electnc Plant Umt 2 Sffe Vtce President Duke Energy Progress 3581 West Entrance Road Hartsvtfle SC 29550 0 843 857 1704 F 843 857 1319

~\like. Glo1*~t@ Juke*tnogy. ct~m 10 CFR 50.55a Serial: RNP-RA/15-0081 SEP 17 2015 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 /RENEWED LICENSE NO. DPR-23 SUBMITTAL OF NINETY DAY INSERVICE INSPECTION

SUMMARY

REPORT Ladies and Gentlemen:

In accordance with the requirements of 10 CFR 50.55a, "Codes and Standards," Duke Energy Progress, Inc., is providing, as an attachment to this letter, the lnservice Inspection Summary Report for Class 1 and Class 2 pressure retaining components and their supports. This report has been prepared in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2007 Edition, 2008 Addenda, Article IW A-6000. This report is further prepared in accordance with the requirements of ASME Code Case N-532-5 , and it covers inspection activities before and during Refueling Outage 29 at the H. B. Robinson Steam Electric Plant, Unit No.2.

There are no regulatory commitments made in this submittal. If you have any questions regarding this submittal, please contact Mr. R. Hightower at (843) 857-1329.

I declare under penalty of perjury that the foregoing is true and correct.

Executed On: '\- \1-\S" Sincerely,

~A.-~

R. Michael Glover Site Vice President

United States Nuclear Regulatory Commission Serial: RNP-RA/15-0081 Page 2 of 2 RMG/am

Enclosure:

NINETY DAY INSERVICE INSPECTION

SUMMARY

REPORT cc: Mr. V. M. McCree, NRC, Region II Ms. M. C. Barillas, NRC Project Manager, NRR Mr. D. J. Galvin, NRC Project Manager, NRR Mr. K. M. Ellis, NRC Sr. Resident Inspector, HBRSEP Unit No.2

United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/15-0081 Page 1 of 7 (including cover)

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 INSERVICE INSPECTION

SUMMARY

REPORT FOR REFUELING OUTAGE 29

Form OAR-1 OWNER'S ACTIVITY REPORT Page 1 of 6 Report Number: _ __ , _ R " - F _ , 0 , _ - = . 2 9 " ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Plant: _ _ _ _ ___,_H""-.,8_,_.,_,R""o""'b'""in,.s""'o!.!.n_,_N_,_,u..,c""'l...

e a.,_r_,S...ta""t"'io..,_n..___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Unit No.:_ _---'2=---- Commercial Service Date: _ ___,0""'3,./"""07_,_,/'-'1-"9_,_7_,_1__ Refueling Outage No . :_---'-'R.,_F_,.0'""'-2..,9~

Current Inspection Interval: IWB. IWC.IWD. IWF: Fifth Interval IWEIIWL: Second Interval Current Inspection Period:

IWB. IWC.IWD. IWF: First Period of the Fifth Interval IWEIIWL: Second Period of the Second Interval Edition and Addenda of Section XI applicable to the inspection plans:

lSI: 2007 Edition Thru 2008 Addenda. IWE/IWL: 2001 Edition Thru 2003 Addenda Date and Revision of Inspection Plans:

lSI: RNP-PM-009. Revision 4. 09/25/2014 IWEIIWL: RNP-PM-007. Revision 5. 6/25/2014 Edition and Addenda of Section XI applicable to Repair/Replacement activities, if different than the Inspection Plans: N/A Code Cases used: N-639. N-731. N-729-1. N-770-1. N-586-1. N-460. N-532-5. N-600 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 _....,R..,_F"'0-__.2... 9 _ _ _ _ __

(Refueling Outage Number) conform to the requirements of Section XI.

Signed:~ ~wner's 1'14/IAHI, ~ Pllt!ti/IIUtJJate:-49'-L/-'-I...L.

Designee, }lie

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JS: wL-- - - - - - -

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 South Carolina and employed by HSB Global Standards of Hartford CT 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.

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.\. . .=~'-'---___.,~.......,.,.;;..__;:::....uf\.\...;::_____.;'----commissions_ ___.!..N,.,B..,..1...,3..,9""'30~Sc~2~64~A..,N!.!..II_...,..,..._ _ _ __

• Inspector's Signature National Board, State, Province, and Endorsements

Form OAR-1 OWNER'S ACTIVITY REPORT Page 2 of6 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number lnservlce Inspection Program Surface Indication identified on data sheet PT-15-088 did not meet the acceptance criteria of IWC-3514. The indication was removed by manual surface conditioning via WO 13528402 and an acceptable surface exam COUPLING TO PIPE was performed in accordance with ASME Section XI, 2007 Edition thru C-F-1, C5.30 (245/29) 2008 Addenda (reference data sheet PT-15-090) . Scope expansion to 8 additional components was performed with no further indications.

Summary No. 316600 has been re-scheduled for examination in RF0-31.

Reference NCR 751556.

A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with satisfactory results. NDE/Design Engineering evaluation EV-15-004 states the bounding technical requirement for support CPL-134-C is its ability to CLEVIS ROD HANGER F-A, F1.10A adequately support the loads imparted by line 2-CH-2502R-8A under all

{134/C) operating conditions. 134/C is a rod hanger support, and therefore supports only dead load of the piping system. The support will perform its function to support deadweight of the pipe as designed in the skewed position. Reference NCR 750210 and EC 300639.

A visual examination was performed on the component support to the WELDED SPRING requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with F-A, F1.10C HANGER satisfactory results. NDE evaluation EV-15-005 states the spring can is set (110/SI-2-451) per the drawing however, only appears to be off-scale, the as-found setting is acceptable. Accept-as-is A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with satisfactory results. NDE/Design Engineering evaluation EV-15-007 ROD HANGER references EC 300662, "BENT ROD EVALUATION FOR SUPPORT 218/D LINE F-A, F1.20A

{218/D) NUMBER 12-AC-601R-8" has evaluated the condition identified in NCR 750280 and NCR 750255 and has determined the condition is acceptable as-is. No rework or repair is required. EC 300662 is approved, thus no NCON assignment is required. Reference NCR 750255.

A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with satisfactory results. NDE/Design Engineering evaluation EV-15-003 states the impacted support, FW-2-6018, is on line 4-FW-24,"Auxiliary Feedwater to 'C' Steam Generator" and near mechanical penetration 59 entering into the containment building. This portion of line 4-FW-24 is analyzed in calculation FW-2-8402. As noted on sheet 1 of the piping isometric, this RESTRAINT SUPPORT F-A, F1.20B support (at node 6018) is not credited in the piping analysis and as such it

{265/FW-2-6018) is not required to restrain any design load. Therefore, line is considered to be fully operable regardless of the lSI as-found condition of the support. It is not known why the support is still installed (historical). Since the piping analysis asserts the support is still installed, just not active, the loose anchor condition shall be corrected (tightened) per WO 13523182 to ensure no adjacent SSCs could be impacted during a seismic event.

Reference NCR 749287. Condition remediated via WO 13523182.

Form OAR-1 OWNER'S ACTIVITY REPORT Page 3 of6 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with unsatisfactory results. Reference NCR 749793 and EV-15-006 for disposition. NDE/Design Engineering evaluation EV-15-006 states that support 215/FW-5A-6008 and the associated piping system is functional and will have performed their design function during the previous operating cycle. The hand tightened U-bolts do not pose a functionality concern for this support. Spring can supports are deadweight supports WELDED DUAL only. As the pipe is supported by the 1-beam on the bottom. The support F-A, F1.20C SPRING HANGER will function as a dead weight support with or without the U-bolt.

(215/FW-5A-6008)

Recommended action: Reset Spring can to 2,025 lbs (+- 101.25 lbs) (Cold Load) and torque U-bolt nuts. The issues were corrected in accordance with Work Order #13525015 and an acceptable reexamination was performed with satisfactory results.

References:

1. HBR2-10618 Sheet 74E

2. Grinnell Pipe Support Catalog

3. CPL-NBR2-C-Oll, Rev. 10, Civil Inspection Requirements.

A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with satisfactory results. NDE/Design Engineering evaluation EV-15-008 states SPRING HANGER F-A, F1.20C the thermal movement for the spring can is very small (0.038") and as long (218/SI-3-6308) as the spring can is not at the top or bottom of the range the as-found condition is acceptable. This NCR is for documentation only. No further action is required . Reference NCR 751666; Accept-as-is.

Form OAR-1 OWNER'S ACTIVITY REPORT Page 4 of 6 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number A visual examination was performed on the component support to the requirements of ASME Section XI, 2007 Edition thru 2008 Addenda with unsatisfactory results. NDE/Design Engineering evaluation EV-15-001 states The support design detailed on drawing G-190551 is comprised of 62 bolt pattern where support 105A/A is missing 111ock nuts and support 105A/B is missing 8 lock nuts. The purpose of a locking nut is to prevent the first nut from being allowed to loosen over time due to factors such as thermal growth of the support. The existing nuts that do not have a locking nut are still torqued and therefore the lack of a locking nut has not degraded the support. The locking nut should be installed to prevent the possibility of future degradation. 2 bolts on support 105A/A and 1 bolt on 105A/B were identified to not have a washer on the bolt head side of the bolted connection . Washers are used in bolted connections to distribute the pressure of the nut evenly over the surface, so that the surface isn't damaged, and to ensure that the nut is pressed against a smooth surface.

Based on pictures located in the world folder of the NCR the missing washers are not of structural concern . It does appear that for these bolts the bold head is not making full contact with the base material due to an interference with the weld . As such the bolt will not carry a tension load.

This connection is a shear connection. With the bolt installed it will still S/G "B" SUPPORT resist the shear forces and therefore perform its design function.

F-A, F1.40 LEGS A, B The flaking paint is a house keeping issue and does not affect the structural capacity of the support. There is debris located in the sliding plate area of the support. These supports are designed to thermally grow and move with the steam generator during plant heat up and cool down.

The debris within this movement area is comprised of dust, paint chips, and small portions of pipe insulation material. This material will not prevent the support from thermally growing and therefore will not prevent the support from performing its design function.

Recommended action:

The issues identified by this NCR should be corrected this outage to align with the design basis for this support. The locking nut and washers should be installed per the design. The chipped paint should be repaired. The debris located in the sliding area of the support should be cleaned up.

Inadequate housekeeping is a predecessor to FME problems.

The issues referenced were corrected in accordance with Work Order #13534971. An examination was performed after resolution of the unsatisfactory conditions with satisfactory results.

References:

l.G-190551, Rev. 8, Reactor Building Equipment Supports Sh. 1.

Reference NCR 749705.

Pressure Test Program Leak at casing studs 9 thru 12. Cleaned and VT-1 inspected via Work Order C-H, C7.10 EST-078, SI-Pump-B 13344925 with satisfactory results. Reference NCR 663924.

Two teaspoons of wet, discolored residue at the packing gland. No quantifiable leakage. Removed stud and performed VT-1 examination in C-H, C7.10 EST-078, Valve SI-868C accordance with Work Order 13350412 with satisfactory results.

Reference NCR 664339.

Form OAR-1 OWNER'S ACTIVITY REPORT page 5 0 f6 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number X teaspoon puddle of clear, wet boric acid at the flange housing stud. No EST-078, Pressure quantifiable leakage. Cleaned and performed a VT-1 examination in C-H, C7.10 Transmitter PT-934 accordance with Work Order 13350203 with satisfactory results.

Reference NCR 6644334.

Approximately two tablespoons of dry, discolored boric acid at the blind flange stud region in contact with a stud. Four studs were identified for B-P, B15.10 replacement as the result of a VT-1 examination in accordance with Work EST-083-1, Valve (Bolted connection Order 13524705. A satisfactory VT-1 examination was performed of the CVC-307D examination) new studs and the threaded region of the flange. Four new studs were installed and the gasket was replaced via Work Order 13524705.

Reference NCR 749815.

B-P, B15.10 Approximately 1 teaspoon of dry, discolored boric acid was found at the (Bolted EST-083-1, Valve body to bonnet stud region in contact with one stud. The stud was connections SI-850F removed and a VT-1 examination was performed in accordance with Work examination) Order 13524718 with satisfactory results. Reference NCR 749814.

Approximately 1 teaspoon of dry, white boric acid was found at the body B-P, B15.10 EST-083-1, Valve to bonnet stud region in contact with one stud. The stud was cleaned and (Bolted connection RC-569 inspected in accordance with Work Order 13524717. Evaluated for examination) acceptable condition per EC 300713.

Approximately 1 teaspoon of dry, white boric acid was found at the body B-P, B15.10 EST-083-1, Valve to bonnet stud region in contact with one stud. The stud was removed and (Bolted connection CVC-310B a VT-1 examination was performed in accordance with Work Order examination) 13524716 with satisfactory results.

Dry discolored boric acid at bolted gasket seal at one stud location. Stud EST-079, Valve C-H, C7.10 was removed and a VT-1 examination was performed in accordance with SI-891B Work Order 13528535 with satisfactory results. Reference NCR 751650.

Form OAR-1 OWNER'S ACTIVITY REPORT Page6 of6 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Date Repair/Replacement Code Class Item Description Description of Work Completed Plan Number Plugged S/G "C" hot leg and cold 1 S/G-C Hot Leg 3/25/2014 13359896-01 leg tubes at row 15 column 31.

1 CVC-313 REPLACE VALVE 3/30/2014 13363487-01 CVC-307D Replace the CVC-307D 1 5/27/2015 13524705-02 downstream blind flange 2 RHR-HTX-B REPLACED STUDS AND NUTS 4/10/2014 12273658-06 SI-890-B REPLACE VALVE DISC DUE TO 2 5/26/2015 13325672-01 INTERNAL WEAR CVC-277A REPLACE VALVE AND PIPING 2 5/14/2014 13381411-01 DUE TO SEAT LEAKAGE RHR-PMP-B REPLACE CASING STUD DUE TO 2 7/29/2014 13306737-01 LEAKAGE CVC-275A Valve bonnet replacement 2 5/27/2014 13389748-04 due to seat leakage 16-FW-10 Weld repair required following 3 flaw removal detected during 6/15/2015 13530418-01 UT examination 3 CVC-379 Replacing bonnet assembly 6/24/2014 12148373-01 3 CH-16-1011 REPLACE U-BOLT HANGER 6/13/2014 13397712-01 4-FW-32 Replace AFW branch connection 3 6/18/2015 13500661-11 TO 16-FW-9 Due To Weld Indication 16-FW-9 Replace TEE Due To Weld 3 6/19/2015 13500661-25 Indication 3 CV LINER Replace CV Liner Studs 6/6/2015 13301308-01 3 FCV-499 Replace Valve 5/16/2015 11436811-01 Note: Table 2 repair replacement activities required for continued service include all activities up to and including 08/18/2015.

Any repair replacement documentation closed after 08/18/2015 will be documented in the next OAR-1 Owner's Activity Report.