ML15205A289

Notification of Part 21 Report - Deviation in Nozzle Modeling Internal Reports

ML15205A289
Person / Time
Site:	Beaver Valley, Indian Point, North Anna, Ginna, Diablo Canyon
Issue date:	07/24/2015
From:	Wilson T Electric Power Research Institute
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
51181
Download: ML15205A289 (10)

Text

0 7/24/2O15 U.S. Nuclear Regulatory Commission Onerations Center Event Rennrt Non-Agreement State Event # 51181 Rep Org: ELECTRIC POWER RESEARCH INSTITUTE Notification Date/ITime: 06/25/2015 15:40 (EDT)

Licensee: ELECTRIC POWER RESEARCH INSTITUTE Event Date I Time: 05/01/2015 (EDT)

Last Modification: 07/24/2015 Region: 1 Docket #:

City: CHARLOTTE Agreement State: Yes County: License #:

State: NC NRC Notified by: TRACY WILSON Notifications: JOHN ROGGE R1 DO HQ Ops Officer: DONG HWA PARK KATHLEEN O'DONOHUE R2DO Emergency Class: NON EMERGENCY VIVIAN CAMPBELL R4DO 10 CFR Section:

21 .21 (a)(2) INTERIM EVAL OF DEVIATION PART 21 REPORT - DEVIATION IN NOZZLE MODELING INTERNAL REPORTS The following was received via facsimile:

"[This report pertains] to a deviation in a basic product (EPRI nozzle modeling internal reports) supplied by EPRI (Electric Power Research Institute) regarding Westinghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic Inspections. EPRI will complete all evaluation efforts and provide a determination of reportability in accordance with 10 CFR Part 21 no later than July 24, 2015.

"EPRI has conducted an evaluation to the basic product's actual use and determined that the ASME examination volume coverage for at least one of the pressurizer nozzles has changed and is now 90 percent or less. A 90 percent threshold is required by ASME Boiler & Pressure Vessel Code, Section Xl.

"Design inputs used in EPRI modeling for ultrasonic scanning coverage for nuclear safety related component nozzles may have been inaccurate. In some cases, the upper and lower heads of Westinghouse pressurizers can be offset from the center of each nozzle (spray, safety, relief, surge). This offset results in a change in the thickness of the pressurizer head as compared to an on-axis pressurizer head with the same radial dimensions.

Some of the computer models EPRI used to describe these pressurizer heads did not account for an increase in the thickness due to these offsets. As a result, in some cases the ultrasonic inspection parameters produced by these computer models may have produced inaccuracies in the examination volume coverage calculations.

"In the case of a basic component which contains a defect or falls to comply, the number-and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.

07/24/2015 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 2 Utility Name/Plant Name Exelon Corporation / Ginna First Energy Nuclear Operating / Beaver Valley 1 Entergy I Indian Point 2 Entergy I Indian Point 3 Pacific Gas & Electric Co. / Diablo Canyon Unit 2 Dominion Generation / North Anna "EPRI has reviewed the pressurizer upper and lower head drawings for the nozzles that it has modeled and determined if these offsets are present. For those cases that are potentially affected EPRI has recalculate the new examination volume coverage for the nozzle inspection detection techniques and provided this information to the corresponding licensees.

"EPRI staff shall develop a matrix or table to better define the necessary design inputs for computer modeling of nozzles. This should also include a question to the utility regarding any obstructions or thickness changes which '

would impact the ultrasonic inspection parameters. EPRI staff shall improve its documentation for review and approval of design inputs for computer modeling. Consideration shall also be given to including a review of design inputs by the member along with an acknowledgement from the member that the design inputs are appropriate for use. EPRI staff shall consider methods of including additional conservatism to the modeling results to better accommodate changes which may be observed in the field. The project quality plan and quality project instruction shall be updated as necessary to accommodate or clarify these improvements. Completion commitment date -

10/27/2015.

"The coverage calculations indicated in the notification letters would likely increase if the EPRI modeled scan plans are exceeded and or if additional inspection angles were implemented. Conversely, these coverage calculations would likely decrease if physical field limitations prevented the ultrasonic probe from executing the EPRI modeled scan pattern. It is on this basis that recipients of this letter must evaluate the condition pursuant to 10 CFR Part 21.21 to determine if it could represent a substantial safety hazard reportable under 10 CFR Part 21 ."

Potentially affected US plants include Ginna, Beaver Valley Unit 1, Indian Point Units 2 and 3, Diablo Canyon Unit 2, and North Anna.

• *

• UPDATE AT 0938 EDT ON 07/24/15 FROM NEIL WILMSHURST TO JEFF HERRERA VIA FACSIMILE ** *

"As part of the evaluation, EPRI [Electric Power Research Institute] performed an 'extent of condition' review.

During the course of the review, EPRI found that the above described deviation also affected EPRI nozzle modeling internal reports supplied by EPRI (Electric Power Research Institute) regarding Westinghouse Steam Generator Primary Nozzles.

"After conducting the 'extent of condition' review, which included recalculation of the modeling data, EPRI concluded that there were no other known reportable conditions associated with this deviation.

"EPRI has completed all evaluation efforts and issued reportability notification letters in accordance with 10CFR Part 21 within the respective reporting timeframes."

Notified the R1 DO (Kennedy), R2DO (Musser) and R4DO (Gepford) and Part 21 Group (via email).

~E2lRES(, I*.ClI INSrflruT

______ ~Message - -- j I*-* *r/L **_.. ..

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~RESEARCHI INSTITUTE

• I'!'NEIL WILMSNURST

• It Vice President and

• Chief Nltear Officer S July 22, 2:015 S U.S. Nuclear Regulatory Commission

,, Attn: Document Control Desk

" Washington, DC 20555-0001

Subject:

Final Report: Part 21 - Notification:

Westinghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic Inspections Dear Sir/M~adam; This letter constitutes the Electric Power Research Institute's (EPRI) final report addressing a deviation ina basic product (EPRi nozzle modeling internal reports) supplied by EPRI to its utility members regarding Westinghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic Inspections.

As part of the evaluation, EPRI performed an "extent of condition" review. During the course of the review, EPRI found that the above described deviation also affected EPRI nozzle modeling internal reports supplied by EPRI (Electric Power Research Institute) regarding Westinghouse Steam Generator Primary Nozzles.

After conducting the "extent of condition" review, which ihncluded recalculation of the modeling data, EPRI concluded that there were no other known reportable conditions associated with this deviation, EPRI has completed all evaluation efforts and issued reportability notification letters inaccordance with IOCFR Part 21 within the respective reporting timeframes.

i The information for this report per §21.21 isprovided inthe following attachments.

I' Ifyou have any questions, please contact me.

Sincerely, ii. NMW/rv/tw

[ Attachment(s)

Togethler . . . Shaping the Future oF: Electricity 1300 West W.T. Harris Boulevard, Charlotie, NC 28262-8550 USA

• 704.595.2732 *,Mobile 704,,490.2653 e nwilmshursttepricom

Part 21 - Final Report Notification:

Westinghouse Pressurizer Head Nozzle inner Corner Region Ultrasonic inspections Page 2 U.S. Plants Affected S - -A Exelon Corporation Ginna Pressurizer First Energy Nuclear Operating Beaver Valley 1 Pressurizer Entergy Indian Point 2 Pressurizer Entergy Indian Point 3 Pressurizer Pacific Gas &Electric Co. Diablo Canyon Unit 2 Pressurizer Dominion Generation North Anna Unit I Pressurizer Dominion Generation North Anna Unit 2 Pressurizer NOTE: Calculations for another twelve plants resulted inchanges to certain examination coverage calculations, but not to levels below the 90% threshold. EPRI has sent Information Notices to these plants.

Athird group of plants had no changes.

! Part 21 - Final Report Nolifocallon:

!* Westinghouse Pressurizer H-ead Nozzle Inner Corner Region UhIrasonlc Inspections

" Page 3 E;Attachment 2

'i Part 21.Reporting Information

,,, (i) Name and address of the Individual or individuals informing the Commission.

Neil M.Wilmshurst Vice President and CNO Electric Power Research Institute 1300 West WT Harris Blvd j Charlotte NC 28262-2867 (ii) Identification of the facility, the actlvity; or the basic component suppilied for such facility which fails to cOmply or contains a defect.

EPRI has conducted an evaluation to the basic product's actual use and determined that the ASME examination volume coverage for the pressurizer nozzles identified inthis letter have changed since oginael modeling calculations were preformed and are now 90% or less. A90% threshold is required by ASME Boiler &Pressure Vessel Code, Section Xl. .  :

! (i~i) Identification of the firm constructing the facility or supplying the basic component which S fails to comply or contains a defect.

'* EPRI supplied the basic product (report) to the licensees listed inTable 1from 2008 to the present.

!I (iv) Nature of the defect or failure to comply and the safety hazat'd which is created or could be i! created by such defect or failure to comply.

I'* Design inputs used inEPRI modeling for ultrasonic scanning, coverage for nuclear safety related

,4.component nozzles may have been inaccurate, insome cases, the upper and lower heads of

2. Westinghouse pressurizers can be offset from the center of each nozzle (spray. safety, relief, surge). This

. offset results ina change inthe thickness of the pressurizer head as compared to an on-axis pressurizer il head with the same radial dimensions (see examples inAttachment 3). Some of the computer models EPRI used to describe these pressurizer heads did not account for an increase inthe thickness due to these offsets. As a result, insome cases the ultrasonic inspection parameters produced by these computer models may have produced inaccuracies inthe examination volume coverage calculations. This offset condition was also found inthe case of some Westinghouse steam generator channel heads (refer to Figure 3).

(v) The date on which the Information of such defect or failure to comply was obtained.

,l An EPRI Corrective Action Report (CAR 2015-0032) to explore the extent of the issue was initiated on I

, May 2015..

.1

'I ii'

i Part 21 - Final Report Notification:

Westinghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic Inspections

=,;Page 4

, (vi) Inthe case of a basic component which contains a defect or fails to cornply1 the number i; and location of these components in use at, supplied for, being supplied for, or may be supplied i for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations inthis part.

i See Table 1.

(vii) The corrective action, which has been, is being, or will be taken; the name of the Individual

• , or organizationresponsiblefor the action; and the length of time that has been or will be taken to

,* complete the action.

i' EPRI has reviewed the pressurizer upper and lower head drawings for the nozzles that ithas modeled and i; determined that these offsets are present, Steam generator channel head drawings were as included inthis

! review. For those cases that are potentially affected EPRI has recalculated the new examination volume i! coverage for the nozzle inspection detection techniques and provided this information to the corresponding Ji licensees.

li EPRI staff shall develop a matrix or table to better define the necessary design inputs for computer

, modeling of nozzles. This should also include a question to the utility regarding any obstructions or i! thickness changes which would impact the ultrasonic inspedtion parameters. EPRI staff shall improve its i documentation for review and approval of design inputs for computer modeling. Consideration shall also be

!: given to including a review of design inputs by the member along with an acknowledgement from the

, member that' the design inputs are appropriate for use. EPRI staff shall consider methods of including

J!, additional conservatism to the modeling results to better accommodate changes which may be observed in

i the field. The project quality plan and quality project instruction shall be updated as necessary to

• i accommodate or clarify these improvements. Completion commitment date - 10/27/2015 h (viii) Any advice relatedto the defect or failure to comply about the facility, activity, or basic

" component that has been, is being, or will be given to purchasersor licensees.

• The coverage calculations indicated inthe notification letters would likely increase ifthe EPRI modeled scan plans were exceeded and or ifadditional inspection angles were implemented. Conversely, these i coverage calculations would likely decrease ifphysical field limitations prevented the ultrasonic probe from

• , executing the EPRI modeled scan pattern. Itis on this basis that recipients of this letter must evaluate the

• condition pursuant to 10 CFR Part 21.21 to determine ifitcould represent a substantial safety hazard Ii* reportable under 10 CFR Part 21.

(ix) Inthe case of an earlysite permits the en titles to whom an early site permit was transferred.

, This isnot an early site permit concern.

Part 21 - Final Report Nolification:

Wesltnghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic Inspections Page 6 Attachment 3 Westinghouse Pressurizer Head Nozzle Inner Corner Region Ultrasonic

i Inspections -Supporting Figures i

Figure i below contains a sketch of a typical Westinghouse pressurizer upper head indicating that the outside surface isoffset from the center of the inside surface and the center of each safety-relief and spray nozzle. The ASME Section XI Class 1examination volume isalso identified inthis figure.

OhangeIn Tolclcras Due tQ,w:)s.l Nnz~le xi 0dmIgI Deaf Volum.

Prnaerbor SproyNofle Ceter Pont (s)io ~clauu I ElmniVolume lIed (Shell) Outsde '*

S Radius RL'diuo Flgu~e 1.Westinghouse ePressurizer Upper Head Sketch with Offsets 1.

Part 21 - FinaiRepori Notification:

Westinghouse Pressurizer Head Nozzle Inner Corner Region U[trasonic Inspections Page 6 Attachment 3 (cant.)

Figure 2 below contains a sketch of a typical Westinghouse pressurizer lower head indicating that the outside surface isoffset from the center of the inside surface and the center of the surge nozzle. The ASME Section XI Class 1 examination volume isalso identified inthis figure.

tentHeedProeurizr Su Oenlcr PcInt (or; ASEX Cu -ExmVl Wad (Sh.O)hntd* Aqous

- V~¶w PeW(s)Ion Head ~Stc5~OrAsd. Rq#ey I,)

Figure 2. Westinghouse Pressurizer Lower Head Sketch with Offsets I.

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Part 21 Final Report Nofificaflon:

Westinghouse Pressurizer Head Nozzle Inner Corner Region Uilrasoniic Inspections i" Page 7 I, L (cont.)

Flgure 3 below contains a sketch of a typical Westinghouse steam generator channel head (excluding the manway) indicating that the outside surface isoffset from the center of the inside surface and the center of the primary nozzles. The ASME Section XI Class 1examination volume is also identified inthis figure.

Note Ohortge In TI~iCtkrces Due to Offset

'cm Genero*tor Prtnitiy Waflle XI Cbs. 1 Exam Volume

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I 7

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7 7

A 7

7, ii, 9/

Center Point for Channel H-eadOutsie~lIbdius

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C.enterPaont for Channel Head Inside Rodlus Figure 3.Westinghouse Steam Generator Channel Head Primary Nozzle Sketch with Offset

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