ML020520040

Overview of Reactor Pressure Head Penetration Examination Plans for Davis-Besse Nuclear Power Station

ML020520040
Person / Time
Site:	Davis Besse
Issue date:	02/14/2002
From:	Bergendahl H FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2761, FOIA/PA-2002-0229
Download: ML020520040 (11)

Text

FENOC FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Ohio 43449-9760 Howard W Bergendahl Vice President - Nuclear 419-321-8588 Fax-419-321-8337 Docket Number 50-346 Contains Proprietary and Confidential Information Pursuant to 10CFR2.790.

License Number NPF-3 Serial Number 2761 February 14, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Reactor Pressure Vessel Head Penetration Examination Plans for the Davis Besse Nuclear Power Station Ladies and Gentlemen:

The purpose of this letter is to document the examination plans for the Reactor Pressure Vessel (RPV) head penetrations to be conducted during the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS) 13 th Refueling Outage (13RFO) scheduled to begin on February 16, 2002. These examination plans were presented by the DBNPS staff to the NRC staff on January 23, 2002, in further response to NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles," and satisfied a commitment made in FirstEnergy Nuclear Operating Company (FENOC) letter Serial Number 2746, dated November 30, 2001. An overview of the discussion is provided in. provides a proprietary version of the detailed examination information as was discussed during the January 23, 2002, meeting. Attachment 3 provides the Framatome-ANP affidavit complying with the requirements of 10 CFR 2.790 citing the rationale for this information to be withheld from public disclosure.

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 2 of 2 If you have any questions, or require further information, please contact Mr. David H.

Lockwood, Manager - Regulatory Affairs, at (419) 321-8450.

Very truly yours A/

Enclosure and Attachments cc: J. E. Dyer, Regional Administrator, NRC Region III S. P. Sands, DB-1 NRC/NRR Project Manager C. S. Thomas, DB-1 Senior Resident Inspector Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Enclosure Page 1 of 1 SUPPLEMENTAL INFORMATION IN RESPONSE TO NRC BULLETIN 2001-01 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NUMBER 1 This letter is submitted pursuant to 10 CFR 50.54(f) and contains supplemental information concerning the response (Serial 2731, dated September 4, 2001) to NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles," for the Davis-Besse Nuclear Power Station, Unit Number 1.

I, Howard W. Bergendahl, state that (1) I am Vice President - Nuclear of the FirstEnergy Nuclear Operating Company, (2) I am duly authorized to execute and file this certification on behalf of the Toledo Edison Company and The Cleveland Electric Illuminating Company, and (3) the statements set forth herein are true and correct to the best of my knowledge, information and belief.

Howard W. Bergendahl, Vice President - Nuclear Affirmed and subscribed before me this fourteenth day of February, 2002.

N<ary Public, State of Ohio YvUNNE MI. H^PLL My oota~*

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 1 of 2 Overview of DBNPS Reactor Pressure Vessel Head Penetration Inspection Plans 13 th RFO The DBNPS 13th RFO is scheduled to begin on February 16, 2002. The Reactor Pressure Vessel (RPV) head removal to the RPV head inspection stand should be completed on February 21, 2002, and RPV head penetration nozzle examinations are scheduled to begin on February 22, 2002.

The RPV head will undergo a remote qualified visual examination of the Control Rod Drive Mechanism (CRDM) nozzles. The qualified visual examination will be video taped and will inspect the full 3600 around each nozzle. The results of the visual examination will determine what type of subsequent ultrasonic testing (UT) will be performed on the individual nozzles. This is illustrated in Figure 1 and is summarized below:

1. If the visual examination results indicate there is no leakage from the RPV head to CRDM nozzle annulus area and there is no CRDM flange leakage present around the affected CRDM nozzle, the nozzle will be subjected to a subsequent "bottom up" blade probe UT.

2. If the visual examination is obscured such that the full 3600 cannot be observed, but there is no indication of leakage from the RPV head to CRDM nozzle annulus area, and there is no CRDM flange leakage, the affected CRDM nozzle will be subjected to a subsequent "bottom up" blade probe UT.

3. If the visual examination indicates potential leakage from the RPV head to CRDM nozzle annulus area, or if a CRDM flange exhibits leakage requiring repair, the affected CRDM will be removed and the CRDM nozzle will be subjected to a "top down" rotating probe UT.

If any flaws are discovered during the subsequent UT, they will be resolved as indicated on Figure 2 and summarized below:

1. Flaws that are discovered below the J-weld and do not challenge the integrity of the reactor coolant system (RCS) pressure boundary will be evaluated using the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 95% confidence curve to determine if crack growth during the next cycle (Cycle

14) will challenge the integrity of the RCS pressure boundary or if crack growth during Cycle 14 may result in potential loose parts generation. If the evaluation reveals that crack growth is such that the RCS pressure boundary may be

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 2 of 2 challenged or that loose parts may be generated, the flaws will be repaired.

Otherwise, the flaws will be allowed to remain during Cycle 14.

2. Flaws discovered in the J-weld or in the pressure boundary area of the CRDM nozzle outer diameter that are circumferential or axial will be repaired.

3. Flaws discovered in the CRDM nozzle inner diameter that are circumferential will be repaired.

4. Flaws discovered in the CRDM nozzle inner diameter that are axial will be evaluated in accordance with ASME Section XI for acceptability. If the flaw is acceptable pursuant to the ASME Code, then further evaluation will be conducted to determine if the crack growth, using the EPRI MRP 95%

confidence curve, during Cycle 14 may challenge RCS pressure boundary integrity. If either the ASME Section XI evaluation determines the flaw to be unacceptable or the crack growth evaluation determines the RCS pressure boundary integrity may be challenged, the flaw will be repaired.

5. Any flaw that results in a verified leak path will be subjected to a dye penetrant test (PT) prior to any repairs being performed.

Because remote machining technology is not available, the flaws detected may not be destructively characterized nor will laboratory samples be obtained. This is consistent with ALARA principles, as stated in FENOC letter Serial Number 2747, in that manually characterizing the flaws and obtaining samples could result in an accumulated dose for this effort (based on the dose experienced in a similar effort at another utility) that is approximately 40% above the projected dose for the repair effort outlined above.

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 1 of 1 Framatome ANP Affidavit for January 23, 2002 Presentation Slides (Attachment 2)

(3 Pages Follow)

AFFIDAVIT COMMONWEALTH OF VIRGINIA

)

) ss.

CITY OF LYNCHBURG

1.

My name is James F. Mallay. I am Director, Regulatory Affairs, for Framatome ANP ("FRA-ANP"), and as such I am authorized to execute this Affidavit.

2.

I am familiar with the criteria applied by FRA-ANP to determine whether certain FRA-ANP information is proprietary. I am familiar with the policies established by FRA-ANP to ensure the proper application of these criteria.

3.

I am familiar with the information contained in a presentation made by Framatome ANP to the NRC on January 23, 2002 during a meeting between First Energy Nuclear Operating Company and the NRC concerning inspections at the Davis Besse plant.

This presentation material, a copy of which is being provided to the NRC by FENOC, is referred to herein as "Document." Information contained in this Document has been classified by FRA ANP as proprietary in accordance with the policies established by FRA-ANP for the control and protection of proprietary and confidential information.

4.

This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by FRA-ANP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5.

This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in the Document be withheld from public disclosure.

6.

The following criteria are customarily applied by FRA-ANP to determine whether information should be classified as proprietary:

(a)

The information reveals details of FRA-ANP's research and development plans and programs or their results.

(b)

Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c)

The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for FRA-ANP.

(d)

The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for FRA-ANP in product optimization or marketability.

(e)

The information is vital to a competitive advantage held by FRA-ANP, would be helpful to competitors to FRA-ANP, and would likely cause substantial harm to the competitive position of FRA-ANP.

7.

In accordance with FRA-ANP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside FRA-ANP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8.

FRA-ANP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9.

The foregoing statements are true and correct to the best of my knowledge, information, and belief.

SUBSCRIBED before me this day of 1 2002.

Ella F. Carr-Payne NOTARY PUBLIC, STATE OF VIRGINIA MY COMMISSION EXPIRES: 08/31/05

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions the DBNPS.

They are described only for information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8450) at the DBNPS of any questions regarding this document or associated regulatory commitments.

COMMITMENTS DUE DATE None

Docket Number 50-346 License Number NPF-3 Serial Number 2761 Page 1 of 1 Framatome ANP January 23, 2002 Presentation Slides UT Inspection Approach for Davis-Besse CRDM Nozzle Examinations THE FOLLOWING DOCUMENT CONTAINS PROPRIETARY INFORMATION (30 pages follow)