IR 05000341/2010011

IR 05000341-10-011 (DRS) on 07/21/2010 08/06/2010 for Fermi Power Plant, Unit 2, Refueling and Other Outage Activities Inspection

ML102390072
Person / Time
Site:	Fermi
Issue date:	08/26/2010
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Jennifer Davis Detroit Edison
References
IR-10-011
Download: ML102390072 (12)

Text

gust 26, 2010

SUBJECT:

FERMI POWER PLANT, UNIT 2 NRC INSPECTION REPORT 05000341/2010-011(DRS)

Dear Mr. Davis:

On August 6, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Fermi Power Plant, Unit 2. The enclosed inspection report documents the inspection results, which were discussed on August 6, 2010, with you and other members of your staff.

This inspection report documents a review of the control of heavy loads specific to the reactor building crane, reactor building crane support structure and reactor building superstructure conducted in conjunction with Operating Experience Smart Sample (OpESS)

FY2007-03, Crane And Heavy Lift Inspection, Supplemental Guidance for Inspection Procedure (IP) 71111.20, Revision 2.

Based on the results of this inspection, no findings were identified.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No.: 50-341 License No.: NPF-43

Enclosure:

Inspection Report 05000341/2010-011(DRS)

w/Attachment: Supplemental Information

REGION III==

Docket No: 50-341 License No: NPF-43 Report No: 05000341/2010-011(DRS)

Licensee: Detroit Edison Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Dates: July 21 through August 6, 2010 Inspectors: J. Bozga, Reactor Inspector Approved by: David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000341/2010011(DRS); 07/21/2010 - 08/06/2010; Fermi Power Plant, Unit 2; Refueling and Other Outage Activities Inspection.

This report covers portions of the Refueling and Other Outage Activities Inspection Procedure.

The inspection was conducted by Region III inspectors. Based on the results of this inspection, no NRC-identified findings were discovered that involved violations of NRC requirements. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

NRC-Identified

and Self-Revealed Findings

Cornerstone: Initiating Events

No violations of significance were identified.

Licensee-Identified Violations

No violations of significance were identified.

REPORT DETAILS

1R20 Outage Activities

.1 Refueling Outage Activities

a. Inspection Scope

From January 13, 2010 through June 1, 2010, the inspectors inspected the Independent Spent Fuel Storage Installation (ISFSI) Control of Heavy loads portion of Inspection Procedure 60854.1 Preoperational and Operational Testing of an Independent Spent Fuel Storage Installation. During this inspection the inspectors identified design calculation issues associated with the reactor building crane, reactor building crane support structure, and the reactor building super-structure. The ISFSI inspection remains ongoing. However, because the reactor building crane, reactor building crane support structure, and reactor building super-structure are used to lift not only ISFSI related loads but other heavy loads as well, Region III staff opted in the interim to expedite review of these issues via a separate inspection.

Hence, from July 21, 2010 through August 6, 2010, the inspector reviewed the licensees control of heavy loads program in conjunction with a portion of the NRCs Operating Experience Smart Sample (OpESS) FY2007-03, Crane and Heavy Lift Inspection, Supplemental Guidance for IP-71111.20, Revision 2 specifically related to the removal and installation of the Reactor Pressure Vessel (RPV) head during refueling outages as well as design calculations associated with the reactor building crane, reactor building crane support structure and the reactor building super-structure. Documents reviewed during the inspection are listed in the Attachment of this report.

b. Findings

(1) Reactor Building Crane and Reactor Building Crane Support Structure/Superstructure Design Calculation Issues

Introduction:

The inspectors determined that an unresolved item (URI) existed concerning the design calculations that demonstrate the design adequacy of the reactor building crane, reactor building crane support structure and reactor building superstructure.

Description:

The inspectors reviewed Calculation No. CN-23934, Reactor Building Crane for Enrico Fermi Atomic Power Plant No. 2 Bridge and Trolley Structural Calculations, dated March 8, 1973, Calculation No. 4.02.09, Reactor Building Superstructure Steel Girt and Column Framing Design, Volume I, Revision A, Calculation No. DC-6019, Assessment of the Interior Columns for the Reactor Building Steel Superstructure Including Crane Lifted Load, Volume IA, Revision 0, and Calculation No. 4.02.04, Superstructure Roof Framing Bracing System, Volume I, Revision A.

The inspectors were concerned that the reactor building crane and reactor building crane support structure/superstructure had been evaluated using acceptance criteria that were not contained within UFSAR Table 3.8-18, Loading Combinations for Steel Structures Elastic Design. Also, inspectors were concerned that the reactor building crane and reactor building crane support structure/superstructure had not been evaluated for the applied loads that were part of the design and licensing basis load cases/load combinations specified in UFSAR Table 3.8-18, Loading Combinations for Steel Structures Elastic Design.

In response to the inspectors concern, the licensee initiated corrective action program documents related to the reactor building crane and reactor building crane support structure/superstructure. The licensee entered these items into their corrective action program (CAP) as the following condition assessment and resolution documents (CARD):

2. CARD 10-22723; NRC ISFSI Issue Need to Revise Calculation CN-23934; dated

March 29, 2010

4. CARD 10-22979; NRC ISFSI Issue-Inspectors Questions About Calculations

DC-6019 and 4.02.04; dated April 7, 2010

5. CARD 10-22979; NRC ISFSI Issue-Inspectors Questions About Calculations

DC-6019 and 4.02.04; dated April 7, 2010

7. CARD 10-23797; NRC ISFSI Issue-Revise Calculation 4.02.04; dated

May 5, 2010

9. CARD 10-24045; NRC ISFSI Issue-Calculation DC-6019 Load Combinations;

dated May 14, 2010

10.

CARD 10-24166; NRC ISFSI Issue-CMTRs used in calculation 4.02.09; dated May 19, 2010

11.

CARD 10-26275; NRC ISFSI Issue-Clarification of Analysis in DC-6019; dated July 24, 2010

12.

CARD 10-26276; NRC ISFSI Issue; dated July 24, 2010

13.

CARD 10-26277; NRC ISFSI Issue-Licensing Basis for Allowable Axis Stresses in 4.02.04; dated July 24, 2010

14.

CARD 10-26278; NRC ISFSI Issue-Stresses is DC-6019 and 4.02.09; dated July 24, 2010

15.

CARD 10-26279; NRC ISFSI Issue-Extraction of Loads Used in 4.02.04; dated July 24, 2010

16.

CARD 10-26280; NRC ISFSI Issue-Acceptance Criteria in Calc. 4.02.09; dated July 24, 2010

17.

CARD 10-26282; NRC ISFSI Issue-Use of CMTRs in EDP-34473; dated July 24, 2010

18.

CARD 10-26415; NRC ISFSI Question on Design Basis for Response Spectra used in Design Calculation DC-6019; dated July 28, 2010

19.

CARD 10-26545; NRC Question- ISFSI-RB5 Structure Corner Column Buckling Calculation Compliance with AISC Code; dated July 30, 2010

20.

CARD 10-26548; NRC Questions-ISFSI-RB5 Structure Corner Column Peak Critical Yield Analysis Not Evaluated as Plastic According to AISC requirements; dated July 30, 2010

21.

CARD 10-26691; ISFSI NRC Issue - Crane Runway Girder Splice; dated August 4, 2010 This item is being held as an unresolved item (URI 05000341/2010011-01) pending evaluation of these concerns by the licensee and subsequent inspector review and discussion with the licensee. The licensee indicated that they would provide the inspectors multiple revised analyses addressing the issues relevant to the reactor building crane, reactor building crane support structure and reactor building superstructure on September 10,

4OA6 Management Meetings

.1 Exit Meeting Summary

The inspector presented the results of the inspection including discussing URI 05000341/2010011-01 and planned actions to resolve the related issues with Mr. M.

Caragher and other members of the licensees staff via telephone on August 6, 2010.

Licensee personnel acknowledged the inspection results presented. The inspector asked the licensee whether any materials examined during the inspection are considered proprietary.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

C. Walker, Nuclear Organizational Effectiveness Director

M. Caragher, Nuclear Engineering Director

K. Hullum-Lawson, Nuclear Engineering Supervisor

S. Hassoun, Nuclear Licensing Supervisor

R. Salmon, Nuclear Compliance Supervisor

R. Johnson, Nuclear Licensing Manager

B. Keck, Nuclear Engineering Manager

G. Abdallah, Lead Civil Engineer

E. Odar, Consultant

Nuclear Regulatory Commission

D. Hills, Chief, Division of Reactor Safety, Engineering Branch 1

M. Morris, Senior Resident Inspector

LIST OF ITEMS

Opened

Reactor Building Crane and Reactor Building Crane Support

05000341/2010011-01 URI Structure/Superstructure Design Calculation Issue Closed and

Discussed

None Attachment