ML021650180

RAI, Exigent Steam Generator Technical Specification

ML021650180
Person / Time
Site:	San Onofre
Issue date:	06/10/2002
From:	Wang A NRC/NRR/DLPM
To:	Ray H Southern California Edison Co
References
TAC MB5145, TAC MB5146
Download: ML021650180 (4)

Text

June 10, 2002 Mr. Harold B. Ray Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR EXIGENT STEAM GENERATOR TECHNICAL SPECIFICATION CHANGE (TAC NOs. MB5145 AND MB5146 )

Dear Mr. Ray:

By letter dated May 22, 2002, Southern California Edison (SCE/licensee) submitted a request for an exigent technical specification (TS) change regarding the TS 5.5.2.11.f.1.h, Steam Generator Tube Surveillance Inspection Program, for the San Onofre Generating Stations, Units 2 and 3. The NRC has concluded that additional information is needed to complete the review. Enclosed is a request for additional information regarding your May 22, 2002, submittal. Please respond by June 11, 2002. This request has been discussed with Jack Rainsberry of your staff and he has agreed to this schedule. If you have any questions regarding this request, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362

Enclosure:

As stated cc: See next page

June 10, 2002 Mr. Harold B. Ray Executive Vice President Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR EXIGENT STEAM GENERATOR TECHNICAL SPECIFICATION CHANGE (TAC NOs. MB5145 AND MB5146 )

Dear Mr. Ray:

By letter dated May 22, 2002, Southern California Edison (SCE/licensee) submitted a request for an exigent technical specification (TS) change regarding the TS 5.5.2.11.f.1.h, Steam Generator Tube Surveillance Inspection Program, for the San Onofre Generating Stations, Units 2 and 3. The NRC has concluded that additional information is needed to complete the review. Enclosed is a request for additional information regarding your May 22, 2002, submittal. Please respond by June 11, 2002. This request has been discussed with Jack Rainsberry of your staff and he has agreed to this schedule. If you have any questions regarding this request, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362 DISTRIBUTION:

PUBLIC RidsOgcRp

Enclosure:

As stated PDIV-2 r/f RidsAcrsAcnwMailCenter RidsNrrPMAWang RidsRegion4MailCenter (CJohnson, cc: See next page RidsNrrLAMMcAllister LHurley, DBujol)

SDembek ACCESSION NO.: ML021650180 OFFICE PDIV-2/PM PDIV-1/LA PDIV-2/SC NAME AWang:sp MMcAllister JHickman for:

SDembek DATE 6/10/02 6/10/02 6/10/02 OFFICIAL RECORD COPY

Request for Additional Information San Onofre Generating Stations, Units 2 and 3 Steam Generator Tube Inspection Program Proposed Technical Specification Change In order to complete the review of the proposed amendment, additional information is needed to clarify certain points in the WCAP-15894-P report.

1. Please provide a brief description of the steam generator including model, number of tubes per steam generator, thickness of the tubesheet, tube outside diameter and wall thickness, tube material (e.g., mill annealed alloy 600), number of tube supports, design (e.g., lattice grid ) of tube supports, tube support material, and tube support thickness.

2. Clarify definitions of "joint length" and "tube engagement area length. Specifically address whether these measurements are from the top of the tubesheet or from the bottom of the expansion transition. If from the top of the tubesheet, provide a table depicting the distance from the top of the tubesheet to the bottom of the transition for each of the specimens.

3. The inspection distance is specified from the top of the tubesheet. Are all tubes expanded such that the bottom of the expansion transition is located at the top of the tubesheet? If not, provide a histogram summarizing the distance from the top of the tubesheet to the bottom of the expansion transition.

4. A value of 4410 psid was used to correspond to the 3 times the normal operating differential pressure acceptance criterion. What was the secondary side pressure used in determining this value.

5. Please provide a summary of all of the conservatisms in your analysis (if different than that on page 13 of WCAP-15894-P, Revision 1).

6. Please provide a description of the results of your inspections in the tubesheet region.

Please clarify that all tubes with indications in the tubesheet were repaired (specifically address how axial indications detected by the bobbin in the lower part of the tubesheet were dispositioned). Please describe the size of the largest circumferential indication found in this outage and in prior outages. Please provide the number of circumferential indications found.

7. With respect to tubesheet bow (and tubesheet hole dilation), what is the limiting "region" of the steam generator? Is it in the interior of the tube bundle or in the periphery?

Please clarify if the allowance for tubesheet bow is for the worst "position" in the steam generator.

8. Compare the Westingouse and CE explosive expansion methods in terms of the resultant contact pressures (i.e., ability of the tube to resist pullout from the tubesheet).

Does the CE method provide comparable contact pressures?

9. Describe the extent to which denting has occurred at San Onofre 2. If denting has occurred, discuss whether it would prevent/limit the potential for tube pullout. Describe whether any prior tube pulls provided any insights on the extent to which denting may limit the potential for tube pullout.

San Onofre Nuclear Generating Station, Units 2 and 3 cc: Mr. Steve Hsu Radiologic Health Branch Mr. R. W. Krieger, Vice President State Department of Health Services Southern California Edison Company Post Office Box 942732 San Onofre Nuclear Generating Station Sacramento, CA 94327-7320 P. O. Box 128 San Clemente, CA 92674-0128 Mr. Ed Bailey, Radiation Program Director Radiologic Health Branch Mr. Douglas K. Porter State Department of Health Services Southern California Edison Company Post Office Box 942732 (MS 178) 2244 Walnut Grove Avenue Sacramento, CA 94327-7320 Rosemead, CA 91770 Resident Inspector/San Onofre NPS Mr. David Spath, Chief c/o U.S. Nuclear Regulatory Commission Division of Drinking Water and Post Office Box 4329 Environmental Management San Clemente, CA 92674 P. O. Box 942732 Sacramento, CA 94234-7320 Mayor City of San Clemente Chairman, Board of Supervisors 100 Avenida Presidio County of San Diego San Clemente, CA 92672 1600 Pacific Highway, Room 335 San Diego, CA 92101 Mr. Dwight E. Nunn, Vice President Southern California Edison Company Eileen M. Teichert, Esq. San Onofre Nuclear Generating Station Supervising Deputy City Attorney P.O. Box 128 City of Riverside San Clemente, CA 92674-0128 3900 Main Street Riverside, CA 92522 Mr. Robert A. Laurie, Commissioner California Energy Commission Mr. Gary L. Nolff 1516 Ninth Street (MS 31)

Power Projects/Contracts Manager Sacramento, CA 95814 Riverside Public Utilities 2911 Adams Street Riverside, CA 92504 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Mr. Michael Olson San Onofre Liaison San Diego Gas & Electric Company P.O. Box 1831 San Diego, CA 92112-4150 December 17, 2001