ML20134A876

Notification of 970130 Meeting W/Util in Rockville,Md to Discuss SG Insp Results.W/Agenda

ML20134A876
Person / Time
Site:	San Onofre
Issue date:	01/24/1997
From:	Fields M NRC (Affiliation Not Assigned)
To:	Bateman W NRC (Affiliation Not Assigned)
References
NUDOCS 9701290144
Download: ML20134A876 (6)

Text

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". January 24, 1997

'f MEMORANDUM TO: William H. Bateman, Director-

. Project Directorate IV-2 Division of Reactor Projects III/IV ORIGINAL SIGNED BY FROM: Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV

SUBJECT:

FORTHCOMING MEETING WITH SOUTHERN CALIFORNIA EDIS0N TO DISCUSS STEAM GENERATOR INSPECTION RESULTS DATE & TIME: Thursday January 30, 1997 1:00 pm - 4:00 pm

. LOCATION: U.S. NRC One White Flint North 11555 Rockville Pike Rockville, MD 20852 Room 0-13B9 PURPOSE: To provide the NRC with an update on the steam generator inspection results for the San Onofre Nuclear Generating Station, Unit 2. A meeting agenda is attached.

PARTICIPANTS *: fiBq Southern California Edison Jack Strosnider Mike Short, et. al.

Ted Sullivan Phillip Rush Mel Fields Docket Nos. 50-361 and 50-362

Attachment:

Agenda i l

cc w/att: See next page '

, CONTACT: M. Fields 415-3062

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff I Meetings Open to the Public" 59 Federal Reaister 48340, 9/20/94.

DOCUMENT NAME: S013097.MTG l 1

0FC PDIV-2/PM MFJ/f$:ye PDIV-2/LA Q NAME EP N n  ;

,DATE- 1/lM/97 194/97 0FFICIAL RECORD _ COPY l 1

9701290144 970124 DR ADOCK 0500 1 NBC FRE CDRER COPY

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E NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20eeNm01

\*****/ January 24, 1997 MEMORANDUM 10: William H. Bateman, Director Project Directorate IV-2 Division of R act jects ./IV FROM: Mel r an' gen ProjectDireeforateIV Division of Reactor Projects III/IV l

SUBJECT:

FORTHCOMING MEETING WITH SOUTHERN CALIFORNIA EDIS0N TO DISCUSS STEAM GENERATOR INSPECTION RESULTS DATE & TIME: Thursday January 30, 1997 .

1:00 pm - 4:00 pm  !

LOCATION: U.S. NRC l One White Flint North 11555 Rockville Pike Rockville, MD 20852 Room 0-1389 PURPOSE: To provide the NRC with an update on the steam generator ir.spection results for the San Onofre Nuclear Generating

'tation,

, Unit 2. A meeting agenda is attached.

PARTICIPANTS *: EG Southern California Edison Jack Strosnider Mike Short, et. al.

Ted Sullivan Phillip Rush Mel Fields Docket Nos. 50-361 and 50-362

Attachment:

Agenda cc w/att: See next page CONTACT: M. Fields 415-3062

• Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meetings Open to the Public" 59 Federal Reaister 48340, 9/20/94.

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Mr. R. W. Krieger, Vice President Resident Inspector / San Onofre NPS ,

Southern California Edison Company c/o U.S. Nuclear Regulatory Commission l

San Onofre Nuclear Generating Station Post Office Box 4329 P. O. Box 128 San Clemente, California 92674

San Clemente, California 92674-0128 5

Mayor

Chairman, Board of Supervisors City of San Clemente  !

County of San Diego 100 Avenida Presidio 1600 Pacific Highway, Room 335 San Clemente, California 92672 l l San Diego, California 92101 '

] Mr. Harold B. Ray 1

Alan R. Watts, Esq. Executive Vice President

, Rourke & Woodruff Southern California Edison Company

701 S. Parker St. No. 7000 San Onofre Nuclear Generating Station

. ' Orange, California 92668-4702 P.O. Box 128 San Clemente, California 92674-0128

! Mr. Sherwin Harris Resource Project Manager

Public Utilities Department

City of Riverside

! 3900 Main Street Riverside, California 92522 I Dr. Harvey Collins, Chief Division of Drinking Water and Environmental Management i California Department of Health Services P. O. Box 942732 Sacramento, California 94234-7320 l

i Regional Administrator, Region IV l U.S. Nuclear Regulatory Commission 3

Harris Tower & Pavilion j 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064

< Mr. Terry Winter i Manager, Power Operations San Diego Gas & Electric Company

P.O. Box 1831 San Diego, California 92112-4150 Mr. Steve Hsu Radiologic Health Branch 4'

State Department of Health Services Post Office Box 942732

Sacramento, California 94234 l

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Attachment b

NEETING NITH SOUTHERN CALIFORNIA EDIS0N-i TO DISCUSS STEAN GENERATOR INSPECTION RESULTS FOR SAN ON0FRE NUCLEAR GENERATING STATION UNIT 2 NEETING AGEWA

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i The following list of issues is included to facilitate the discussions of the

! steam generator tube inspection results for San Onofre Unit 2. The issues

! will be addressed to the extent possible during the meeting.  ;

1. For each mode of degradation (e.g., TTS circumferential, axial freespan) i i discuss how the completed or planned inspection scope is sufficient to '

ensure that tubes with significant or potentially significant (at the

end of the next cycle) indications are identified and removed from

, service. Specifically address the extent to which the nondestructive

evaluation (NDE) techniques used for the detection of axial freespan and l eggcrate indications satisfy the guidance in Section C.I.2 of the draft i regulatory guide (RG) on steam generator tube integrity. The NRC staff  !

recognizes that the RG is not yet finalized; nevertheless, the ideas 1

incorporated into the draft RG reflect the most current and

comprehensive means of evaluating NDE techniques.

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2. Discuss how the most significant indications detected to date will be

assessed with respect to the margins specified in Regulatory Guide

! 1.121. Explain how these indications bound the other detected i

! indications for each mode of degradation.

3. Summarize the scope of the in-situ pressure testing and tube pulls planned for the current refueling outage. Specifically address how the tube pulls will be used to support a cycle length assessment of the axial freespan degradation. Provide the basis for assuming that the

pull candidates are representative (or bounding) of similar indications identified at other locations within the steam generators and that the l- scope of the tube pull program is sufficient to obtain a range of i degradation depths from below the detection limits of the inspection l technique to the bounding indications.

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4. Discuss the relative quality of the eddy current inspection data (i.e.,

noise / interfering signals) for the tube pull and in-situ pressure test e candidates to both the population of tubes identified with similar indications and to all the remaining of tubes in the bundle. Also compare the overall quality of the eddy current data obtained in the current refueling outage to previous outages and to other CE units that have identified similar modes of degradation. Only consider corrosion-g induced tube damage mechanisms.

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!* i I 5. The overall objective for addressing tube denting should be to understand the initiation and growth of cracking due to the influence of denting so that unacceptable crack lengths and depths will not be ,

present at any point during the next operating cycle. Discuss the efforts taken to date to address this issue. Also, explain the criteria for identifying dents in the current and prior operating cycles from the

bobbin coil probe data. Include in the presentation a discussion 2

describing the dented locations within the steam generators identified both in the current and in previous inspections.

! 6. Discuss the scope, possible methodologies, and schedule for completing a runtime assessment.

7. Please submit to the NRC, the raw eddy current inspection data from both the Plus Point and bobbin coil inspections for those tubes that have or will be in-situ pressure tested or pulled during the current refueling

outage. Also, include the data for at least two crack indications detected at dented locations. If in-situ test or tube pull candidates

, have not been finalized, provide the data for the most likely choices. ,

Along with the eddy current data, provide the drawings of the standards that were used to calibrate the inspection probes. The data should be compatible with Eddynet95.

! 8. Based on our understanding of the inspection results completed to date, '

the axial freespan indications do not appear to be located in areas of the tube bundle that might be identified from a thermal-hydraulic i analysis (i.e., ATHOS). This finding is not entirely consistent with i conclusions from other licensees that have indicated that the general

- areas affected by this mode of tube degradation may be identified

through analytical models. To the extent practical, discuss the models that are used to predict the location of susceptible regions for CE

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designed steam generators at all plants that have inspected for this i mode of degradation to date. Compare and contrast analysis results and inspection findings for similar steam generators. Provide evidence j supporting the conclusion that computational modeling can or cannot be j used to predict these areas. Discuss the following to support your

conclusion

(1) the inspection scope, (2) model results, and (3)

inspection findings (i.e., deposits and indications).

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