ML20205N882

From kanterella
Jump to navigation Jump to search
Forwards Questions Transmitted by Fax on 990415 to J Rainsberry of SCE & Request for Conference Call to Be Scheduled with Staff to Discuss SG Eddy Current Insp Results Obtained During Imminent Refueling Outage
ML20205N882
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/15/1999
From: Raghavan L
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9904190214
Download: ML20205N882 (2)


Text

I a ,-

pa %g y 4" UNITED STATES j NUCLEAR REGULATORY COMMISSION I If WASHINGTON, D.C. 20555-0001 l

A I

4...../

! April 15,1999 MEMORANDUM FOR: Docket File FROM: L. Raghavan, Senior Project Manager 4 [~

Project Directorate IV, Section 2 (/

Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND l 3 -- FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING PHONE CONVERSATION ON STEAM GENERATOR INSPECTION RESULTS l

l The attached questions were transmitted by fax today to Mr. Jack Rainsberry of Southern l

Californal Corporation (SCE) to request him to schedule a conference call with the staff and to discuss their steam generator eddy current inspection results obtained during their imminent ,

refueling outage. The call would be most beneficial when thev are about mid-way or three-fourths complete and have some results to chare with us. Attached is a list of typical discussion areas.

l l The licensee's participation in the call is on a voluntary basis. l This memorandum and the attachment do not convey a formal request for information or l represent an NRC staff position.

' i

/

Docket Numbers 50-361 50-362 l

Distribution p PUBLIC S. Dembeck

[ TUI SONGS r!f J. Sloan, SRI L. Smith, RIV S. Coffin 9904190214 990415 PDR ADOCK 05000361 O PCR

g -

6 #~

Steam Generator Tube inspection Results ,

l Licensees' steam Generator (SG) tube eddy current (EC) inspections play a vital role in the j management of SG tube degradation. The results are used to demonstrate adequate structural  !

and leakage integrity of the SG tubes.

NRC staff is interested in discussing the licensee'u steam generc*or inspection plans and results, althu.gh the licensee is not required to participate in this discussion. Typical areas of discussion include: .

l

{

e ;onmary to secondary leakage prior to shutdown e Results of secondary side hydro e For each steam generator, a general description of areas examined; includir.g expansion criteria and type of probe used in each area e For analyzed EC results, a description of bobbin indications (those not examined with RPC) and RPC/Plus Point /Cecco indications. Including the following information: location, number, degradatien mode, disposition, and voltages / depths / lengths of most significant indications e Description of repair / plugging plans i

  • Discussion of previous history; "look backs" performed; consideration of similar plants'

! experiences e Discussion of new inspection findings, including loose parts indications e Description of in-situ pressure test plans and results; include tube selection criteria, test pressure plans, test configuration e Describe tube pull plans and preliminary results; include tube selectie i criteria and evaluation plans e Assessment of tube integrity for previous operating cycle

  • Assessment of tube integrity for next operating cycle e Provide schedule for steam generator-related activities during remainder of current outage Note: It may facilitate the discussion if the licensee provides details on the topics listed above prior to the conference call (e.g., simple tables and figures).

i w -