ML101060640

Summary of Tele Conference Call Held on 4/9/10, Btw the USNRC and Arizona Public Service Company, Concerning Draft Requests for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1,2, and 3, License Renewa

ML101060640
Person / Time
Site:	Palo Verde
Issue date:	04/27/2010
From:	Susco J License Renewal Projects Branch 1
To:	Arizona Public Service Co
SUSCO, J NRR/DLR 415-2927
References
Download: ML101060640 (8)

Text

April 27, 2010 LICENSEE: Arizona Public Service Company FACILITY: Palo Verde Nuclear Generating Station, Units 1, 2, and 3

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on April 9, 2010, to discuss and clarify the staffs draft requests for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs draft RAIs. provides a listing of the participants, and Enclosure 2 contains a listing of the draft RAI questions discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA/

Jeremy J. Susco, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530

Enclosures:

As stated cc w/encls: See next page

ML101060640 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR PM:RPB1:DLR NAME IKing LRegner DWrona JSusco DATE 04/21/10 04/22/10 04/27/10 04/27/10 Memorandum to Arizona Public Service Company from J. Susco dated April 27, 2010

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 9, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION:

HARD COPY:

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TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 9, 2010 PARTICIPANTS AFFILIATIONS Jeremy Susco U.S. Nuclear Regulatory Commission (NRC)

Abdul Sheikh NRC Hans Ashar NRC Glenn Michael Arizona Public Service Company Eric Blocher Strategic Teaming and Resource Sharing Alliance Ahmed Ouaou Oak Ridge National Laboratory ENCLOSURE 1

DRAFT REQUESTS FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on April 9, 2010, to discuss and clarify the following draft requests for additional information (RAI) concerning the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, license renewal application (LRA).

DRAFT RAI 4.5-3

Background:

In LRA Section 4.5, the applicant provided Table 4.5-1, Tendon Regression Analysis Input Data.

The table contains lift-off forces of individual tendons used in the regression analysis. The review of the table identified the following anomalies:

a. Only the shop end force is provided for tendons H13-19, H21-04 (3rd year surveillance),

V07 and V015.

b. The lift-off force for tendon H21-04 was measured in the 3rd year surveillance and again in the 5th year.

c. The Unit 3 dome horizontal tendon lift-off average forces are greater than the wall horizontal lift-off average forces; in some cases by nearly 100 kips (i.e., H13-45, H32-42, and H21-43).

Issue:

The anomalies in items (a) and (c) could influence the slope of regression analysis conducted to demonstrate that the predicted prestress forces remain above their respective minimum required values (MRVs) through the period of extended operation. In particular, the staff is concerned with the influence of the higher Unit 3 dome horizontal tendon forces on the combined wall and dome trend line (Figure 4.5-3), which shows the least margin. Item (b) may not satisfy IWL-2521, which requires that tendons examined during an inspection shall be selected on a random basis from a sample of tendons that have not been examined in earlier examinations.

Request:

The applicant is requested to explain the anomalies and confirm they have no impact on its conclusion that regression analysis trend lines indicate that tendon prestress will remain above the MRV through the period of extended operation.

Discussion: The applicant indicated that additional data for tendon H13-19 was submitted in its April 1, 2010 response to RAI 4.5-1. The staff agreed that the data had been provided.

Therefore, the staff will remove H13-19 from the draft and send this as a formal RAI.

ENCLOSURE 2

Draft RAI B2.1.28-3

Background:

In response to RAI B2.1.28-2, dated February 19, 2010, the applicant stated that the frequency of inspection for the ASME Section XI, Subsection IWL AMP is consistent with ASME Section XI Subsection IWL, paragraph IWL-2421, Sites with Multiple Plants. This paragraph allows inspection intervals of every ten years staggered, so that at least one unit is inspected every five years. Therefore, the applicant concludes that the existing program is consistent with ASME Section XI Subsection IWL and the Generic Aging Lessons Learned Report, and no exception is required.

Issue:

ASME Section III, Subsection IWL, Subarticle IWL-2421 allows the inspection frequency to increase to ten years for examinations required by IWL-2524 and IWL-2525. However, IWL-2524 and IWL-2525 requirements are for examination of tendon anchorage areas and corrosion protection medium and free water in the post-tensioning system, respectively. The requirements for concrete surface examinations are described in IWL-2521.

Request:

Provide the basis for containment concrete surface visual examination inspection frequency of ten years.

Discussion: The staff explained to the applicant the nature of the request. The applicant explained that what was missing from the request was an appropriate reference to IWL-2410, which the staff referenced in its verbal explanation over the phone. The staff agreed to revise the request to read:

Request:

Provide the basis for containment concrete surface visual examination inspection frequency of ten years. IWL-2410(a) states, Concrete shall be examined in accordance with IWL-2510 at 1, 3, and 5 years following the completion of the containment Structural Integrity Test CC-6000 and every 5 years thereafter.

DRAFT RAI 3.5.2.3-4

Background:

For the component type supports ASME 2 and 3, LRA Table 3.5.2-14 credits the ASME Section XI Subsection IWF (B2.1.29) Program to manage loss of material for carbon and stainless steel components in 1) a raw water environment, and 2) a fuel oil environment.

The LRA states that these environments are not in NUREG-1801 for carbon and stainless steel components.

Issue:

The components in the environments identified above may have limited accessibility. It is not clear to the staff how the ASME Section XI Subsection IWF Program will inspect the component to ensure the aging effect is being managed.

Request:

Explain how the ASME Section XI Subsection IWF Program will manage the effect of aging on carbon and stainless steel components in 1) a raw water environment, and 2) a fuel oil environment.

Discussion: The applicant indicated that the question is clear. This question will be sent as a formal RAI.

Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc:

Mr. Steve Olea Mr. John C. Taylor, Director, Nuclear Arizona Corporation Commission Generation 1200 W. Washington Street El Paso Electric Company Phoenix, AZ 85007 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 Mr. Douglas Kent Porter, Senior Counsel Southern California Edison Company Mr. James Ray Law Department, Generation Resources Public Service Company of New Mexico P.O. Box 800 2401 Aztec NE, MS Z110 Rosemead, CA 91770 Albuquerque, NM 87107-4224 Senior Resident Inspector Mr. Geoffrey M. Cook U.S. Nuclear Regulatory Commission Southern California Edison Company P.O. Box 40 5000 Pacific Coast Highway, Bldg. D21 Buckeye, AZ 85326 San Clemente, CA 92672 Regional Administrator, Region IV Mr. Robert Henry U.S. Nuclear Regulatory Commission Salt River Project 612 E. Lamar Blvd., Suite 400 6504 E. Thomas Road Arlington, TX 76011-4125 Scottsdale, AZ 85251 Chairman Mr. Jeffrey T. Weikert Maricopa County Board of Supervisors Assistant General Counsel 301 W. Jefferson, 10th Floor El Paso Electric Company Phoenix, AZ 85003 Mail Location 167 123 W. Mills Mr. Aubrey V. Godwin, Director El Paso, TX 79901 Arizona Radiation Regulatory Agency 4814 S. 40th Street Mr. Eric Tharp Phoenix, AZ 85040 Los Angeles Department of Water & Power Southern California Public Power Authority Mr. Ron Barnes, Director P.O. Box 51111, Room 1255-C Regulatory Affairs Los Angeles, CA 90051-0100 Palo Verde Nuclear Generating Station Mail Station 7636 Mr. Brian Almon P.O. Box 52034 Public Utility Commission Phoenix, AZ 85072-2034 William B. Travis Building P.O. Box 13326 Mr. Dwight C. Mims, Vice President 1701 N. Congress Avenue Regulatory Affairs and Plant Improvement Austin, TX 78701-3326 Palo Verde Nuclear Generating Station Mail Station 7605 Mr. Randall K. Edington P.O. Box 52034 Executive Vice President Phoenix, AZ 85072-2034 Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034