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Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Wolf Creek Nuclear Operating Corporation, Concerning Draft Requests for Additional Information Pertaining to the Wolf Creek, Unit 1, LRA
	ML071240286
Person / Time
Site:	Wolf Creek
Issue date:	05/20/2007
From:	Veronica Rodriguez; NRC/NRR/ADRO/DLR/RLRB
To:	; Wolf Creek
	rodriguez v m, ADRO/DLR/RLRB, 415-3703
References
	Download: ML071240286 (8)
	v • d • e

May 20, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 2, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on May 2, 2007, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs 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/

Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482

Enclosures:

1. List of Participants

2. List of Draft Requests for Additional Information cc w/encls: See next page

ML071240286 OFFICE PM:RLRB:DLR LA:DLR BC:RLRB:DLR NAME VRodríguez YEdmonds RAuluck DATE 05/16/07 05/16/07 05/20/07 TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 2, 2007 PARTICIPANTS AFFILIATIONS Verónica M. Rodríguez U.S. Nuclear Regulatory Commission (NRC)

Samuel Miranda NRC Lorrie Bell Wolf Creek Nuclear Operating Corporation (WCNOC)

Bill Selbe WCNOC Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS)

Paul Crawley STARS Richard Geiger STARS Gordon Chen STARS Enclosure 1

DRAFT REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION MAY 2, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 2, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA).

Reactor Vessel and Internals D-RAI 2.3.1.1-1 LRA Table 2.3.1-1 indicates that the reactor vessel head vent pipe is within the scope of license renewal and that it has a pressure boundary intended function. The staff requests that the applicant clarify which portions of the reactor head vent system, shown in Updated Safety Analysis Report (USAR) Figure 18.2-1, are within the scope of license renewal. The staff requests that the applicant identify which license renewal criteria these components meet and their intended functions.

Discussion: The applicant indicated that the question is clear. The applicant clarified that although not specifically indicated in LRA Section 2.3.1.1, both, D-RAIs 2.3.1.1-1 and 2.3.1.1-2, reference the same license renewal drawing LR-WCGS-BB-M-12BB04. Based on the discussion with the applicant, the staff agreed to combine these D-RAIs and revise this question as follows. The revised question will be sent as a formal RAI.

USAR Figures 18.2-1 and 18.2-13 shows the reactor head vent system and the reactor vessel level instrumentation system, respectively. The staff requests that the applicant indicate which portions of the reactor head vent system are within the scope of license renewal. In addition, the applicant should clarify if the spare head penetration of the level instrumentation system is within the scope of license renewal. The staff requests that the applicant identify which license renewal criteria these components meet and their intended functions.

D-RAI 2.3.1.1-2 USAR Figure 18.2-13 shows the reactor vessel level instrumentation system. The staff requests that the applicant clarify if the spare head penetration of this system is within the scope of license renewal. If the penetration is not within the scope of license renewal, the staff requests that the applicant justify its response.

Discussion: This question has been combined with D-RAI 2.3.1.1-1. Therefore, this question is withdrawn and will not be sent as a formal RAI.

Enclosure 2

Reactor Makeup Water System D-RAI 2.3.2.6-1 LRA Section 2.3.2.6-1 states that the reactor makeup water system provides containment isolation for penetration P-25. The staff requests that the applicant specifically identify the components (and their functions) affected by the containment isolation. In addition, the staff requests that the applicant clarify if these components are within the scope of license renewal.