WM 07-0050, Operating Corporation - Response to NRC Requests for Additional Information Related to License Renewal Application

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Operating Corporation - Response to NRC Requests for Additional Information Related to License Renewal Application
ML071580194
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/01/2007
From: Matthew Sunseri
Wolf Creek
To:
Document Control Desk, Office of New Reactors
References
WM 07-0050
Download: ML071580194 (9)


Text

W.LF CREEK JNUCLEAR OPERATING CORPORATION June 1, 2007 Matthew W. Sunser Vice President Oversight WM 07-0050 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

1) Letter ET 06-0038, dated September 27, 2006, from T. J. Garrett, WCNOC, to USNRC 2) Letter dated May 6, 2007, from V. Rodriguez, USNRC, to T. J. Garrett, WCNOC (ML071220180)

Subject:

Docket No. 50-482: Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application Gentlemen:

Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) License Renewal Application for the Wolf Creek Generating Station (WCGS). Reference 2 requested additional information regarding the License Renewal Application.

Attachment I provides the WCNOC response to each NRC request.Attachment II provides a summary of the commitment made in this response.If you have any questions concerning this matter, please contact me at (620) 364-4008, or Mr.Kevin Moles at (620) 364-4126.Sincerely, Matthew W. Sunseri MWS/rlt P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET-A!I2- /

WM 07-0050 Page 2 of 3 Attachment I: Response to NRC Request for Additional Information Attachment I1: List of Commitments cc: J. N. Donohew (NRC), w/a V. G. Gaddy (NRC), w/a B. S. Mallett (NRC), w/a V. Rodriguez (NRC), w/a Senior Resident Inspector (NRC), w/a WM 07-0050 Page 3 of 3 STATE OF KANSAS COUNTY OF COFFEY))Matthew W. Sunseri, of lawful age, being first duly sworn upon oath says that he is Vice President Oversight of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.Matthew W. Sunseri Vice President Oversight SUBSCRIBED and sworn to before me this I day ofJT110, 2007.Notary Public Expiration Date L D1* )

Attachment I to WM 07-0050 Page 1 of 5 Attachment I WCNOC Response to NRC Requests for Additional Information (ML071220180)

Dated May 6, 2007 RAI 2.3.1.1-1 RAI 2.3.2.6-1 RAI 2.3.2.10-1 RAI 2.3.3.7-1 RAI 2.3.3.7-2 RAI 2.3.3.7-3 Attachment I to WM 07-0050 Page 2 of 5 WCNOC Response to NRC Requests for Additional Information (ML071220180)

Dated May 6, 2007 Reactor Vessel and Internals RAI 2.3.1.1-1 Updated Safety Analysis Report (USAR) Figures 18.2-1 and 18.2-13 show 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.

RAI 2.3.1.1-1 Response The portions of the reactor head vent system that are within the scope of license renewal are shown in the boundary drawing LR-WCGS-BB-M-12BB04.

The boundary starts from the connection with the vessel head (zone E-4) up to the second isolation valves (zones F-2 and G-2). These components have the intended function of pressure boundary and are in scope for the criteria of 10CFR54.4(a)(1).

The reactor vessel level instrumentation system (RVLIS) used a spare vessel head penetration for the upper level tap. The vessel head still has several blind flanged spare penetrations, all of which have the intended function of pressure boundary and are in scope for the criteria of 1OCFR54.4(a)(1).

The portions of the RVLIS that are within the scope of license renewal are also shown on boundary drawing LR-WCGS-BB-M-12BB04 (zone E-4 to F-5). The head penetration of the level instrumentation system and the spares are addressed in the License Renewal Application (LRA) Table 2.3.1-1 as component type of reactor vessel (RV)Penetrations.

Reactor Makeup Water System 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.RAI 2.3.2.6-1 Response The components that are affected by the containment isolation associated with penetration P-25 are the line segment and the associated drain between the isolation valves that are shown as green on the boundary drawing LR-WCGS-BL-M-12BL01.

Components affected by containment isolation have a pressure Attachment I to WM 07-0050 Page 3 of 5 WCNOC Response to NRC Requests for Additional Information (ML071220180)

Dated May 6, 2007 boundary intended function and are in the scope of license renewal based on the criteria of 10CFR54.4(a)(1).

Other portions of the reactor water makeup system are in scope of license renewal for structural integrity and spatial interaction based on criterion of 10CFR54.4(a)(2) and are shown as red in the boundary drawing LR-WCGS-BL-M-12BLO1.

High Pressure Coolant Injection System RAI 2.3.2.10-1 License renewal drawing LR-WCGS-EM-M-12EM01 shows the refueling water storage tank within the scope of license renewal. However, the piping and components EBNO1A, EBNO1B and EBNO1C, which are entirely enclosed by this tank, are not. The staff requests that the applicant justify why these components are not within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

RAI 2.3.2.10-1 Response USAR 6.3.2.2 states that the heat exchangers (steam heating coils EBN01A, EBN01B, and EBN01C) are wrapped around the exterior shell of the tank. The steam heating coils are under the insulation that is also wrapped around the outside of the tank. The steam heating coils are not enclosed internally in the tank.The non-safety related steam heating coils that are attached to the exterior shell of the tank may have spatial interactions with the safety related tank and it's associated instrumentation in an event of heating coil leak. Thus the steam heating coils will be added to the scope of license renewal based on the criterion of 10CFR54.4(a)(2).

On license renewal drawing LR-WCGS-EM-M-12BNO1 the steam heating coils EBN01A, EBN01B, and EBN01C and the associated piping will be included in scope. LRA Table 2.3.2-10 will be amended to add steam heating coils under the component type of "Heat Exchanger Tube Side" with an Intended Function of Leakage Boundary.

LRA Table 3.2.2-10 will be amended to add lines of aging evaluation for the component type of "heat exchanger tube side".Chemical and Volume Control System RAI 2.3.3.7-1 License renewal drawing LR-WCGS-BG-M-12BG03 shows the volume control tank (TBG05) within the scope of license renewal. The staff requests that the applicant explain why the piping and spray nozzles are not included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

Attachment I to WM 07-0050 Page 4 of 5 WCNOC Response to NRC Requests for Additional Information (ML071220180)

Dated May 6, 2007 RAI 2.3.3.7-1 Response The Volume Control Tank (VCT) has an intended function of pressure boundary.The VCT spray nozzle assembly (nozzle and pipe stub) does not have an intended function (reference USAR Section 9.3.4). Failure of the nozzle assemblies does not support the structural integrity of the VCT nor does their failure affect the intended function of the VCT. The VCT spray nozzle assemblies do not have an intended function for any of the license renewal regulated events. The VCT nozzle assemblies are not within the scope of license renewal based on the criteria of I OCFR54.4(a)(1), (a)(2) or (a)(3).Failure of the spray nozzle assemblies would result in abnormal control room indications/alarms and operator action would be taken to correct the condition.

RAI 2.3.3.7-2 LRA Table 2.3.3-7 does not list component type of pumps and tanks supports.

The staff requests that the applicant clarify if the pumps and tanks supports are within the scope of license renewal. If the supports are not within the scope of license renewal the staff requests that the applicant justify its response; if they are, the applicant should indicate where these components are discussed.

RAI 2.3.3.7-2 Response Chemical and Volume Control System supports within the scope of license renewal are addressed as structural commodities in LRA Section 2.4.22. Pump and Tank supports for the Chemical and Volume Control System are shown in LRA Table 2.4-22 as "Supports, Mechanical Equipment Class 2 and 3" or"Supports, Mechanical Equipment Non-ASME" depending upon the classification of the component.

RAI 2.3.3.7-3 License renewal drawing LR-WCGS-BG-M-12BG04 shows the spent resin storage tanks outside the scope of license renewal; however, all their connecting lines were included within the scope. The staff requests that the applicant explain and justify this inconsistency.

RAI 2.3.3.7-3 Response The portion of the Chemical and Volume Control System shown on boundary drawing LR-WCGS-BG-M-12BG04 is the boron thermal regeneration system. The"spent resin storage tanks" referenced in the RAI are the thermal regeneration demineralizers FBG02A, FBG02B, FBG02C, FBG02D, and FBG02E. The piping shown is in the scope of license renewal for spatial interaction in the auxiliary Attachment I to WM 07-0050 Page 5 of 5 WCNOC Response to NRC Requests for Additional Information (ML071220180)

Dated May 6, 2007 building.

Each thermal regeneration demineralizer tank is located in a concrete compartment.

There are no safety-related components in the tank compartments.

Therefore the demineralizer tanks are not in the scope of license renewal based upon the criterion of 10 CFR 54.4(a)(2).

Attachment II to WM 07-0050 Page 1 of 1 LIST OF COMMITMENTS The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation in this document.

Any other statements in this letter are provided for information purposes and are not considered regulatory commitments.

Please direct questions regarding these commitments to Mr. Kevin Moles, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4126.REGULATORY COMMITMENT DUE DATE License Renewal Application changes discussed in this 08/31/2007 document will be submitted in an amendment to the application.