L-08-297, Response to Request for Additional Information - 2007 Steam Generator Tube Inspections

Response to Request for Additional Information - 2007 Steam Generator Tube Inspections

ML082900489
Person / Time
Site:	Beaver Valley
Issue date:	10/10/2008
From:	Sena P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-08-297, TAC MD8392
Download: ML082900489 (6)

Text

FENOC NP.O.

Beaver Valley Power Station Box 4 FirstEnergyNuclear Operating Company Shippingport, PA 15077 Peter P. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 October 10, 2008 L-08-297 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Response to Request for Additional Information - 2007 Steam Generator Tube Inspections (TAC No. MD8392)

By letter dated March 18, 2008, FirstEnergy Nuclear Operating Company (FENOC) submitted information summarizing the results of the 2007 steam generator tube inspections at Beaver Valley Power Station (BVPS) Unit No. 1. By letter dated September 11, 2008, the NRC staff requested additional information in order to complete its review of the March 18, 2008 steam generator tube inspection report. The FENOC responses to this request are attached.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at 330-761-6071.

Sincerely, Peter P. Sena III

Attachment:

Response to Request for Additional Information, 2007 Steam Generator Tube Inspections, Beaver Valley Power Station, Unit No. 1 cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative

Attachment L-08-297 Response to Request for Additional Information 2007 Steam Generator Tube Inspections Beaver Valley Power Station, Unit No. 1 Page 1 of 5 By letter dated March 18, 2008, the FirstEnergy Nuclear Operating Company (FENOC) submitted information summarizing the results of the 2007 steam generator (SG) tube inspections during the eighteenth refueling outage (1R1 8) at Beaver Valley Power Station, Unit No. 1 (BVPS-1). To complete their review, the NRC staff has requested additional information regarding the license amendment application for the measurement uncertainty recapture power uprate. The staff request is provided below in bold type followed by the FENOC response for BVPS-I.

1. Please provide the following design information on the BVPS-1 SGs:

a. Whether the u-bends were stress relieved after bending Rows 1 through 8 were stress relieved following the bending process. No other rows were stress relieved after bending.

b. The smallest u-bend radius (typically row 1)

Row 1 is the smallest U-bend with a radius of 3.14".

c. A tubesheet map A tubesheet map is provided in Figure 1.

d. The SG tube support plate naming convention used The SG tube support plate naming convention is illustrated in Figure 2.

e. The tubing manufacturer The tubing manufacturer is Sandvik, located in Sandviken, Sweden.

f. Whether the SGs have a flow distribution baffle plate, and if so, a description of the plate The Model 54F design includes a flow distribution baffle (Labeled "FBH" and "FBC" on Figure 2) located between the top of tubesheet and first tube support plate. The flow distribution baffle (FDB) is designed to minimize the number of tubes exposed to low velocity flow in the vicinity of the tubeplate. The flow distribution baffle, fabricated from ASME SA-240, Type 405 stainless steel, has octafoil shaped broached tube holes. The effective annular flow area between

Attachment L-08-297 Page 2 of 5 the tube outside diameter and the effective hole inside diameter is less in the case of the flow distribution baffle than for the tube support plates. Also, the center portion of the flow distribution baffle is cut out as indicated in Figure 3.

This flow distribution baffle design controls the cross-flow velocity so that the low velocity region (and sludge deposition zone) is located at the center of the tube bundle, near the blowdown intake.

2. Please provide the cumulative effective full power months of operation that the SGs had accumulated at the first inservice inspection.

At the end of Cycle 18, which was the first in-service inspection of the steam generators after replacement, the steam generators had accumulated 16.85 effective full power months of operation.

3. Please clarify whether any secondary side inspections (other than the secondary side visual inspection of the top of the tubesheet and in-bundle inspections of possible loose part locations) were performed. Please discuss the results of any secondary side inspections, including the visual inspection of the top of the tubesheet and the in-bundle inspections of possible loose part locations.

The secondary side visual inspection program performed during the BVPS-1 2007 outage included the top of the tubesheet, annulus and in-bundle areas looking at possible loose part (PLP) locations. The PLP reported locations were a result of the primary side eddy current examinations. Accessible portions of the flow distribution baffle (no tube lane) were also visually examined. No other secondary side inspections were performed.

No significant abnormalities were noted during the secondary side inspections.

Small pieces of gasket material and weld splatter were retrieved while one sludge rock in SG 1B broke apart during retrieval attempts and was not removed. No foreign material was observed in the accessible portions of the flow distribution baffle.

Attachment L-08-297 Page 3 of 5 1 54P TENIPLATE,

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Attachment L-08-297 Page 4 of 5 n r----n I TEH TSH -- Tube End Hot Tubesheet Hot FBH - Flow Baffle Hot 01 H - 1st Tube Support Plate Hot 07H - 7th Tube Support 07H 07C Plate Hot AV1 - 1st Anti-Vibration Bar 06H 06C AV6 - 6th Anti-Vibration Bar 07C - 7th Tube Support 05H o5c Plate Cold 01C - 1st Tube Support 04H 04C Plate Cold FBC - Flow Baffle Cold 03H 03C TSC - Tubesheet Cold TEC - Tube End Cold 02H 02C OIH oIc FBH FBC H I- TSC~

TIEH Figure 2 - BVPS-1 Steam Generator Support Plate Naming Convention

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