ML050070159

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Supporting Materials for Review of BAW-1643(NP), Revision 4, Supplement 5, Supplement to the Master Integrated Reactor Vessel Surveillance Program
ML050070159
Person / Time
Site: Oconee, PROJ0693, Crane  Duke Energy icon.png
Issue date: 01/05/2005
From: Holm J
B & W Owners Group, Framatome ANP
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BAW-1543(NP), Rev 4, NRC:05:001, OG:05:1859
Download: ML050070159 (3)


Text

Duke Energy Company Entergy Operations, Inc.

Florida Power Corporation Oconee 1, 2, 3 ANO-1 Crystal River 3 AmerGen Energy Company, LLC The B&W FirstEnergy Nuclear Operating Company Owners Groupl Framatome ANP TMI-1 D-B Working Together to Economically Provide Reliable and Safe Electrical Power January 5, 2005 OG :05:1859 NRC:05:001 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Supporting Materials for Review of BAW-1643(NP), Revision 4, Supplement 5, "Supplement to the Master Integrated Reactor Vessel Surveillance Program" Ref.: 1. Letter, James F. Mallay (Framatome ANP), to Document Control Desk (NRC), Request for Review and Approval of BAW-1543(NP), Revision 4, Supplement 5, 'Supplement to the Master Integrated Reactor Vessel Surveillance Program'," OG:03:1838, NRC:03:091, December 19, 2003.

Ref.: 2. Letter, James F. Mallay (Framatome ANP) to Document Control Desk (NRC), "Response to RAI on BAW-1543(NP), Revision 4, Supplement 5, 'Supplement to the Master Integrated Reactor Vessel Surveillance Program'," OG:04:1847, NRC:04:030, July 7, 2004.

Ref.: 3. Letter, James F. Mallay (Framatome ANP) to Document Control Desk (NRC), "Supporting Materials for Review of BAW-1543(NP), Revision 4, Supplement 5, 'Supplement to the Master Integrated Reactor Vessel Surveillance Program'," OG:04:1855, NRC:04:068, November 30, 2004.

On behalf of the B&W Owners Group Reactor Vessel Working Group, Framatome ANP (FANP) requested the NRC's review and approval for referencing in licensing actions the topical report BAW-1 543(NP), Revision 4, Supplement 5, "Supplement to the Master Integrated Reactor Vessel Surveillance Program," (Reference 1). Our response to a Request for Additional Information was provided in Reference 2. A supplemental request for clarification of the contents of Table VIII of the report was discussed in a telephone call on November 23, 2004 (Reference 3). A second request for further clarification of the contents of Table VIII was discussed in a telephone call on December 1, 2004, between Mr. Brian Hall of FANP and Ms. Meena Khanna of the NRC.

Framatome ANP, Inc. B&W Owners Group 3315 Old Forest Road Lynchburg, VA 24501 Phone: 434-832-3635 Fax: 434-832-4121

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Document Control Desk NRC:05:001/OG:05:1859 January 5, 2004 Page 2 Attachment I provides a revised Table Vil that clarifies how Oconee Unit 2, Oconee Unit 3 and TMI are meeting the minimum number of capsules to be withdrawn and tested in accordance with ASTM E185-82. This table completely replaces the table submitted in Reference 3.

We would appreciate your timely review.

Very truly yours, Jerald S. Holm, Director Regulatory Affairs Enclosure cc:

D. G. Holland B&WOG Reactor Vessel Working Group Project 693

Document Control Desk January 5, 2005 NRC:05:001/OG:05:1859 Page A-1 Attachment I Comparison of the Plant-Specific Surveillance Capsules with ASTM E 185 Requirements Table VIII. Comparison of the Plant-Specific Surveillance Capsules with ASTM E 185 Requirements ASTM E 185-82 5 Capsule Program Requirement 3 EFPY EOL 1.5 EFPY or or or Fluence Midway 6 EFPY 15 EFPY 1-2 Times EOL Fluence Fluence > 5E1 8 Between First and or or (Capsule may be Plant ARTNDT o 50°F Third Capsule T/4 EOL Fluence IS EOL Fluence held w/o testing)

Oconee-I F-l/T (a)

E-VT A-IUT C-IT Oconee-2 C-I/T A-I/T TMI2-LG1/T E-1T AS/T Oconee-3 A-U1T B-I/T LI/T D-I/T CR3 -LG2/T TMI-I E-I/T Wl/T CR3-LGI/T C-I/T TMI2-LG2/T Crystal River-3 B-UT

()

C-I/T D-I/T F-UlT ANO-I E-I/T

()

B-IT A-UT C-UT Davis-Besse F-I/T (a)

B-T D-I/T A-U/T Point Beach-I V-I/T S-I/T T-U/T R-I/T P-INT Point Beach-2 V-I/T T-llT R-I/T S-I/T P-I/NT SurWy-I T-U1T W-ITrl)

V-I/T X-I/T S,U-R Surry-2 X-I/T W-Irlo)

V-I/T Y-I/T S-I/Ib);T-R Turkey Point-3 T-UT V-UT S-U/T X-IT U,W-R Turkey Point-4 T-UlT S-I/T X-R V-R U,W-R Legend: I/T = Irradiated and tested I/NT = Irradiated and not tested R = In reactor (a) Only 4 capsules required per ASTM E185-82.

(b) Only dosimetry evaluated.