ML031681408

Risk-Informed ISI Relief Requests R-1 Response to Request for Additional Information

ML031681408
Person / Time
Site:	Surry, North Anna
Issue date:	06/05/2003
From:	Hartz L Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
03-235A, NL&OS/ETS RO
Download: ML031681408 (5)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 5, 2003 United States Nuclear Regulatory Commission Serial No.: 03-235A Attention: Document Control Desk NL&OS/ETS RO Washington, D. C. 20555 Docket Nos. 50-338, 339 50-280, 281 License Nos.: NPF-4, 7 DPR-32, 37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 RISK-INFORMED ISI RELIEF REQUESTS R-1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION In a letter dated June 13, 2002 (Serial No.02-212), Virginia Electric and Power Company (Dominion) submitted Relief Request R-1 for Surry Unit 1 and revised Relief Requests R-1 for North Anna Units 1 and 2 and Surry Unit 2. These relief requests apply to socket-welded connections and their associated branch connections 2 inches and smaller nominal pipe size. The relief requests address the difficulty of perforrning volumetric examinations on these type of connections.

During staff review of the relief requests, the NRC requested additional information clarifying the performance of the examination of the socket-welded connections. A conference call was held on June 3, 2003, to discuss the staff questions. At the conclusion of the conference call, Dominion agreed to provide a written response to the NRC's questions. Our response is provided in the attachment.

If you have any questions or require additional information, please contact us.

Very truly yours, Leslie N. Hartz Vice President - Nuclear Engineering Attachment Commitments made in this letter: None

'%t cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center, Suite 300 4201 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. R. A. Smith Authorized Nuclear Inspector Surry Power Station Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8H12 Rockville, MD 20852 Mr. C. Gratton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8G9 Rockville, MD 20852

Attachment Response to NRC Request for Additional Information Relief Requests R-1 North Anna Units I and 2 Surry Units 1 and 2 Virginia Electric and Power Company (Dominion)

Attachment Response to Request for Additional information Relief Requests R-1 North Anna and Surrv Power Station Units I and 2 Dominion Clarification:

In general, the VT-2 examination and pressure test required by relief request R-1 will conform to the requirements of ASME Section XI IWA-2000 & 5000 of the Edition and Addenda applicable to the station's Inservice Inspection (ISI) program. Additionally, NRC approved Code Case N-498-1 (or later revision as approved by the NRC) may be applied for the end of interval testing.

NRC Question (1)

What hold times will be used?

Dominion Response (1)

The requirements of ASME Section Xl IWA-5000 or Code Case N-498-1 (or later NRC approved revision) will be followed as applicable for hold times. This response also comports with the latest NRC regulation on this subject found in 10 CFR50.55a(b)(2)(xix).

Specifically:

Class 1 High Safety Significant (HSS) hold times Insulated components - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> minimum at test pressure Non-insulated components - 10 minutes minimum at test pressure Class 2 or 3 HSS (Surrv Unit 1 only) hold times Normally oDerating Insulated components - system operating for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Non-insulated components - system operating for at least 10 minutes Normally standby (not ooerating)

Insulated and non-insulated - 10 minutes minimum at test pressure Page 1 of 2

NRC Question (2)

What pressure test requirements will be used?

Dominion Response (2)

The requirements of IWA-5000 of ASME Section Xi or ASME Code Case N-498-1 (or later NRC approved revision) shall be followed at nominal operating pressure in conjunction with a visual (VT-2) examination.

NRC Question (3)

Will the test be done In accordance with ASME Code requirements?

Dominion Response (3)

Yes, the test will be performed in accordance with ASME Section Xl IWA-2000 and 5000, or Code Case N-498-1 (or later NRC approved revision), except test frequencies, which will be applied conservatively for Class 2 and 3 piping by testing on an every refueling outage basis. Additionally, the test would require nominal operating pressure even if the Code does not (e.g., Class 1 leakage test beyond first isolation valve).

NRC Question (4)

Will the test be done In accordance with system leakage test, system functional test, hydrostatic test, and or system pressure test requirements?

Dominion Response (4)

The appropriate pressure tests, as required by ASME Section Xl IWA-5000 or Code Case N-498-1 (or later NRC approved revision), will be performed on these piping segments.

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