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NRR-PMDAPEm Resource From: Sreenivas, V Sent: Friday, February 07, 2014 9:17 AM To: 'david.heacock@dom.com' Cc: 'david.sommers@dom.com'; Pascarelli, Robert; Barillas, Martha; 'Gary D Miller'; Tom Shaub
Subject:
Surry-Unit1: RAI: ALTERNATIVE S1-I5-SPT-01 REGARDING SYSTEM PRESSURE TEST OF BOTTOM OF REACTOR VESSEL REQUEST FOR ADDITIONAL INFORMATION (RAI)
REQUEST FOR ALTERNATIVE S1-I5-SPT-01 REGARDING SYSTEM PRESSURE TEST OF BOTTOM OF REACTOR VESSEL VIRGINIA ELECTRIC AND POWER COMPANY - DOMINION SURRY POWER STATION, UNIT 1 DOCKET NUMBER 50-280 By letter dated November 26, 2013 (Agencywide Documents Access and Management Systems (ADAMS)
Accession No. ML13336A142), Virginia Electric and Power Company - Dominion (the licensee) submitted for the U.S. Nuclear Regulatory Commission (NRC) approval request for alternative (RFA) S1-I5-SPT-01. The licensee proposed an alternative to a certain requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. RFA S1-I5-SPT-01 relates to the inservice inspection (ISI) requirement of IWB-5220 during the system leakage test of the bottom of the reactor vessel every refueling outage. The licensee submitted the request for the Surry Power Station (Surry), Unit 1.
The NRC staff requests the following additional information.
- 1. Discuss how the VT-2 visual examination is performed for the bottom of the reactor vessel? (e.g., Is this a bare metal visual of the reactor vessel bottom shell? If not, how is a potential leak from the insulated area on the bottom of the reactor vessel be detected? Are there any vessel bottom head penetrations that are also subject to the VT-2 examinations under this request?).
- 2. Section 5 of the request stated, in part, that Dominion will continue to monitor leakage on the bottom of the reactor vessel with other surveillance requirements and alarms Describe what the other surveillance requirements and alarms are. Discuss the leakage detection capabilities at the plant, or any measure(s) taken, to monitor and identify leakage in an unlikely event of a through wall leak on the bottom head of the reactor vessel during normal operation.
- 3. For justifications that the structural integrity and leak tightness of the bottom of reactor vessel be reasonably ensured without performing the required ASME Code system leakage test, discuss whether there has been any pant-specific, fleet, and industry operating experience (OE) regarding potential degradation of the bottom head of the reactor vessel due to known degradation mechanisms that would lead to leakage.
- 4. The licensee asked relief from the IWB-5220 System Leakage Test requirements. The NRC staff notes that IWB-5220 contains two separate paragraphs, IWB-5221 and IWB-5222. Confirm that the request for alternative will be to both of the IWB-5221 and IWB-5222 requirements. If yes, provide alternative to each paragraph of IWB-5222 (i.e., IWB-5222(a) and IWB-5222(b)).
Please submit the response to these RAIs by March 10, 2014. If you have any questions please contact me at your earliest.
1
V. Sreenivas, PH.D., C.P.M.,
Project Manager, Rm.#O8F6, LPL2-1 North Anna and Surry Power Reactors, Units 1 and 2 Division of Operating Reactor Licensing-NRR (301) 415-2597, v.sreenivas@nrc.gov
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2
Hearing Identifier: NRR_PMDA Email Number: 1071 Mail Envelope Properties (V.Sreenivas@nrc.gov20140207091700)
Subject:
Surry-Unit1: RAI: ALTERNATIVE S1-I5-SPT-01 REGARDING SYSTEM PRESSURE TEST OF BOTTOM OF REACTOR VESSEL Sent Date: 2/7/2014 9:17:09 AM Received Date: 2/7/2014 9:17:00 AM From: Sreenivas, V Created By: V.Sreenivas@nrc.gov Recipients:
"'david.sommers@dom.com'" <david.sommers@dom.com>
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None "Barillas, Martha" <Martha.Barillas@nrc.gov>
Tracking Status: None
"'Gary D Miller'" <gary.d.miller@dom.com>
Tracking Status: None "Tom Shaub" <tom.shaub@dom.com>
Tracking Status: None
"'david.heacock@dom.com'" <david.heacock@dom.com>
Tracking Status: None Post Office:
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