ML14115A445
| ML14115A445 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/18/2014 |
| From: | Martha Barillas Plant Licensing Branch II |
| To: | Heacock D Dominion Generation |
| References | |
| MF3200 | |
| Download: ML14115A445 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Barillas, Martha Sent:
Friday, April 18, 2014 4:02 PM To:
David.heacock@dom.com; Pascarelli, Robert Cc:
David.sommers@dom.com; Gary D Miller (Generation - 6)
Subject:
Draft RAI for Surry Unit 1 RR S1-I5-ISI-02 TAC MF3200 DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF NO. S1-I5-ISI-02 PRESSURIZER SURGE NOZZLE INNER RADIUS VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION, UNIT 1 DOCKET NO. 50-280 (TAC NO. MF3200)
By letter dated November 26, 2013, (Agencywide Document Access and Management System (ADAMS)
Accession Number ML13336A142), Virginia Electric and Power Company (Dominion), (the licensee),
submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the fifth 10-year Inservice Inspection (ISI) Program for Surry Power Station, Unit No. 1. This request is in relation to the pressurizer surge nozzle inner radius examination. The Surry, Unit No. 1 fifth 10-year ISI interval started on December 14, 2013, and will end on October 13, 2023.
The staff reviewed the information provided by the licensee, and requests the following Request For Additional Information (RAI) to complete its review:
- 1. The request states that the dose estimate for disconnection and removal of heater cables is 56 man-rem.
Please provide the assumptions and basic calculations for this estimate.
- 2. The requests states that the Cumulative Usage Factor for the nozzle inner radius is 0.29 (inside surface) and 0.11 (outside surface).
- a. Are these estimates of the current cumulative usage or the estimated usage at end of life for Surry Unit?
- b. Where is this evaluation documented?
- 3. Volumetric examination of components exposed to similar environmental conditions would further provide assurance of the subject component structural integrity, e.g. the surge line weld to the reactor coolant hot leg.
- a. Does the licensee plan any regularly scheduled or augmented inservice inspection of similar reactor coolant system components?
- b. If a thermal fatigue flaw was discovered in a surge line component other than the subject component, would the licensee take action to volumetrically examine the subject component?
- 4. When was the subject component last examined in accordance with ASME Code as conditioned by 10 CFR 50.55a, and were there any indications identified?
2 Please provide your RAI response by May 20, 2014. If you have any questions, you may reach me at (301) 415-2760.
Respectfully, Martha Barillas Project Manager-Surry Units 1 & 2 NRR/DORL/Licensing Branch II-1 US Nuclear Regulatory Commission 301-415-2760
Hearing Identifier:
NRR_PMDA Email Number:
1246 Mail Envelope Properties (Martha.Barillas@nrc.gov20140418160100)
Subject:
Draft RAI for Surry Unit 1 RR S1-I5-ISI-02 TAC MF3200 Sent Date:
4/18/2014 4:01:53 PM Received Date:
4/18/2014 4:01:00 PM From:
Barillas, Martha Created By:
Martha.Barillas@nrc.gov Recipients:
"David.sommers@dom.com" <David.sommers@dom.com>
Tracking Status: None "Gary D Miller (Generation - 6)" <gary.d.miller@dom.com>
Tracking Status: None "David.heacock@dom.com" <David.heacock@dom.com>
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2682 4/18/2014 4:01:00 PM Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
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Recipients Received: