ML14195A028
| ML14195A028 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/11/2014 |
| From: | Andrea George Division of Operating Reactor Licensing |
| To: | Linda Williams Energy Northwest |
| References | |
| MF3562 | |
| Download: ML14195A028 (3) | |
Text
1 NRR-PMDAPEm Resource From:
George, Andrea Sent:
Friday, July 11, 2014 1:25 PM To:
Williams, Lisa L.
Subject:
Request for Additional Information - ISI Program Alternative Request 3ISI-15 (TAC No.
MF3562)
Attachments:
RAIs MF3562.docx Ms. Williams, By letter dated March 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14077A173), Energy Northwest (the licensee), submitted for staff review and approval ISI Program Alternative Request 3ISI-15, which requests an alternative to the ASME Section XI code requirement of subarticle IWB-5220 for pressure testing of the Class 1 reactor vessel flange leak-off line each inspection period.
Draft RAIs were issued on July 9, 2014. The NRC project mananger was notified that a clarification call is not needed and it was agreed that Energy Northwest will respond to these RAIs within 45 days, which is August 25, 2014.
If circumstances result in the need to revise the agreed-upon response date, please contact me at (301) 415-1081 or via email at andrea.george@nrc.gov.
Thank you, Andrea George Project Manager Nuclear Regulatory Commission Division of Operating Reactor Licensing andrea.george@nrc.gov 301-415-1081
Hearing Identifier:
NRR_PMDA Email Number:
1422 Mail Envelope Properties (Andrea.George@nrc.gov20140711132500)
Subject:
Request for Additional Information - ISI Program Alternative Request 3ISI-15 (TAC No. MF3562)
Sent Date:
7/11/2014 1:25:15 PM Received Date:
7/11/2014 1:25:00 PM From:
George, Andrea Created By:
Andrea.George@nrc.gov Recipients:
"Williams, Lisa L." <llwilliams@energy-northwest.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1113 7/11/2014 1:25:00 PM RAIs MF3562.docx 27555 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR ALTERNATIVE 3ISI-15 COLUMBIA GENERATING STATION ENERGY NORTHWEST DOCKET NUMBER 50-397 By letter dated March 7, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14077A173), Energy Northwest (the licensee),
submitted for staff review and approval ISI Program Alternative Request 3ISI-15, which requests an alternative to the ASME Section XI code requirement of subarticle IWB-5220 for pressure testing of the Class 1 reactor vessel flange leak-off line each inspection period.
In order to complete its review, the U.S. Nuclear Regulatory Commission staff requests the following additional information:
- 1. Describe the Columbia Generating Station operating experience with regard to reactor pressure vessel flange O-ring leakage and/or leak-off line leakage (i.e.
history of any leakage, cause, corrective actions).
- 2. What is the fluid head pressure that exists in the leak-off line when the refueling cavity is filled to its normal refueling water level?
- 3. What actions will be taken when using the proposed alternative to ensure the leak-off lines are clear of air prior to performance of the VT-2 examination.
- 4. Is the leak-off piping requiring VT-2 examination during the leakage test all accessible for examination? If not, describe the accessible and inaccessible portions of the piping?
- 5. For the accessible portions of the Reactor Pressure Vessel Flange Leak-off Piping:
- a. Discuss if the piping is insulated or not. If the piping is insulated will the insulation be removed? If insulation will not be removed, discuss how the piping will be examined to identify potential pipe through-wall leakage.
- b. If the subject piping is located in a high elevation or far away location from the examiner, describe how the pipe through-wall leakage can be identified.
- 6. If any of the piping segments requiring VT-2 examination during the leakage test are inaccessible, discuss how the structural integrity of this piping will be demonstrated.