PLA-5804, Clarification to Responses Provided for Relief Requests 3RR-01, 3RR-02 and 3RR-04 for Third Ten-year Interval Inservice Inspection Program Susquehanna Ses Units 1 and 2 on June 18, 2004
| ML042710272 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/16/2004 |
| From: | Mckinney B Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5804 | |
| Download: ML042710272 (7) | |
Text
Britt T. McKlnney Vice President-Nuclear Site Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@ pplweb.com
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SEP 1 6 2004 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P1-137 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION CLARIFICATION TO RESPONSES PROVIDED FOR RELIEF REQUESTS 3RR-01, 3RR-02 AND 3RR-04 FOR THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM SUSQUEHANNA SES UNITS 1 AND 2 ON JUNE 18,2004 PLA-5804 Docket Nos. 50-387 and 50-388
Reference:
Letterfrom B. L Shriver (PPL) to NRC Document Control Desk titled, "Response to Request for Additional Infornation from NRC on Proposed Relief Request Nos. 3RR-01, 3RR-02, and 3RR-04 to the Third 10-Year Inservice Inspection program for Susquehanna SES Units I and 2, " dated June 18, 2004.
The purpose of this letter is to clarify certain of the responses provided in the above referenced letter. In a conference call on August 3, 2004, the NRC requested that PPL make the following clarifications:
Relief Request 3RR-01; Question 2:
PPL will perform sample expansions in accordance with the EPRI Topical Report, EPRI TR-1 12657, Section 3.6.6.2. This change will also be incorporated into the text of Relief Request 3RR-01 when this Relief Request is revised due to the updating of our PRA.
Relief Request 3RR-02; Relief from the inspection requirements on RHR Pump Casing Welds:
The following information is provided to clarify PPL's position. For the RHR Pump Casing welds, a surface or volumetric examination will be performed on the welds or portions of welds that are accessible. Should a weld or portion of weld become accessible through normal maintenance activities, these welds will also have a surface or volumetric examination performed. Should access to these welds be restricted so that inspectors cannot adequately perform a surface or volumetric examination, a visual examination (VT-1) will be performed to the extent practical. Should this access be limited, a remote visual (VT-1) examination will be performed to the extent practical on accessible welds or portions of welds.
Document Control Desk PLA-5804 Request 3RR-04, Ouestion 1:
Attached are photographs that show the peripheral CRD region. These photographs support our contention that the peripheral welds are not accessible for inspection. Based on the configuration, a VT-1 examination would most likely have to be performed through a remote visual inspection process. At this time, we cannot assure that the inspection can be completed due to the small dimensions and concerns with the remote inspection devices becoming entangled in the various cables and structural supports associated with the peripheral CRD housings.
Request 3RR04, Question 2:
Susquehanna has no knowledge of degradation of CRD housing welds in the BWR fleet.
There are no new commitments made in this letter. If you have any questions, please contact Mr. C. T. Coddington at (610) 774-4019.
Sincerely, B.
cKinney Attachment - five photographs of the CRD housing area.
copy: NRC Region I Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP
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X Peripheral CRD showing shoot out steel and CRD flange
PLA-5804 Peripheral CRD's with shoot out steel
PLA-5804 Peripheral CRD flange
PLA-5804 Peripheral CRD bundles with CRD flanges and shoot out steel