PLA-7015, Response to Request for Additional Information on Proposed Relief Request No. 3RR-20 to the Third 10-Year Inservice Inspection Program
| ML13157A170 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/06/2013 |
| From: | Franke J Susquehanna |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| PLA-7015 | |
| Download: ML13157A170 (7) | |
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I UN ()) 6 Z013 Jon A. Franke Site Vice President PPLSusquehannaJLLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@pplweb.com ppl.~~~:
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED RELIEF REQUEST NO. 3RR-20 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM PLA-7015 Docket No. 50-388
References:
"Susquehanna Steam Electric Station Proposed Relief Request No. 3RR-20 to the Third 10-Year htservice Inspection Program for Susquehanna SES Unit 2, "
dated May 6, 2013.
- 2)
Letter from NRC to PPL, "Susquehanna Steam Electric Station Unit 2 -
Request for Additional Information Regarding Relief Request 3RR-20 to the Third 10-Year Inservice bMpection Program (J'AC No. MF1756), dated May 9, 2013".
In Reference 1, PPL Susquehanna, LLC (PPL) submitted a proposed relief request for the Susquehanna Steam Electric Station (SSES) Unit 2 Third 10-Year Inservice Inspection Program. On May 9, 2013, the NRC requested additional infotmation (RAI) via Reference 2. The attachments to this letter contain PPL' s response to the RAI.
There are no new regulatory commitments contained in this letter.
Please direct and any questions or requests for additional information to Mr. Duane L. Filchner at (610) 774-7819.
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'if!/flke 1- - Response to NRC Request for Additional Information - Flange Bolting Area Sketch TM Copy:
Mr. W. M. Dean, NRC Region I Administrator Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP Document Control Desk PLA-7015 to PLA-7015 Response to NRC Request for Additional Information to PLA-7015 Page 1 of2 Response to NRC Request for Additional Information NRC QUESTION 1:
Please describe the Susquehanna operational experience with any possible leakage from the Reactor Recirculation Pump Flange mechanical joint, which might be indicative of degradation of the joint materials.
PPL RESPONSE:
No leakage has ever been observed from the Susquehanna Reactor Recirculation Pump (RRP)
Flange mechanical joints during any periods of reactor power operation. During these periods of power operation, the drywell was inerted and no personnel entries were made.
During the Unit 2-15th Refueling and Inspection Outage, on 5/9/2011 the reactor vessel leak check was performed in accordance with surveillance test procedure SE-200-002. While performing the reactor vessel leak check, the RRP cover-to-casing joints for both the '2A' and the '2B' RRP were observed to be leaking. Condition Report (CR) 1403912 reported a 300 drop per minute (dpm) leakage rate from RRP 2P401A, and CR 1403914 reported a 450 dpm leakage rate from RRP 2P401B. Engineering Work Request (EWR) 1403994 documented that the leakage observed during the Reactor Pressure Vessel in-service leak test is consistent with historical observations and is expected to reduce as the seals heat up under pressure.
Susqueharma experience is that any leakage that has been observed during reactor leak checks has diminished and stopped as a result of the higher temperatures seen during unit startups using nuclear heat. There is no evidence of damage from leakage at the pump flange mechanical joints. Visual signs of damage would be expected if the flanges were leaking during reactor power operation.
NRC QUESTION 2:
The submittal states that, after discovery of the missed VT -1 of the 'A' Reactor Recirculation Pump Flange a VT -1 examination was performed of the assembled joint which achieved 98% of the required coverage. Provide a sketch or some other means of detailing the limitations of the VT -1 examination perfotmed on the 'A' Reactor Recirculation Pump Flange.
PPL RESPONSE:
A sketch of the flange bolting area and associated inspection area is provided in.
NRC QUESTION 3:
On page 2 of the submittal, the licensee states, in part, that:
Attaclunent 1 to PLA-7015 Page 2 of2 PPL will also perform [a] VT-2 examination on the pump prior to startup of Unit 2.
Please describe the plant conditions and hold time applicable to the performance of this VT -2 examination. If the pressure associated with the VT -2 examination will be different from that required by IWB-5221, please provide justification.
PPL RESPONSE:
The VT-2 examination was performed on May 21,2013. During the examination, no leakage was observed from the '2A' RRP 2P401A flange mechanical joint. An improved gasket was installed in this joint as a part of the '2A' RRP motor replacement.
The hold time applicable to this VT-2 examination (per SE-200-002) was 10 minutes.
The plant conditions applicable to this VT -2 examination were:
- Pressure of 1,035 psig to 1,045 psig.
Temperature of 101 degrees F to 200 degrees F.
Since the pressure associated with the VT -2 examination was NOT different from the IWB-5221 requirements, additional justification is not required.
to PLA-7015 Flange Bolting Area Sketch
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