ML12216A095: Difference between revisions

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{{Adams
#REDIRECT [[PLA-6884, Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program]]
| number = ML12216A095
| issue date = 08/03/2012
| title = Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program
| author name = Helsel J M
| author affiliation = PPL Susquehanna, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000387, 05000388
| license number =
| contact person =
| case reference number = PLA-6884
| document type = Letter
| page count = 2
| project =
| stage = Withdrawal
}}
 
=Text=
{{#Wiki_filter:\ I I Jeffrey M. Helsel Nuclear Plant Manager PPL Susquehanna, LLC 7 69 Salem Boulevard Berwick , P A 18603 Tel. 5 7 0.542.3510 Fax 5 7 0.542.1504 \ ' I I I ' \ t I I I .I .. , Pp .l==: ...... TM U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION WITHDRAWAL OF PROPOSED RELIEF REQUEST NO. 3RR-19 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM FOR SUSQUEHANNA UNITS 1AND2 PLA-6884 Docket Nos. 50-387 and 50-388
 
==Reference:==
 
Letter (PLA-6847)from J. M. Helsel (PPL) to USNRC (Document Control Desk) Titled "Proposed Relief Request No. JRR-19 to the Third 10-Year lnservice Inspection Program for Susquehanna SES Units 1 and 2," dated April24, 2012. In the above referenced letter, PPL Susquehanna, LLC (PPL) requested the approval of Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program for Susquehanna SES Units 1 and 2. This Relief Request proposed the approval of ASME Code Case N-702 for use at Susquehanna SES. BWRVIP-108 is the technical basis used to implement the Code Case. Recent operating experience pointed out that not all design assumptions required for the use of BWRVIP-108 have been taken into consideration by the industry.
Most of these assumptions are called out under the Assumptions section of the BWRVIP document.
One assumption, however, was found in a later section of the BWRVIP-108 document and was not validated prior to submittal of the Relief Request. The assumption that was missed is that the number of thermal cycles (start-up and shut down) is assumed to be 40 or less over a 40-year plant life. This assumption is too conservative for most of the BWR fleet and Susquehanna exceeded this number well before its 40-year plant life. The problem of over-conservatism regarding the number of thermal cycles has been discussed with EPRI. EPRI/BWRVIP is working to correct/revise the BWRVIP-108 document so that it reflects a more realistic plant thermal cycle. At this time, there is no timeframe established for revision and publication of a revised BWRVIP-108 document.
Since design assumption on the number of thermal cycles has been exceeded, PPL requests that proposed Relief Request No. 3RR-19 be withdrawn. Document Control Desk PLA-6884 If you have any questions or require additional information, please contact Mr. John L. Tripoli, Nuclear Regulatory Affairs Manager, at (570) 542-3100.
Copy: NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Ms. C. J. Sanders, RC Project Manager Mr. L. J. Winker, DEP/BRP}}

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