PLA-6884, Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program: Difference between revisions

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| issue date = 08/03/2012
| issue date = 08/03/2012
| title = Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program
| title = Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program
| author name = Helsel J M
| author name = Helsel J
| author affiliation = PPL Susquehanna, LLC
| author affiliation = PPL Susquehanna, LLC
| addressee name =  
| addressee name =  
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=Text=
=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  
{{#Wiki_filter:Jeffrey M. Helsel                 PPL Susquehanna, LLC                       \    I  I
                                                                                                    .I ..,
Nuclear Plant Manager                      769 Salem Boulevard            \   ' I I     I
                                                                                                '   \   t I I I     ~
                                                                                                  ~~*******~~ ~
Berwick, PA 18603 Tel. 570.542.3510 Fax 570.542.1504 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                                                                             Docket Nos. 50-387 PLA-6884                                                                                      and 50-388


==Reference:==
==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.


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.
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.
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}}
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}}

Latest revision as of 01:11, 12 November 2019

Withdrawal of Proposed Relief Request No. 3RR-19 to the Third 10-Year Inservice Inspection Program
ML12216A095
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 08/03/2012
From: Helsel J
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6884
Download: ML12216A095 (2)
v • d • e


Text

Jeffrey M. Helsel PPL Susquehanna, LLC \ I I

.I ..,

Nuclear Plant Manager 769 Salem Boulevard \ ' I I I

' \ t I I I ~

~~*******~~ ~

Berwick, PA 18603 Tel. 570.542.3510 Fax 570.542.1504 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 Docket Nos. 50-387 PLA-6884 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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