PLA-7418, Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-21

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Response to Request for Additional Information for the Third Interval Relief Requests 3RR-19, 3RR-20 and 3RR-21
ML15345A005
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 12/10/2015
From: Franke J
Susquehanna, Talen Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7418
Download: ML15345A005 (4)
v • d • e


Text

Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard TALEN ~

Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542 .1504 ENERGY jon.franke@talenenergy.com DEC .1 0 2DJ~

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON FOR THE THIRD INTERVAL RELIEF REQUESTS 3RR-19, 3RR-20 AND 3RR-21 Docket Nos. 50-387 PLA-7418 and 50-388

References:

I. Letter PLA-7338, "End of Interval ReliefRequests [3RR-19, 3RR-20 and 3RR-21} for Third Inservice Inspection Interval, "dated May 28, 2015 (Accession ML15148A774).

2. Letter PLA-7371, "Response to Request for Supplemental Information for the Third Interval ReliefRequests 3RR-19, 3RR-20 and 3RR-21 "dated August 6, 2015 (Accession ML15233A089).
3. NRC Letter, "Request for Additional Information Regarding Proposed ReliefRequests for the Third 10-Year Inservice Inspection Interval, (CAC Nos. MF6302 Through MF6307), "dated November 13, 2015 (Accession ML15316A563).

The purpose of this letter is for Susquehanna Nuclear, LLC to provide the requested additional information (RAI). With Reference 1, and as supplemented by additional information in Reference 2, Susquehanna Nuclear, LLC submitted requests in accordance with 10 CR 50.55(a)(g)(5)(iii), which involve determinations of impracticality that apply to certain required examinations for the third 10-year Inservice Inspection (IS I) Interval.

Their examinations demonstrated limitations experienced when attempting to comply with the required Code requirements for components described by these requests.

In Reference 3, the RAI includes the question RAI 1 about request 3RR-20. A response is provided in Attachment 1.

There are no new regulatory commitments associated with this response.

If you have any questions or require additional information, please contact Mr. Jas ennings (570) 542-3155 .

. A. Franke

Document Control Desk PLA-7418 : Response to Requested Additional Infmmation Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. M. Shields, P A DEP/BRP

Attachment 1 to PLA-7418 Response to Requested Additional Information

Attachment 1 to PLA-7418 Page 1 of 1 Response to Requested Additional Information

RAI 1

In Relief Request No. 3RR-20, the achieved examination coverage for weld DG-DH is 7.7 percent for SSES, Unit 1, during the third 10-year lSI interval. The NRC staff notes that the DG-DH achieved examination coverage is 23.7 percent for both SSES units for all previous 10-Year lSI Intervals for this weld. Please explain why the achieved examination coverage decreased from 23.7 percent to 7.7 percent for weld DG-DH for SSES, Unit 1, during the third 10-year lSI interval.

Response to RAI 1:

Susquehanna Nuclear, LLC has not determined the cause for the discrepancy between Unit 1 and 2 coverage obtained for the DG and DH Bottom Head Dollar Side Plate welds. Based on the documentation provided under the examination datasheet, (e.g.,

limited due to bottom head penetrations), the differences may have resulted from physical personnel limitations and/or the measurements taken from the covered area. With no cause for the apparent discrepancy determined, these differences in the obtained examination coverage are entered into the station's Corrective Action Program. This will provide an oppmiunity to investigate the cause further, by performing additional examination. This additional examination of the DG and DH welds will be done in an upcoming Unit 1 refueling outage, in Spring 2016. No compensatory measures are required. The examinations previously performed on the DG and DH welds in Unit 1 resulted in examination coverage of23.7 percent, which have remained consistent with the third Interval Unit 2 coverage. No relevant indications have been observed in any of these previous examinations resulting in the 23.7 percent Code volume achieved for the DG and DH Bottom Head Dollar Side Plate welds. This shows there is no history of indications detected from any of the previous examinations.

Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard TALEN ~

Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542 .1504 ENERGY jon.franke@talenenergy.com DEC .1 0 2DJ~

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON FOR THE THIRD INTERVAL RELIEF REQUESTS 3RR-19, 3RR-20 AND 3RR-21 Docket Nos. 50-387 PLA-7418 and 50-388

References:

I. Letter PLA-7338, "End of Interval ReliefRequests [3RR-19, 3RR-20 and 3RR-21} for Third Inservice Inspection Interval, "dated May 28, 2015 (Accession ML15148A774).

2. Letter PLA-7371, "Response to Request for Supplemental Information for the Third Interval ReliefRequests 3RR-19, 3RR-20 and 3RR-21 "dated August 6, 2015 (Accession ML15233A089).
3. NRC Letter, "Request for Additional Information Regarding Proposed ReliefRequests for the Third 10-Year Inservice Inspection Interval, (CAC Nos. MF6302 Through MF6307), "dated November 13, 2015 (Accession ML15316A563).

The purpose of this letter is for Susquehanna Nuclear, LLC to provide the requested additional information (RAI). With Reference 1, and as supplemented by additional information in Reference 2, Susquehanna Nuclear, LLC submitted requests in accordance with 10 CR 50.55(a)(g)(5)(iii), which involve determinations of impracticality that apply to certain required examinations for the third 10-year Inservice Inspection (IS I) Interval.

Their examinations demonstrated limitations experienced when attempting to comply with the required Code requirements for components described by these requests.

In Reference 3, the RAI includes the question RAI 1 about request 3RR-20. A response is provided in Attachment 1.

There are no new regulatory commitments associated with this response.

If you have any questions or require additional information, please contact Mr. Jas ennings (570) 542-3155 .

. A. Franke

Document Control Desk PLA-7418 : Response to Requested Additional Infmmation Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. M. Shields, P A DEP/BRP

Attachment 1 to PLA-7418 Response to Requested Additional Information

Attachment 1 to PLA-7418 Page 1 of 1 Response to Requested Additional Information

RAI 1

In Relief Request No. 3RR-20, the achieved examination coverage for weld DG-DH is 7.7 percent for SSES, Unit 1, during the third 10-year lSI interval. The NRC staff notes that the DG-DH achieved examination coverage is 23.7 percent for both SSES units for all previous 10-Year lSI Intervals for this weld. Please explain why the achieved examination coverage decreased from 23.7 percent to 7.7 percent for weld DG-DH for SSES, Unit 1, during the third 10-year lSI interval.

Response to RAI 1:

Susquehanna Nuclear, LLC has not determined the cause for the discrepancy between Unit 1 and 2 coverage obtained for the DG and DH Bottom Head Dollar Side Plate welds. Based on the documentation provided under the examination datasheet, (e.g.,

limited due to bottom head penetrations), the differences may have resulted from physical personnel limitations and/or the measurements taken from the covered area. With no cause for the apparent discrepancy determined, these differences in the obtained examination coverage are entered into the station's Corrective Action Program. This will provide an oppmiunity to investigate the cause further, by performing additional examination. This additional examination of the DG and DH welds will be done in an upcoming Unit 1 refueling outage, in Spring 2016. No compensatory measures are required. The examinations previously performed on the DG and DH welds in Unit 1 resulted in examination coverage of23.7 percent, which have remained consistent with the third Interval Unit 2 coverage. No relevant indications have been observed in any of these previous examinations resulting in the 23.7 percent Code volume achieved for the DG and DH Bottom Head Dollar Side Plate welds. This shows there is no history of indications detected from any of the previous examinations.

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