ML113250228

Request for Additional Information, Relief Request No. PRR-21

ML113250228
Person / Time
Site:	Pilgrim
Issue date:	11/22/2011
From:	Richard Guzman Division of Operating Reactor Licensing
To:	Entergy Nuclear Operations
Guzman R, NRR/DORL 415-1030
References
TAC ME5788
Download: ML113250228 (3)

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• • • • 1C Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 SUB..IECT: REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NO. PRR-21 (TAC NO. ME5788)

Dear Sir or Madam:

By letter dated August 5, 2011 (Agencywide Documents Access Management System (ADAMS)

Accession No. ML11230A919), Entergy Nuclear Operations, Inc. (the licensee or Entergy) requested Nuclear Regulatory Commission (NRC) approval to use the previously approved alternative repair plan discussed in Entergy letter No. 2.09.032, Pilgrim Relief Request (PRR)-19, "Jet Pump Instrumentation Nozzle Weld, RPV-N9A-1 Repair Plan," dated May 1, 2009, to repair reactor pressure vessel standby liquid control safe end to nozzle weld RPV-N14 1, if flaw indications are detected during in service inspection.

The NRC staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on November 21, 2011, and it was agreed that your response would be provided within 60 days of the date of this letter.

Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION PILGRIM RELIEF REQUEST (PRR) NO. 21 DOCKET NO. 50-293 The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by Entergy Operations, Inc. (the licensee), for Pilgrim Nuclear Power Station (Pilgrim) in its letter dated August 5, 2011, and has determined that additional information is necessary to complete the review of Relief Request No. PRR-21. 8ased on the staff's review, please provide a response which addresses the following request for additional information (RAI).

8y letter dated August 5, 2011, Entergy requested NRC approval to use the previously approved alternative repair plan discussed in Entergy Letter No. 2.09.032, Pilgrim Relief Request (PRR)-19, "Jet Pump Instrumentation Nozzle Weld, RPV-N9A-1 Repair Plan," dated May 1, 2009, to repair Reactor Pressure Vessel Standby Liquid Control safe end to nozzle weld RPV-N14-1, if flaw indications are detected during in-service inspection. PRR-19 was approved by NRC letter dated September 11, 2009, "Relief Request (PRR-19), Install a Weld Overlay on Jet Pump Instrumentation Nozzle Weld RPV-N9A-1 ," Pilgrim Nuclear Power Station. Entergy also stated, 'This relief request essentially becomes a supplement to the previously approved PRR-19 dated September 11,2009, expanding the scope to include RPV-N14-1 SLC safe end nozzle weld. As such, the NRC approved PRR-19 would apply to the RPV-N14-1 weld contingency repair plan." The approval of PRR-19 allowed an Alloy 52 overlay to be applied over a low alloy steel nozzle (SA-508 Class 2) to stainless steel (SA-182 F304) penetration seal weldment; also, the Alloy 52 overlay covered two welds and a safe end between the nozzle and the penetration. The approval of PRR-19 provided relief from portions of ASME Code Cases N-638-1 and N-504-3.

However, the relief request in the August 5, 2011 submittal, PRR-21, would apply to an Alloy 52 overlay over an Inconel nozzle (S8-166 Alloy) to stainless steel (SA-182 F304) safe end dissimilar weldment. Since the overlay materials are different, the staff requests that PRR-21 be revised to exclude the materials which do not apply to the welding of an Alloy 52 overlay over an Inconel nozzle to stainless steel (SA-182 F304) safe end weld.

Since PRR-21 is not applicable to a low alloy steel material, Entergy has requested that ASME Code Case N-638 be deleted from this request. References to ASME Code Case N-638 are interspersed throughout PRR-19. The NRC staff requests that clarification be provided to specify the parts of PRR-19 which are applicable to the application of the weld overlay on RPV N 14-1, and the parts of PRR-19 which are not applicable to the application of the weld overlay on RPV-N14-1. Therefore, the staff requests that PRR-21 be revised to exclude all references to items for which relief is not requested, i.e., delete all references to ASME Code Case N-638.

Enclosure

November 22,2011 Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NO. PRR-21 (TAC NO. ME5788)

Dear Sir or Madam:

By letter dated August 5,2011 (Agencywide Documents Access Management System (ADAMS)

Accession No. ML11230A919), Entergy Nuclear Operations, Inc. (the licensee or Entergy) requested Nuclear Regulatory Commission (NRC) approval to use the previously approved alternative repair plan discussed in Entergy letter No. 2.09.032, Pilgrim Relief Request (PRR)-19, "Jet Pump Instrumentation Nozzle Weld, RPV-N9A-1 Repair Plan," dated May 1, 2009, to repair reactor pressure vessel standby liquid control safe end to nozzle weld RPV-N14 1, if flaw indications are detected during inservice inspection.

The NRC staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on November 21, 2011, and it was agreed that your response would be provided within 60 days of the date of this letter.

Sincerely, Ira!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

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