ML102650536
| ML102650536 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/22/2010 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Division of License Renewal |
| References | |
| 06-848-02-LR | |
| Download: ML102650536 (14) | |
Text
PilgrimRenewal NPEmails From: Regner, Lisa Sent: Wednesday, September 22, 2010 3:21 PM To: Mogolesko, Fred Cc: PilgrimRenewal NPEmails
Subject:
Action request: DRAFT conference call summaries for comment Attachments: conf call 06 02 2010 - socket welds.doc; conf call 05 25 2010 - fogger housing.doc
- Fred, Attached are two conference call summaries from several weeks ago. I apologize for their lateness, but still would like your comments on accuracy. Response requested by 10/1.
- Thanks, Lisa Lisa Regner Palo Verde PM License Renewal 3014151906 1
Hearing Identifier: PilgrimRenewalNonPublic_EX Email Number: 250 Mail Envelope Properties (28C67094311E124FBAF1AA3E42B8819119F9C34E19)
Subject:
Action request: DRAFT conference call summaries for comment Sent Date: 9/22/2010 3:21:21 PM Received Date: 9/22/2010 3:21:23 PM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients:
"PilgrimRenewal NPEmails" <PilgrimRenewal.NPEmails@nrc.gov>
Tracking Status: None "Mogolesko, Fred" <fmogole@entergy.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 285 9/22/2010 3:21:23 PM conf call 06 02 2010 - socket welds.doc 64506 conf call 05 25 2010 - fogger housing.doc 63482 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Pilgrim Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JUNE 2, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING THE PILGRIM NUCLEAR POWER STATION, LICENSE RENEWAL APPLICATION (TAC NO. MC9669)
The U.S. Nuclear Regulatory Commission (the staff) and representatives of Entergy Nuclear Operations, Inc., (the applicant) held a telephone conference call on June 2, 2010, to discuss the Small-Bore Piping Aging Management Program (AMP) concerning the Pilgrim Nuclear Power Station (Pilgrim), license renewal application.
A supplemental review of One-Time Inspection of ASME Code Class 1 Small-Bore Piping Program in the June 2007, Safety Evaluation Report for Pilgrim revealed that the examination of socket welds was not adequately addressed and that the inspection only includes VT-2 (visual) and surface examinations. This is not consistent with the recommendation of Generic Aging Lessons Learned AMP XI.M.35. provides a listing of the participants and Enclosure 2 includes the draft request for additional information discussed with the applicant, including a brief description on the status of the item.
The applicant had an opportunity to comment on this summary.
Lisa M. Regner, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
As stated cc w/encls: Distribution via Listserv
ML102590077 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME LRegner YEdmonds DWrona LRegner DATE Memorandum to Entergy Nuclear Operations, Inc. from L. Regner dated September XX, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 25, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING THE ANNUAL UPDATE ASSOCIATED WITH THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxbes Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource JRobinson JDozier RAuluck LRegner JKim SUttal, OGC DJackson, RI MSchneider, RI NSheehan, RI
TELEPHONE CONFERENCE CALL PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JUNE 2, 2010 PARTICIPANTS AFFILIATIONS Lisa Regner U.S. Nuclear Regulatory Commission (NRC)
Steve Jones NRC Steve Bethay Entergy Nuclear Operations, Inc. (Entergy)
Joe Lynch Entergy Fred Mogolesko Entergy Dave Heard Entergy Paul Smith Entergy Rich Pardee Entergy Dave Lach Entergy Dave King Entergy ENCLOSURE 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION JUNE 2, 2010 DRAFT RAI xxxx - Small-Bore Piping Socket Welds
Background:
During the past year, the U.S. Nuclear Regulatory Commission (NRC or the staff) has worked extensively with license renewal applicants, the Nuclear Energy Institute, and the industry on socket weld examination issues for license renewal. The efforts also include review of operating experience of socket welds and various techniques for examination of socket welds.
The staff finds that volumetric examination of Class 1 small-bore piping socket welds recommended by the Generic Aging Lessons Learned (GALL) Report aging management program (AMP), XI.M.35, One-Time Inspection of ASME Code Class 1 Small-Bore Piping is warranted based on the operating experience review. It provides additional assurance either aging of small-bore American Society of Mechanical Engineers (ASME) Code Class 1 piping is not occurring or the aging is insignificant.
The staff noted that VT-2 examination, as ASME Section XI Code currently requires on socket welds, is leakage detection and not adequate for license renewal aging management. Since cracking of socket welds, in most cases, starts from the inside surface, by the time a flaw is detected by VT-2 or a surface examination, the subject component would have already failed and lost its intended function. This is the reason the GALL Report AMP recommends one-time volumetric examinations of small-bore piping, including socket welds, because examination of the external surface is not an adequate way to detect cracks initiating on the interior surface of a pipe.
The staff also finds that several demonstrated ultrasonic testing (UT) techniques have been developed and used by the nuclear industry. They provide an adequate result in the examination of socket welds. Recently developed and improved techniques have increased the capability to differentiate construction flaws and service induced flaws. Measures have been taken to minimize the possibility of false-positive indications. The staff understands that the GALL Report also recognizes additional options available to applicants including performing available industry-demonstrated UT, opportunistic destructive examinations, or Performance Demonstration Initiative qualified UT, when available, on socket welds.
Issue:
A supplemental review of One-Time Inspection of ASME Code Class 1 Small-Bore Piping Program in the LRA for Pilgrim Nuclear Power Station revealed that the examination of socket welds was not adequately addressed and that the inspections only include VT-2 and surface examinations. This is not consistent with the recommendation of the GALL Report.
ENCLOSURE 2
Request:
Explain how the One-Time Inspection of ASME Code Class 1 Small-Bore Piping Program will adequately manage the aging of socket welds given recent industry operating experience.
Discussion:
Entergy Nuclear Operations, Inc. (the applicant) explained that question is clear. The applicant will submit a response addressing the staffs concern.
LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Pilgrim Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 25, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING THE ANNUAL UPDATE ASSOCIATED WITH THE PILGRIM NUCLEAR POWER STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Entergy Nuclear Operations, Inc. (the applicant) held a telephone conference call on May 25, 2010, to discuss and clarify the staffs draft request for additional information (RAI) concerning the Pilgrim Nuclear Power Station, license renewal application. The draft RAI was associated with a letter submitted by the applicant dated December 28, 2009, in accordance with Title 10 of the Code of Federal Regulations, Part 54.21(b). The telephone conference call was useful in clarifying the intent of the staffs draft RAI. provides a listing of the participants and Enclosure 2 includes the draft RAI discussed with the applicant, including a brief description on the status of the item.
The applicant had an opportunity to comment on this summary.
Lisa M. Regner, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
As stated cc w/encls: Distribution via Listserv
ML102590086 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME LRegner DWrona LRegner DATE Memorandum to Entergy Nuclear Operations, Inc. from L. Regner dated September XX, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 25, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING THE ANNUAL UPDATE ASSOCIATED WITH THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxbes Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource JRobinson JDozier RAuluck LRegner JKim SUttal, OGC DJackson, RI MSchneider, RI NSheehan, RI
TELEPHONE CONFERENCE CALL PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 25, 2010 PARTICIPANTS AFFILIATIONS Lisa Regner U.S. Nuclear Regulatory Commission (NRC)
Steve Jones NRC Fred Mogolesko Entergy Nuclear Operations, Inc. (Entergy)
Steve Bethay Entergy Joe Lynch Entergy Dave Heard Entergy Paul Smith Entergy Rich Pardee Entergy Dave Lach Entergy Dave King Entergy ENCLOSURE 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION MAY 25, 2010 The U.S. Nuclear Regulatory Commission (the staff) and representatives of Entergy Nuclear Operation, Inc. (the applicant) held a telephone conference call on May 25, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Pilgrim Nuclear Power Station (PNPS) license renewal application (LRA).
Background:
Item 5 of the PNPS Annual Update, submitted by letter dated December 28, 2009, deletes the fogger housing component type from the LRA Table 2.3.3-4, Emergency Diesel Generator System Components Subject to Aging Management Review; and LRA Table 3.3.2-4, Emergency Diesel Generator System Summary of Aging Management Evaluation. LRA Table 2.3.3-4 identified the intended function of the fogger housing as a pressure boundary. LRA Table 3.3.2-4 identified the fogger housing material as copper alloy>15% Zn with an internal environment of untreated air and external environment of indoor air. This material/environment combination is different than the material/environment combination for other emergency diesel generator (EDG) components.
Section 2.3.3.4 of the LRA included the following discussion:
The EDG system has the following intended function for 10 CFR 54.4(a)(1):
- Provide power to essential AC busses during a loss of offsite power.
The air start and turbo air assist systems support the startup and operation of the emergency diesel generators. Each EDG engine is started by high pressure air, which powers the air motors to crank the engine and start combustion.
Issue:
LRA Drawing M219 showed a component identified as a Motor Oil Fogger in the piping supporting delivery of pressurized air from the EDG air receivers to 1 of the 2 sets of 2 air motors relied on to start the A EDG and to both sets of 2 air motors relied on to start the B EDG. Thus, the staff concluded that fogger housing described a unique component type whose integrity would be necessary for accomplishment of the EDG intended function for 10 CFR 54.4(a)(1).
Request:
Expain: 1) how the fogger housing is no longer required to support the EDG intended function, and 2) how the pressure boundary function is being achieved.
Discussion:
The applicant explained that question is clear. The applicant will submit a supplement to the December 28, 2009, Annual Update addressing the staffs question.
ENCLOSURE 2
ENCLOSURE 2