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=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd. Glen Allen, VA 23060-6711  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711


==SUBJECT:==
==SUBJECT:==
NORTH ANNA POWER STATION, UNIT NO. 1 -REVIEW OF STEAM GENERA TOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033)  
NORTH ANNA POWER STATION, UNIT NO. 1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033)


==Dear Mr. Stoddard:==
==Dear Mr. Stoddard:==


By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18255A061
By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018.
), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018. The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033.
The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033. The enclosure documents the NRC staff's review of the submittal.
The enclosure documents the NRC staff's review of the submittal.
Sincerely, JC.~~,~~
Docket No. 50-338  
Plant Licensing Branch 11-1 Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-338


==Enclosure:==
==Enclosure:==


Review of Steam Generator Tube Inspection Report cc: Listserv Sincerely, J C.~~,~~ Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338
Review of Steam Generator Tube Inspection Report cc: Listserv
* By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML 18255A061
), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26.
* North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped.
The U-bend regions of the tubes in rows one through eight were stress-relieved after bending. The licensee provided the scope , extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings.
Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure 


==SUBJECT:==
REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338
NORTH ANNA POWER STATION, UNIT NO. 1 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033)
* By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26.
DATED APRIL 23, 2019 DISTRIBUTION:
* North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped. The U-bend regions of the tubes in rows one through eight were stress-relieved after bending.
PUBLIC PM Reading File RidsNrrLAKGoldstein Resource RidsNrrDorl Resource RidsRgn2MailCenter Resource RidsNrrPMNorthAnna Resource RidsNrrDmlrMccb Resource RidsNrrDmlrMphb Resource PKlein, NRR AJohnson, NRR AHuynh, NRR ADAMS Accession No. ML 19106A356 OFFICE DORL/LPL2-1  
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings.
/PM DORL/LPL2-1/LA NAME JRHall KGoldstein (JBurkhardt for) DATE 04/17/19 04/17/19 OFFICE DMLR/MPHB/BG*
Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
DORL/LPL2-1/BC NAME SBloom MMarkley (SWilliams for) DATE 03/06/19 04/18/19 OFFICIAL RECORD COPY *via email DORL/LPL2-1/LAit KZeleznock 04/17/19 DORL/LPL2-1/PM JRHall 04/23/19}}
Enclosure
 
ML19106A356                                          *via email OFFICE     DORL/LPL2-1 /PM       DORL/LPL2-1/LA             DORL/LPL2-1/LAit NAME       JRHall               KGoldstein (JBurkhardt for) KZeleznock DATE       04/17/19             04/17/19                    04/17/19 OFFICE     DMLR/MPHB/BG*         DORL/LPL2-1/BC             DORL/LPL2-1/PM NAME       SBloom               MMarkley (SWilliams for)   JRHall DATE       03/06/19             04/18/19                   04/23/19}}

Latest revision as of 20:27, 19 October 2019

Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage
ML19106A356
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/23/2019
From: Hall J
Plant Licensing Branch II
To: Stoddard D
Virginia Electric & Power Co (VEPCO)
Hall J NRR/DORL 415-4032
References
EPID L-2018-LRO-0033
Download: ML19106A356 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 April 23, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT:

NORTH ANNA POWER STATION, UNIT NO. 1 - REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR THE CYCLE 26 SPRING 2018 REFUELING OUTAGE (EPID L-2018-LR0-0033)

Dear Mr. Stoddard:

By letter dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company (the licensee) submitted its steam generator (SG) tube inspection report for the North Anna Power Station (North Anna), Unit No. 1, in accordance with Technical Specification (TS) 5.6.7, "Steam Generator Tube Inspection Report." The report summarizes the SG tube inspections performed during the North Anna, Unit No. 1 Cycle 26 refueling outage, in the spring of 2018.

The U.S. Nuclear Regulatory Commission (NRC) staff completed its review of the submittal and concluded that the licensee provided the information required by the North Anna, Unit No. 1 TSs. No additional follow-up is required at this time. This completes the NRC staff's efforts for EPID L-2018-LR0-0033. The enclosure documents the NRC staff's review of the submittal.

Sincerely, JC.~~,~~

Plant Licensing Branch 11-1 Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-338

Enclosure:

Review of Steam Generator Tube Inspection Report cc: Listserv

REVIEW OF THE 2018 STEAM GENERATOR TUBE INSPECTION REPORT VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 1 DOCKET NO. 50-338

  • By letter dated September 4, 2018 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML18255A061 ), Virginia Electric and Power Company, Inc. (the licensee), submitted information SlJmmarizing the results of the 2018 steam generator (SG) inspections at North Anna Power Station (North Anna), Unit No. 1. These inspections were performed during refueling outage 26.
  • North Anna, Unit No. 1 has three Westinghouse Model 54F replacement steam generators that were installed in 1993, each containing 3,592 thermally treated Alloy 690 tubes. The tubes have a nominal outside diameter of 0.875 inches, a nominal wall thickness of 0.050 inches, and are supported by seven stainless steel tube support plates and a baffle plate. Most of the tube support plate holes are quatrefoil-shaped. The U-bend regions of the tubes in rows one through eight were stress-relieved after bending.

The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions, such as tube plugging, taken in response to the inspection findings.

Based on its review of the information provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee provided the information required by North Anna, Unit No. 1 Technical Specification 5.6.7, "Steam Generator Tube Inspection Report." In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

Enclosure

ML19106A356 *via email OFFICE DORL/LPL2-1 /PM DORL/LPL2-1/LA DORL/LPL2-1/LAit NAME JRHall KGoldstein (JBurkhardt for) KZeleznock DATE 04/17/19 04/17/19 04/17/19 OFFICE DMLR/MPHB/BG* DORL/LPL2-1/BC DORL/LPL2-1/PM NAME SBloom MMarkley (SWilliams for) JRHall DATE 03/06/19 04/18/19 04/23/19

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