ML19119A186: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 13, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 | ||
==SUBJECT:== | ==SUBJECT:== | ||
SURRY POWER STATION, UNIT 1 -REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING END-OF-CYCLE 28 REFUELING OUTAGE (EPID: L-2019-LR0-0219) | SURRY POWER STATION, UNIT 1 - REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING END-OF-CYCLE 28 REFUELING OUTAGE (EPID: L-2019-LR0-0219) | ||
==Dear Mr. Stoddard:== | ==Dear Mr. Stoddard:== | ||
By letter dated November 19 , 2018 (Agencywide Documents Access and Management Systems Accession No. ML18331A162), Virginia Electric and Power Company (the licensee) submitted information summarizing the results of the spring 2018, steam generator tube inspections performed at Surry Power Station , Unit 1, during end-of-cycle 28 refueling outage. The NRC staff has completed its review of the information provided, concludes that the licensee provided the information required by their technical specifications, and that no additional follow-up is required at this time. The staff's review of the report is enclosed. | By letter dated November 19, 2018 (Agencywide Documents Access and Management Systems Accession No. ML18331A162), Virginia Electric and Power Company (the licensee) submitted information summarizing the results of the spring 2018, steam generator tube inspections performed at Surry Power Station, Unit 1, during end-of-cycle 28 refueling outage. | ||
If you have any questions, please contact me at (301) 415-1438, or via email at Karen.Cotton@nrc.gov. Docket No.: 50-280 | The NRC staff has completed its review of the information provided, concludes that the licensee provided the information required by their technical specifications, and that no additional follow-up is required at this time. The staff's review of the report is enclosed. | ||
If you have any questions, please contact me at (301) 415-1438, or via email at Karen.Cotton@nrc.gov. | |||
Sincerely, Karen Cotton-Gross, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-280 | |||
==Enclosure:== | ==Enclosure:== | ||
As stated cc: Listserv | |||
OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTION REPORT DURING END-OF-CYCLE 28 REFUELING OUTAGE VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 1 DOCKET NO. 50-280 By letter dated November 19, 2018 (Agencywide Documents Access and Management Systems Accession No. ML18331A162), Virginia Electric and Power Company (the licensee) submitted information summarizing the results of the spring 2018 steam generator (SG) tube inspections performed at Surry Power Station, Unit 1, during refueling outage 28. | |||
* The three replacement SGs at Surry Unit 1 were installed in 1981. Westinghouse fabricated the replacement SGs and each SG contains 3,342 thermally treated Alloy 600 tubes. Each tube has a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by stainless steel tube support plates (TSPs ). The U-bends of the tubes installed in rows 1 through 8 were thermally stress relieved after bending. The licensee provided the scope, extent , methods, and results of their SG tube inspections in the documents referenced above. After reviewing the information provided by the licensee, the staff has the following observation: | * The three replacement SGs at Surry Unit 1 were installed in 1981. Westinghouse fabricated the replacement SGs and each SG contains 3,342 thermally treated Alloy 600 tubes. Each tube has a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. | ||
* The licensee stated that there was no reportable pitting and no cracking observed above the H-star region in 2018. Based on a review of the information provided , the NRC staff concludes that the licensee provided the information required by their technical specifications. | The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by stainless steel tube support plates (TSPs ). The U-bends of the tubes installed in rows 1 through 8 were thermally stress relieved after bending. | ||
In addition , the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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. Principal Contributor: | The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. After reviewing the information provided by the licensee, the staff has the following observation: | ||
A. Huynh, NRR/DMLR/MCCB | * The licensee stated that there was no reportable pitting and no cracking observed above the H-star region in 2018. | ||
'Enclosure D. Stoddard | Based on a review of the information provided , the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition , the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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. | ||
Principal Contributor: A. Huynh, NRR/DMLR/MCCB | |||
' Enclosure | |||
D. Stoddard | |||
==SUBJECT:== | ==SUBJECT:== | ||
SURRY POWER STATION , UNIT 1 -REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 28 (EPID: L-2019-LR0-0219) | SURRY POWER STATION, UNIT 1 - REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 28 (EPID: L-2019-LR0-0219) DATED MAY 13, 2019 DISTRIBUTION : | ||
DATED MAY 13, 2019 DISTRIBUTION | PUBLIC RidsAcrs_MailCTR Resource RidsNrrDorllpl2-1 Resource RidsNrrLAKGoldstein Resource RidsNrrPMSurry Resource RidsRgn2MailCenter Resource ADAMS Access,on No. ML19119A186 *C oncurrence b1y ema,*1 OFFICE D0RL/LPL2-1/PM D0RL/LPL2-1/LA DMLR/MCCB/BC D0RL/LPL2-1 /BC D0RL/LPL2-1 /PM NAME KCotton KGoldstein SBloom* MMarkley KCotton DATE 05/07/19 05/01/19 04/22/19 05/13/19 05/13/19 OFFICIAL RECORD COPY}} | ||
/BC D0RL/LPL2-1 | |||
/PM SBloom* MMarkley KCotton 04/22/19 05/13/19 05/13/19 OFFICIAL RECORD COPY}} |
Latest revision as of 20:55, 19 October 2019
ML19119A186 | |
Person / Time | |
---|---|
Site: | Surry |
Issue date: | 05/13/2019 |
From: | Cotton K Plant Licensing Branch II |
To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
Cotton K, NRR/DORL/LPL2-1, 415-1438 | |
References | |
EPID L-2019-LRO-0219 | |
Download: ML19119A186 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 13, 2019 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT 1 - REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING END-OF-CYCLE 28 REFUELING OUTAGE (EPID: L-2019-LR0-0219)
Dear Mr. Stoddard:
By letter dated November 19, 2018 (Agencywide Documents Access and Management Systems Accession No. ML18331A162), Virginia Electric and Power Company (the licensee) submitted information summarizing the results of the spring 2018, steam generator tube inspections performed at Surry Power Station, Unit 1, during end-of-cycle 28 refueling outage.
The NRC staff has completed its review of the information provided, concludes that the licensee provided the information required by their technical specifications, and that no additional follow-up is required at this time. The staff's review of the report is enclosed.
If you have any questions, please contact me at (301) 415-1438, or via email at Karen.Cotton@nrc.gov.
Sincerely, Karen Cotton-Gross, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.: 50-280
Enclosure:
As stated cc: Listserv
OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTION REPORT DURING END-OF-CYCLE 28 REFUELING OUTAGE VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 1 DOCKET NO. 50-280 By letter dated November 19, 2018 (Agencywide Documents Access and Management Systems Accession No. ML18331A162), Virginia Electric and Power Company (the licensee) submitted information summarizing the results of the spring 2018 steam generator (SG) tube inspections performed at Surry Power Station, Unit 1, during refueling outage 28.
- The three replacement SGs at Surry Unit 1 were installed in 1981. Westinghouse fabricated the replacement SGs and each SG contains 3,342 thermally treated Alloy 600 tubes. Each tube has a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches.
The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by stainless steel tube support plates (TSPs ). The U-bends of the tubes installed in rows 1 through 8 were thermally stress relieved after bending.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. After reviewing the information provided by the licensee, the staff has the following observation:
- The licensee stated that there was no reportable pitting and no cracking observed above the H-star region in 2018.
Based on a review of the information provided , the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition , the NRC staff concludes that there are no technical issues that warrant follow-up action at this time. 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.
Principal Contributor: A. Huynh, NRR/DMLR/MCCB
' Enclosure
D. Stoddard
SUBJECT:
SURRY POWER STATION, UNIT 1 - REVIEW OF THE SPRING 2018 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 28 (EPID: L-2019-LR0-0219) DATED MAY 13, 2019 DISTRIBUTION :
PUBLIC RidsAcrs_MailCTR Resource RidsNrrDorllpl2-1 Resource RidsNrrLAKGoldstein Resource RidsNrrPMSurry Resource RidsRgn2MailCenter Resource ADAMS Access,on No. ML19119A186 *C oncurrence b1y ema,*1 OFFICE D0RL/LPL2-1/PM D0RL/LPL2-1/LA DMLR/MCCB/BC D0RL/LPL2-1 /BC D0RL/LPL2-1 /PM NAME KCotton KGoldstein SBloom* MMarkley KCotton DATE 05/07/19 05/01/19 04/22/19 05/13/19 05/13/19 OFFICIAL RECORD COPY