Dresden: Difference between revisions

Sites

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Constellation

	Region	Reactor type	Containment type
Braidwood	NRC Region 3	Westinghouse PWR 4-Loop	Ambient Pressure
Byron	NRC Region 3	Westinghouse PWR 4-Loop	Ambient Pressure
Calvert Cliffs	NRC Region 1	CE	Ambient Pressure
Cantera
Clinton	NRC Region 3	GE-6	Mark III
Dresden	NRC Region 3	GE-3 GE-1	Mark I
FitzPatrick	NRC Region 1	GE-4	Mark I
Ginna	NRC Region 1	Westinghouse PWR 2-Loop	Ambient Pressure
Kennett Square	NRC Region 1
LaSalle	NRC Region 3	GE-5	Mark II
Limerick	NRC Region 1	GE-4	Mark II
Nine Mile Point	NRC Region 1	GE-5 GE-2 European Pressurized Reactor	Mark I Mark II
Peach Bottom	NRC Region 1	GE-4 HTGR	Mark I
Quad Cities	NRC Region 4	GE-3	Mark I
Three Mile Island	NRC Region 1	B&W-L-LP	Ambient Pressure

Inspections

NRC Residents: , Roy Elliott Jr., As the, Tom Briley (based on [newsletter list])

Inspections: Latest Schedule letter

Inspection Reports:
2024: 1(0)2(0)10(0)301(0)401(0)402(0)
2023: 1(0)1(0)2(0)3(0)4(0)5(0)6(0)10(0)11(0)301(0)401(0)402(0)501(0)1(0)2(0)10(0)301(0)401(0)402(0)
[full table]

Findings List (0) (CCA Matrix)

Letter
log

	Issue date	Title	Topic
RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .	16 October 2024	Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests	10 October 2024	Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests	Incorporated by reference
ML24275A244	3 October 2024	Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing

Projects

	Start date	Title	Request type	Estimated NRC review hours	Topic
EPID:L-2024-LLA-0061	8 May 2024	TSTF-591	License Amendment
EPID:L-2019-LLA-0124	18 June 2019	TSTF-542	License Amendment

Reactor Unit 2
Status
Docket	05000237
Licensed Power Level (Thermal)	902 MW
Unit type	GE-3
Containment	Mark I
Ultimate Heat Sink	Kankakee River
Commission	June 9, 1970
Renewal	2004
NRC Website
v • d • e

Reactor Unit 3
Status
Docket	05000249
Licensed Power Level (Thermal)	895 MW
Unit type	GE-3
Containment	Mark I
Ultimate Heat Sink	Kankakee River
Commission	November 16, 1971
Renewal	2004
NRC Website
v • d • e

@@ Line 10: / Line 10: @@
 |site unit={{Site unit
 |Unit number=2
+|Power=902 MW
 |Docket=05000237
 |is cancelled=No
 |Commission date=June 9, 1970
+|Renewal date=2004
 |Reactor type=GE-3
 |Containment type=Mark I
+|Ultimate heat sink=Kankakee River
 |url=https://www.nrc.gov/info-finder/reactors/dres2.html
 }}{{Site unit
 |Unit number=3
+|Power=895 MW
 |Docket=05000249
 |is cancelled=No
 |Commission date=November 16, 1971
+|Renewal date=2004
 |Reactor type=GE-3
 |Containment type=Mark I
+|Ultimate heat sink=Kankakee River
 |url=https://www.nrc.gov/info-finder/reactors/dres3.html
 }}{{Site unit
@@ Line 28: / Line 34: @@
 |Docket=05000010
 |is cancelled=No
-|Commission date=1960
+|Commission date=July 4, 1960
-|Decommission date=1978
+|Decommission date=October 31, 1978
+|Reactor type=GE-1
+|Ultimate heat sink=Kankakee River
 |url=https://www.nrc.gov/info-finder/decommissioning/power-reactor/dresden-nuclear-power-station-unit-1.html
 }}
 }}

Revision as of 18:50, 16 June 2018