ML20317A215

ROP Substantive Cross Cutting Issues Summary

ML20317A215
Person / Time
Issue date:	08/09/2017
From:	Office of Nuclear Reactor Regulation
To:
References
Download: ML20317A215 (137)

Text

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Page 1 of 3 End of Cycle 2006 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Page 2 of 3 Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oyster Creek Oconee 1 Oconee 2 Oconee 3 Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Page 3 of 3 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary l Action Matrix Summary l Reactor Oversight Process Last Modified: August 31, 2006

End of Cycle 2006 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1

Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oyster Creek Oconee 1 Oconee 2 Oconee 3 Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2

Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary l Action Matrix Summary l Reactor Oversight Process Last Modified: August 31, 2006

Mid Cycle 2007 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold

Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1

Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 10, 2007

Mid Cycle 2007 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold

Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1

Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 10, 2007

Mid Cycle 2007 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold

Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1

Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 10, 2007

Mid Cycle 2008 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold

Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1

Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 04, 2008

Mid Cycle 2008 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun

Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3

Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 04, 2008

End of Cycle 2008 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2

Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1

Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Apr 14, 2009

End of Cycle 2008 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2

Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1

Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Apr 14, 2009

Mid Cycle 2009 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2

Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2

Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 02, 2009

End of Cycle 2008 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1

Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Jul 23, 2009

End of Cycle 2009 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 04, 2010

End of Cycle 2009 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 04, 2010

Mid Cycle 2010 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 03, 2010

Mid Cycle 2010 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 03, 2010

End of Cycle 2010 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 08, 2011

End of Cycle 2010 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 08, 2011

Mid Cycle 2011 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 06, 2011

Mid Cycle 2011 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 06, 2011

End of Cycle 2011 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 07, 2012

End of Cycle 2011 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2

River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 07, 2012

Mid Cycle 2012 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2

Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2

Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 06, 2012

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Mid Cycle 2012 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Page 1 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Page 2 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Page 3 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Last Modified: Sep 06, 2012 Page 4 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2012 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 05, 2013 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2012 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Page 1 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 Kewaunee La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Page 2 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Page 3 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Last Modified: Mar 05, 2013 Page 4 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Mid Cycle 2013 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Page 1 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Page 2 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Page 3 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Last Modified: Sep 05, 2013 Page 4 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Mid Cycle 2013 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper Crystal River 3 D.C. Cook 1 D.C. Cook 2 Page 1 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Page 2 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 San Onofre 2 San Onofre 3 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Page 3 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Last Modified: Sep 05, 2013 Page 4 of 4

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2013 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 06, 2014 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2013 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 06, 2014 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Mid Cycle 2014 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 04, 2014 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Mid Cycle 2014 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vermont Yankee Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 04, 2014 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2014 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Feb 26, 2015 Page 3 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary End of Cycle 2014 ROP Substantive Cross Cutting Issues Summary The NRC evaluates whether a substantive cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a substantive cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific substantive cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agencys assessment and licensees progress in addressing the issue.

Yes in the matrix below indicates that the plant has a open substantive cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the Yes will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a substantive cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Page 1 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Substantive Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Feb 26, 2015 Page 3 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Mid Cycle 2015 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency?s assessment and licensee?s progress in addressing the issue.

?Yes? in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the ?Yes? will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 01, 2015 Page 3 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Mid Cycle 2015 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency?s assessment and licensee?s progress in addressing the issue.

?Yes? in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the ?Yes? will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Sep 01, 2015 Page 3 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary End of Cycle 2015 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency?s assessment and licensee?s progress in addressing the issue.

?Yes? in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the ?Yes? will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 02, 2016 Page 3 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary End of Cycle 2015 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 02, 2016 Page 3 of 3

HOME FAQ GLOSSARY FACILITY LOCATOR WHAT'S NEW SITE HELP INDEX A-Z CONTACT US EMAIL UPDATES LISTEN TO PAGE NUCLEAR NUCLEAR RADIOACTIVE NUCLEAR PUBLIC MEETINGS & NRC ABOUT REACTORS MATERIALS WASTE SECURITY INVOLVEMENT LIBRARY NRC PRINT OPERATING REACTOR OVERSIGHT Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Cross Cutting Issues Cross Cutting Issues ROP Framework Performance Indicators The NRC evaluates whether a cross cutting issue exists at each operating reactor twice a year; Inspection Reports during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the ROP Evaluation NRC determines that a cross cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross cutting issue to include the Plant Summaries necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that Inspection Findings the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

Action Matrix "Yes" in the matrix below indicates that the plant has an open cross cutting issue in that area based on the Assessment Letters most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the Cross Cutting Issues assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the ROP References assessment letter that describes the issue.

Mid Cycle 2016 Human Problem Identification Safety-Conscious Work Plants Performance and Resolution Environment Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Spotlight Braidwood 1 CHOOSE A SECTION Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton

Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2

Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1

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US NRC Reactor Oversight Process - Cross Cutting Issues Summary Mid Cycle 2016 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3

Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 LaSalle 1 LaSalle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2

Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 Last Modified: Jan 23, 2017

US NRC Reactor Oversight Process - Cross Cutting Issues Summary End of Cycle 2015 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Fort Calhoun Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 La Salle 1 La Salle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Pilgrim 1 Point Beach 1 Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Mar 02, 2016 Page 3 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Mid Cycle 2016 ROP Cross Cutting Issues Summary The NRC evaluates whether a cross-cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross-cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross-cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency?s assessment and licensee?s progress in addressing the issue.

?Yes? in the matrix below indicates that the plant has a open cross-cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the ?Yes? will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross-cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Plants Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Page 1 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 LaSalle 1 LaSalle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Page 2 of 3

US NRC Reactor Oversight Process - Cross Cutting Issues Summary Point Beach 2 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 PI Summary Action Matrix Summary Reactor Oversight Process Last Modified: Jan 23, 2017 Page 3 of 3

NRC: Cross Cutting Issues Page 1 of 3 Home> Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Cross Cutting Issues Cross Cutting Issues The NRC evaluates whether a cross cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has an open cross cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Mid Cycle 2017 Human Problem Identification and Safety-Conscious Work Plants Performance Resolution Environment Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 10/19/2017

NRC: Cross Cutting Issues Page 2 of 3 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 LaSalle 1 LaSalle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 10/19/2017

NRC: Cross Cutting Issues Page 3 of 3 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 Current data as of: Aug 31, 2017 Page Last Reviewed/Updated Wednesday, August 09, 2017 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 10/19/2017

NRC: Cross Cutting Issues Home> Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Cross Cutting Issues Cross Cutting Issues The NRC evaluates whether a cross cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has an open cross cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

Mid Cycle 2017 Human Problem Identification and Safety-Conscious Work Plants Performance Resolution Environment Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 Page 1 of 3

NRC: Cross Cutting Issues Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 LaSalle 1 LaSalle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 Page 2 of 3

NRC: Cross Cutting Issues Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 Current data as of: Aug 31, 2017 Page Last Reviewed/Updated Wednesday, August 09, 2017 Page 3 of 3

NRC: Cross Cutting Issues Page 1 of 3 Home > Nuclear Reactors > Operating Reactors > Reactor Oversight Process > Cross Cutting Issues Cross Cutting Issues The NRC evaluates whether a cross cutting issue exists at each operating reactor twice a year; during the mid-cycle and end-of-cycle assessment meetings in accordance with IMC 0305. If the NRC determines that a cross cutting issue exists at a given plant, the resultant mid-cycle and end-of-cycle assessment letters summarize the specific cross cutting issue to include the necessary actions to resolve the issue. The next mid-cycle or annual assessment letter will either state that the issue has been satisfactorily resolved or summarize the agency's assessment and licensee's progress in addressing the issue.

"Yes" in the matrix below indicates that the plant has an open cross cutting issue in that area based on the most recent mid-cycle or end-of-cycle assessment. Clicking on the "Yes" will take you directly to the assessment letter that describes the issue. "Closed" in the matrix below indicates that the plant had a cross cutting issue closed based on the last assessment. Clicking on the "Closed" will take you directly to the assessment letter that describes the issue.

End of Cycle 2017 Human Problem Identification and Safety-Conscious Work Plants Performance Resolution Environment Arkansas Nuclear 1 Arkansas Nuclear 2 Beaver Valley 1 Beaver Valley 2 Braidwood 1 Braidwood 2 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Brunswick 1 Brunswick 2 Byron 1 Byron 2 Callaway Calvert Cliffs 1 Calvert Cliffs 2 Catawba 1 Catawba 2 Clinton Columbia Generating Station Comanche Peak 1 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 04/18/2018

NRC: Cross Cutting Issues Page 2 of 3 Comanche Peak 2 Cooper D.C. Cook 1 D.C. Cook 2 Davis-Besse Diablo Canyon 1 Diablo Canyon 2 Dresden 2 Dresden 3 Duane Arnold Farley 1 Farley 2 Fermi 2 FitzPatrick Ginna Grand Gulf 1 Harris 1 Hatch 1 Hatch 2 Hope Creek 1 Indian Point 2 Indian Point 3 LaSalle 1 LaSalle 2 Limerick 1 Limerick 2 McGuire 1 McGuire 2 Millstone 2 Millstone 3 Monticello Nine Mile Point 1 Nine Mile Point 2 North Anna 1 North Anna 2 Oconee 1 Oconee 2 Oconee 3 Oyster Creek Palisades Palo Verde 1 Palo Verde 2 Palo Verde 3 Peach Bottom 2 Peach Bottom 3 Perry 1 Pilgrim 1 Point Beach 1 Point Beach 2 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 04/18/2018

NRC: Cross Cutting Issues Page 3 of 3 Prairie Island 1 Prairie Island 2 Quad Cities 1 Quad Cities 2 River Bend 1 Robinson 2 Saint Lucie 1 Saint Lucie 2 Salem 1 Salem 2 Seabrook 1 Sequoyah 1 Sequoyah 2 South Texas 1 South Texas 2 Summer Surry 1 Surry 2 Susquehanna 1 Susquehanna 2 Three Mile Island 1 Turkey Point 3 Turkey Point 4 Vogtle 1 Vogtle 2 Waterford 3 Watts Bar 1 Watts Bar 2 Wolf Creek 1 Current data as of: Mar 05, 2018 Page Last Reviewed/Updated Wednesday, August 09, 2017 https://www.nrc.gov/reactors/operating/oversight/scci-summary.html 04/18/2018