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B$ heron Ntauben EThrem Docket No.: 50-244 MEMOPANDUM FOR:
Gus C. Lainas, Assistant Director for Operating Reactors, Division of Licensing FROMr R. Wayne Houston, Assistant Director for Reactor Safety, Division of Systems Integration SUB.1ECT:
SAFETY IVALUATION FOR R.E. GINNA NUCLEAR POWER PLANT (1) Steam Generator Tube Rupture Thermal-Hydraulic f
Analysis (TACS49344)
(2) Reactor Coolant Pump Alternate Tria #iteria and Restart Criteria (TACS 49345)
(3) Stagnant Flow Scenarios and Pressurized Themal Shock (TACS 49351)
Plant Name:
R. E. Ginna Nuclear Power Plant, Unit 1 Docket No.:
50-244 TAC Nos.:
49344, 49345 and 49351 Licensing Stage:
OR Ro4uested Date:
July 31, 1983
. Review firarch:
Reactor Systems i1 ranch Review Status:
Completed i
Project Manager:
G. Dick The Reactor Systems Branch has completed the evaluation of the subject t
TACS for the R.E. Ginr.a Huclear Pcwer Plant, as provided in the licensee response to HUREG-0916 of November 22, 1982. These Safety Evaluation l
are provided in the enclosures.
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(y concerns'ound the material provided to be acceptable in add We havt identified in NUREG-0916.
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R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration U
Enclosures:
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F. Miraglia D. Crutchfield i
I.J G. Dick tv i c:
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BSheron NLauben EThrom MEMORANDfH FOR Gus C. Laines, Assistant Director for Opera ng Reactors, Division of Licensing FROM:
R. Wayne Houston, Assistant Director f Reactor Safety,DivisionofSystemsIntegrafon
SUBJECT:
SAFETY CYALVATIONS FOR R.E. GINNA JCLEAR POWER PLANT (1) Steam Generator Tube Rupture hernal Hydraulic Analysis (TACS49344)
(2) Reactor Coolant Pump Alte late Trip Criteria and Restart Criteria (T S49345)
(3) Stagnant Flow Scenario. and Pressurized Themal Shock (TACS 51)
The Reactor Systems Branch has completed tfe evaluation of the subject TACS for the R.E. Ginna Nuclear Power P1 nt, as provided in the licensee response to NUREG-0916 of November 22 1982. These Safety Evaluation are provided in the enclosures.
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We have found the material pro ided to the acceptable in addressing the concerns identified in NUREG-4916.
R. Wayne Houston, Assistant Director for Reactor Safety Divit. ion of Systems Integration
Enclosures:
As stated cc:
F. Miragl 'a D. Crute field G. Dic CONTACT:
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