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| number = ML17256A669
| number = ML17256A669
| issue date = 04/28/1983
| issue date = 04/28/1983
| title = Forwards List of safety-related Masonry Walls Per SEP Topics II-2.A,III-2,III-4.A & III-7.B, Structural Reanalysis Program - Block Walls.
| title = Forwards List of safety-related Masonry Walls Per SEP Topics II-2.A,III-2,III-4.A & III-7.B, Structural Reanalysis Program - Block Walls
| author name = MAIER J E
| author name = Maier J
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name = CRUTCHFIELD D
| addressee name = Crutchfield D
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000244
| docket = 05000244
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:REGULATOR)
{{#Wiki_filter:REGULATOR)
<FORMATION DISTRIBUTION SEM(RIDS)"ACCESSION NBR:8305060404 DOC,DATE:
<FORMATION DISTRIBUTION S EM (RIDS)
83/04/28NOTARIZED:
"ACCESSION NBR:8305060404 DOC,DATE: 83/04/28 NOTARIZED:
NODOCKETFACIL:50-244 RobertEmmetGinnaNuclear,Planti Uni,,'tirRochester
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear,Planti Uni,,'t ir Rochester
'G05000244AUTH,NAMEAUTHORAFFILIATION MAIERJ~E~"Rochester Gas8ElectricCorp'ECIP,NAME
'G 05000244 AUTH,NAME AUTHOR AFFILIATION MAIER J ~ E ~
'ECIPIENT AFFILIATION CRUTCHFIELD,D, Operating ReactorsBranch5II
"Rochester Gas 8 Electric Corp'ECIP,NAME
'ECIPIENT AFFILIATION CRUTCHFIELD,D, Operating Reactors Branch 5
II


==SUBJECT:==
==SUBJECT:==
Forwardslistofsafety-related mason>ywallsper"SEP.TopicsII>>2,AgIII-2rIII",4.A8III"7.Bg"StructvralReanalysis.Program'"Block4talls~"DISTRIBUTION CODE:A035SCOPIESRECEIVED;LTR
Forwards list of safety-related mason> y wal ls per "SEP.Topics II>>2,AgIII-2rIII",4.A 8 III"7.Bg "Str uctvr al Reanal ysis.
.ENCLSIZEt,-TITLE:ORSubmittal:
Program '" Block 4talls ~
SEPTopicNOTES:NRR/DL/SEP icy,05000244EGFILE04RECIPIENT IDCODE/NAME NRRORB5:BC=01INTERNAL:
DISTRIBUTION CODE:
NRR/DL/DRAB 11COPIESLTTRENCL3311111RECIPIENT IDCODE/NAME.
A035S COPIES RECEIVED;LTR.
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OR Submittal:
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SEP Topic NOTES:NRR/DL/SEP icy, 05000244 EG FILE 04 RECIPIENT ID CODE/NAME NRR ORB5:BC
lllllllllllll ROCHESTER GASANDELECTRICCORPORATION
=01 INTERNAL: NRR/DL/DRAB 11 COPIES LTTR ENCL 3
~89EASTAVENUE,ROCHESTER, N.Y.14649JOHNE.MAIERVicePreektenc YKLKPHONK ARCACOOKYle546.2700april28,1983DirectorofNuclearReactorRegulation, Attention:
3 1
Mr.DennisM.Crutchfield, ChiefOperating ReactorsBranchNo.5U.S.NuclearRegulatory Commission Washington, D.C.20555
1 1
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lllllllllllll ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vice Preektenc YKLKPHONK ARCA COOK Yle 546.2700 april 28, 1983 Director of Nuclear Reactor Regulation, Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555


==SUBJECT:==
==SUBJECT:==
SEPTopicsII-2.A,III-2,III-4.A,andIII-7.B"Structural Reanalysis Program"-BlockWalls
SEP Topics II-2.A, III-2, III-4.A, and III-7.B "Structural Reanalysis Program" Block Walls
 
==Dear Mr. Crutchfield:==
In our April 22, 1983 submittal, "Structural Reanalysis Program for the Robert E. Ginna Nuclear Power Plant",
RGSE provided our recommendations for structural elements which should be considered for upgrade to withstand tornado effects.
The basis for selection of these structures is noted as those which are required to assure:
0 the integrity of the reactor coolant pressure
: boundary, the capability to shut the reactor down and maintain it in a safe shutdown condition, and o
the capability to prevent accidents which could result in offsite exposure in excess of the dose guidelines of 10 CFR Part 100.
Based upon the safe shutdown scenario discussed in Section 3.5 of the April 22 report, the attached list indicates those walls that RGSE currently considers safety-related and whose integrity must be maintained to assure safe shutdown.
Specifically, RGSE stated that the block walls whose failure could damage required main steam and feedwater line components in the intermediate
: building, and those which would affect the spent fuel assemblies, should be considered for upgrading.
No other block walls potentially exposed to tornado effects are considered as safety-related.
~ Several other block walls are located such that tornadoes could not cause. any structural
: damage, and thus were not evaluated in the April 22 report.
However, using the same safety design
: basis, the following additional walls are considered safety-related:
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Control building walls which could damage vital equipment in the battery room, relay room, and air handling room;
: and, Walls which are internal to containment, as listed in our response to ICE. Bulletin 80-11, submitted by letter of November 4, 1980.
Very truly yours, J.
E. Maier
 
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==DearMr.Crutchfield:==
'SAFETY-RELATED MASONRY WALLS NO ~
BUILDING
'RGEcE DWG''AND IDENTIFICATION*"
1 2
3 4
5 6
7 8
9 10ll 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 Control Control Control Control Control Control Control Cont.rol Control Control Control Control Control Control Control Auxiliary Auxiliary Containment Containment Containment Containment Containment Containment Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate 33013-971 33013-971 33013-971 33013-971 33013-971 33013-971 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-973 33013-973 33013-973 33013-973 33013-973 33013-971 33013-971 33013-971 33013-972 33013-973 33013-973 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-973 33013-973 33013-973 1C 2C 3C 4C 5C 6C 1C 2C 3C 4C 5C 6C 3C 4C 5C 16A 17A 1M 2M 3M 1M 1M 2M 1I 2I 3I 4I 5I 6I 7I 8I 9I 10I 11I Part of lI 11I(P) 9I(P)
*Referenced drawings were submitted as part of the 80-11 Response submitted November 4, 1980.
I.E. Bulletin


InourApril22,1983submittal, "Structural Reanalysis ProgramfortheRobertE.GinnaNuclearPowerPlant",RGSEprovidedourrecommendations forstructural elementswhichshouldbeconsidered forupgradetowithstand tornadoeffects.Thebasisforselection ofthesestructures isnotedasthosewhicharerequiredtoassure:0theintegrity ofthereactorcoolantpressureboundary, thecapability toshutthereactordownandmaintainitinasafeshutdowncondition, andothecapability topreventaccidents whichcouldresultinoffsiteexposureinexcessofthedoseguidelines of10CFRPart100.Baseduponthesafeshutdownscenariodiscussed inSection3.5oftheApril22report,theattachedlistindicates thosewallsthatRGSEcurrently considers safety-related andwhoseintegrity mustbemaintained toassuresafeshutdown.
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Specifically, RGSEstatedthattheblockwallswhosefailurecoulddamagerequiredmainsteamandfeedwater linecomponents intheintermediate
E
: building, andthosewhichwouldaffectthespentfuelassemblies, shouldbeconsidered forupgrading.
/
Nootherblockwallspotentially exposedtotornadoeffectsareconsidered assafety-related.
e-E E
~Severalotherblockwallsarelocatedsuchthattornadoes couldnotcause.anystructural damage,andthuswerenotevaluated intheApril22report.However,usingthesamesafetydesignbasis,thefollowing additional wallsareconsidered safety-related:
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Controlbuildingwallswhichcoulddamagevitalequipment inthebatteryroom,relayroom,andairhandlingroom;and,Wallswhichareinternaltocontainment, aslistedinourresponsetoICE.Bulletin80-11,submitted byletterofNovember4,1980.Verytrulyyours,J.E.Maier r~oxa"p,4C'lI0~f*'*Pl
'SAFETY-RELATED MASONRYWALLSNO~BUILDING'RGEcEDWG''ANDIDENTIFICATION*"
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Latest revision as of 11:00, 8 January 2025

Forwards List of safety-related Masonry Walls Per SEP Topics II-2.A,III-2,III-4.A & III-7.B, Structural Reanalysis Program - Block Walls
ML17256A669
Person / Time
Site: Ginna 
Issue date: 04/28/1983
From: Maier J
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-02-02.A, TASK-03-02, TASK-03-04.A, TASK-03-07.B, TASK-2-2.A, TASK-3-2, TASK-3-4.A, TASK-3-7.B, TASK-RR IEB-80-11, NUDOCS 8305060404
Download: ML17256A669 (8)
v • d • e


Text

REGULATOR)

<FORMATION DISTRIBUTION S EM (RIDS)

"ACCESSION NBR:8305060404 DOC,DATE: 83/04/28 NOTARIZED:

NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear,Planti Uni,,'t ir Rochester

'G 05000244 AUTH,NAME AUTHOR AFFILIATION MAIER J ~ E ~

"Rochester Gas 8 Electric Corp'ECIP,NAME

'ECIPIENT AFFILIATION CRUTCHFIELD,D, Operating Reactors Branch 5

II

SUBJECT:

Forwards list of safety-related mason> y wal ls per "SEP.Topics II>>2,AgIII-2rIII",4.A 8 III"7.Bg "Str uctvr al Reanal ysis.

Program '" Block 4talls ~

DISTRIBUTION CODE:

A035S COPIES RECEIVED;LTR.

ENCL SIZEt,-

TITLE:

OR Submittal:

SEP Topic NOTES:NRR/DL/SEP icy, 05000244 EG FILE 04 RECIPIENT ID CODE/NAME NRR ORB5:BC

=01 INTERNAL: NRR/DL/DRAB 11 COPIES LTTR ENCL 3

3 1

1 1

1 1

RECIPIENT ID CODE/NAME.

NRR/DL/SEPB 12 NRR/DS I/CSB 07 RGN1

)COPIES L~TTR ENCL

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1 1

1 1

~

EXTERNALS ACRS NRC PDR NOTES!

14 02' 6

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LPDR NTIS 03'5 1

1 1

1 TOTAL NUMBER OF COPIES REQUIRED'TTR 21 ENCL

. 21

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Control building walls which could damage vital equipment in the battery room, relay room, and air handling room;

and, Walls which are internal to containment, as listed in our response to ICE.Bulletin 80-11, submitted by letter of November 4, 1980.

Very truly yours, J.

E. Maier

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'SAFETY-RELATED MASONRY WALLS NO ~

BUILDING

'RGEcE DWGAND IDENTIFICATION*"

1 2

3 4

5 6

7 8

9 10ll 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 Control Control Control Control Control Control Control Cont.rol Control Control Control Control Control Control Control Auxiliary Auxiliary Containment Containment Containment Containment Containment Containment Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate Intermediate 33013-971 33013-971 33013-971 33013-971 33013-971 33013-971 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-973 33013-973 33013-973 33013-973 33013-973 33013-971 33013-971 33013-971 33013-972 33013-973 33013-973 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-972 33013-973 33013-973 33013-973 1C 2C 3C 4C 5C 6C 1C 2C 3C 4C 5C 6C 3C 4C 5C 16A 17A 1M 2M 3M 1M 1M 2M 1I 2I 3I 4I 5I 6I 7I 8I 9I 10I 11I Part of lI 11I(P) 9I(P)

  • Referenced drawings were submitted as part of the 80-11 Response submitted November 4, 1980.

I.E. Bulletin

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