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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
| author name = Maier J
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:REGULATOR)     <FORMATION DISTRIBUTION                     S       EM   (RIDS)
{{#Wiki_filter:REGULATOR)
DOC,DATE: 83/04/28 ACCESSION NBR:8305060404                                                NOTARIZED:           NO           DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear,Planti                         Uni,,'t   ir   Rochester     'G 05000244 AUTH, NAME             AUTHOR AFFILIATION MA IER J ~ E ~       "Rochester Gas 8 Electric
<FORMATION DISTRIBUTION S EM (RIDS)
                        'ECIPIENT      AFFILIATION    Corp'ECIP,NAME CRUTCHFIELD,D,           Operating Reactors Branch                 5 list II
"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:==
==SUBJECT:==
Forwards         of safety-related mason> y wal ls per "SEP .Topics II>>2,Ag III-2rIII",4.A 8 III"7.Bg "Str uctvr al Reanal ysis.
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 ~ "
Program '" Block 4talls ~
DISTRIBUTION CODE: A035S         COPIES RECEIVED;LTR             . ENCL               SIZEt,-
DISTRIBUTION CODE:
TITLE:   OR   Submittal:   SEP Topic NOTES:NRR/DL/SEP       icy,                                                                             05000244 RECIPIENT         COPIES          RECIPIENT                              )COPIES ID CODE/NAME        LTTR ENCL      ID CODE/NAME.                          L~TTR ENCL NRR   ORB5:BC   =01     3    3 INTERNAL: NRR/DL/DRAB           11     1     1     NRR/DL/SEPB                     12         '3      3 1    NRR/DS I/CSB                     07         1     1 EG  FILE      04      1     1     RGN1                                        1      1  ~
A035S COPIES RECEIVED;LTR.
EXTERNALS ACRS                 14           6     LPDR                            03          1     1 NRC PDR          02'    1     1     NTIS                             '5         1     1 NOTES!                                  1     1 TOTAL NUMBER OF COPIES         REQUIRED'TTR       21             ENCL     . 21
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
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1 1
RECIPIENT ID CODE/NAME.
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1 1
1 1
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EXTERNALS ACRS NRC PDR NOTES!
14 02' 6
1 1
1 1
LPDR NTIS 03'5 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED'TTR 21 ENCL
. 21


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                                                                                              /             'g YORK
/
  ~ llllllll/I/// lllllllllllll ROCHESTER GAS AND ELECTRIC CORPORATION                 ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER                                                                       YKLKPHONK Vice Preektenc                                                             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
'g YORK
~ llllllll/I///
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:==
SEP Topics II-2.A, III-2, III-4.A,     and   III-7.B "Structural Reanalysis Program" Block Walls
SEP Topics II-2.A, III-2, III-4.A, and III-7.B "Structural Reanalysis Program" Block Walls


==Dear Mr. Crutchfield:==
==Dear Mr. Crutchfield:==
 
In our April 22, 1983 submittal, "Structural Reanalysis Program for the Robert E. Ginna Nuclear Power Plant",
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:
RGSE provided our recommendations for structural elements which should be considered for upgrade to withstand tornado effects.
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.
The basis for selection of these structures is noted as those which are required to assure:
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.
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
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:
the capability to prevent accidents which could result in offsite exposure in excess of the dose guidelines of 10 CFR Part 100.
Bg0506040 4 0>000>44             830428
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:
Bg0506040 0>000>44 4 830428
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Control building walls which could damage vital equipment in the battery room, relay room, and air handling room;
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.
: 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
Very truly yours, J.
E. Maier


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                    'SAFETY-RELATED MASONRY WALLS NO ~     BUILDING                 'RGEcE DWG''AND IDENTIFICATION*"
'SAFETY-RELATED MASONRY WALLS NO ~
1       Control                   33013-971           1C 2      Control                  33013-971           2C 3      Control                  33013-971           3C 4      Control                  33013-971           4C 5      Control                  33013-971           5C 6      Control                  33013-971           6C 7      Control                  33013-972           1C 8      Cont.rol                  33013-972           2C 9      Control                  33013-972           3C 10      Control                  33013-972           4C ll 12 Control Control 33013-972 33013-972 5C 6C 13      Control                  33013-973           3C 14      Control                  33013-973           4C 15      Control                  33013-973           5C 16      Auxiliary                33013-973           16A 17      Auxiliary                33013-973           17A 18      Containment              33013-971           1M 19      Containment              33013-971           2M 20      Containment              33013-971           3M 21      Containment              33013-972           1M 22      Containment              33013-973           1M 23      Containment              33013-973           2M 24      Intermediate              33013-972           1I 25      Intermediate              33013-972           2I 26      Intermediate              33013-972           3I 27      Intermediate              33013-972           4I 28      Intermediate              33013-972           5I 29      Intermediate              33013-972           6I 30      Intermediate              33013-972           7I 31      Intermediate              33013-972           8I 32      Intermediate              33013-972           9I 33      Intermediate              33013-972           10I 34      Intermediate              33013-972           11I 35 36 Intermediate Intermediate 33013-973 33013-973 Part of 11I(P) lI 37      Intermediate              33013-973          9I(P)
BUILDING
*Referenced drawings were submitted as part     of the I.E. Bulletin 80-11 Response submitted November 4, 1980.
'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


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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

'3 3

1 1

1 1

~

EXTERNALS ACRS NRC PDR NOTES!

14 02' 6

1 1

1 1

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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*"

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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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