ML17095A620: Difference between revisions

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| issue date = 06/30/1992
| issue date = 06/30/1992
| title = Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,To Enable NRC to Assess Compliance w/10CFR50.60 & 10CFR50.61 & Fracture Toughness & Matl Surveillance Requirements for RCS
| title = Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,To Enable NRC to Assess Compliance w/10CFR50.60 & 10CFR50.61 & Fracture Toughness & Matl Surveillance Requirements for RCS
| author name = MILTENBERGER S
| author name = Miltenberger S
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Hmn t.Ndtoaborytr JUNS 0 H3<NLR N920$2 United States Nuclear Regulatory Commission Document Control Rooa Washington, DC 20555 Gentlemen:
{{#Wiki_filter:Hmn t. Ndtoaborytr JUNS 0 H3<
RESPONSE TO GENERIC LETTER 92-02~REVISION 2 REACTOR VESSEL STRUCTURE INTEGRITY~
NLR N920$ 2 United States Nuclear Regulatory Commission Document Control Rooa Washington,     DC 20555 Gentlemen:
10CFR50.5i(f)
RESPONSE TO GENERIC LETTER 92-02~ REVISION 2 REACTOR VESSEL STRUCTURE INTEGRITY~ 10CFR50.5i(f)
SALEM CENEBATZNC STATION UNIT NOS~1 AND 2 FACILITY OPERATING LICENSE NPSI DPR 70 AND DPR 75 DOCKET NOS~50 272 AND 50 322 I'eneric Letter 92<<01, Revision 1 requests PSELC to submit information to enable the NRC to assess compliance vith lOCFR50.60 and 10CFRS0.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Baundary set forth in 10CFR50, Appendix G and H.The Salem Generating Station.Unit Nos.1 and 2 responses to Generic Letter 92-01, Revision 1 are provided in Attachment l and 2, respectively.
SALEM CENEBATZNC STATION UNIT NOS ~ 1 AND 2 FACILITY OPERATING LICENSE NPSI DPR 70 AND DPR 75 DOCKET NOS ~ 50 272 AND 50 322 Letter 92<<01, Revision 1 requests PSELC to submit I'eneric information to enable the NRC to assess compliance vith 10CFR50.60 and 10CFRS0.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Baundary set forth in 10CFR50, Appendix G and H.
The Salem Generating Station .Unit Nos. 1 and 2 responses to Generic Letter 92-01, Revision 1 are provided in Attachment l and 2, respectively.
Please do not hesitate to contact us it there are any questions regarding this submittal.
Please do not hesitate to contact us it there are any questions regarding this submittal.
Sincerely, Attachments Affidavit 0 1 t NLR N92081 Th8LC 12 ShLKK VNLT 2 The follo<LnQ information Mae taken from Salem gnlte 1 and 2 Reactor veaeel Meld Data CR Inc., Deelgn Input FLle T01.5 020 November 1985, and MChp 8824, Ntla co.5alem Unit Ho.2 Reactor Ve eel RadLatlon surveillance Program, january 1979.ggggh~c Meld Curve Ll lance Katerlal Meldment made from Lntermedlate ahel1 platee 84712 1 and 84712-2}~~c 132SX~>I Lnde 1092, l,ot Ho.3833~nd LLnde 1092, Lot.Ho.3774 m'dna F10 1.27.DL7.011 5L.29~71 Ko.45.22.015 Tem 100 100-100 50 50<<%0 40 40 40 100 100 100 210 210 210 ther ft<<lbe 4.5 11 6 11 4 35'5 48oS 72 6$AS 71 SOTS 80.5 86 96e5 106 AS 112 111.5 111~5 l shear 2 6 15 18 20 29 52 52 62$9 55 79 100 90 100 98 100 100 Hil~Lateral ta 1 2o5 1 1~5 1'1 27 42 36$0 56 44 62 81 74~5 80 82 8C 8%~5 Tem i t Dro Met hta terformed b Ct NDT<<40 t RTHDT<<20~t VSE 111 ft"lba-1150't for 40 houre}}eaMSTatmee 18 RDVioion 0
Sincerely, Attachments Affidavit


ATTACHHENT 4 (Reference 4)DIABLO CANYON POWER PLANT UNIT I Intermediate Shell Longitudinal Welds 2-442 A, B, and C Lower Shell Longitudinal Welds 3-442 A, B, and C 6223S/85K}}
0 1
t
 
NLR N92081 Th8LC 12 ShLKK VNLT 2 The follo<LnQ      information Mae taken from Salem gnlte 1 and 2 Reactor veaeel Meld Data CR        Inc., Deelgn Input FLle T01.5 020 November 1985, and MChp 8824, Ntla  co. 5alem Unit Ho. 2 Reactor Ve eel RadLatlon surveillance Program, january 1979.
ggggh~c          Meld Curve Lllance Katerlal Meldment made from Lntermedlate
                                                            }~~c            132SX ahel1 platee 84712 1 and 84712-2
                                                            ~>nd ILLnde
                                                                ~
Lnde 1092, 1092, l,ot  Ho. 3833 Lot. Ho. 3774 m        'dna 5L                    Ko F10          1.27      .DL7      .011        .29        ~ 71      .45      .22        .015 Tem                    ther      ft<<lbe            l  shear          Hil~ Lateral ta 100                      4.5                        2                      1 100                      11                          6                      2o5
        -100                        6                        15                      1 50                      11                        18                      1~5 50                      4                        20                    1'1
          <<%0                      35'5                      29                    27 48oS                      52                    42 72                        52                    36 6$ AS                      62                    $0 40                      71                        $9                    56 40                      SOTS                      55                    44 40                      80.5                      79                    62 100                      86                        100                    81 100                      96e5                      90                    74 ~ 5 100                    106 AS                      100                    80 210                      112                        98                    82 210                    111. 5                    100                    8C 210                    111 ~ 5                    100                    8% ~ 5 Tem  i      t      Dro  Met hta          NDT                  RTHDT                VSE terformed    b  Ct                <<40  t              <<20~ t        111    ft"lba
                                          }}eaMSTatmee
-1150't for 40 houre 18 RDVioion      0
 
ATTACHHENT 4 (Reference 4)
DIABLO CANYON POWER PLANT UNIT I Intermediate Shell Longitudinal Welds 2-442 A, B, and C Lower Shell Longitudinal Welds 3-442 A, B, and C 6223S/85K}}

Latest revision as of 11:58, 10 November 2019

Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,To Enable NRC to Assess Compliance w/10CFR50.60 & 10CFR50.61 & Fracture Toughness & Matl Surveillance Requirements for RCS
ML17095A620
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/30/1992
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17095A621 List:
References
GL-92-01, GL-92-1, NLR-N92081, NUDOCS 9207070030
Download: ML17095A620 (6)
v • d • e


Text

Hmn t. Ndtoaborytr JUNS 0 H3<

NLR N920$ 2 United States Nuclear Regulatory Commission Document Control Rooa Washington, DC 20555 Gentlemen:

RESPONSE TO GENERIC LETTER 92-02~ REVISION 2 REACTOR VESSEL STRUCTURE INTEGRITY~ 10CFR50.5i(f)

SALEM CENEBATZNC STATION UNIT NOS ~ 1 AND 2 FACILITY OPERATING LICENSE NPSI DPR 70 AND DPR 75 DOCKET NOS ~ 50 272 AND 50 322 Letter 92<<01, Revision 1 requests PSELC to submit I'eneric information to enable the NRC to assess compliance vith 10CFR50.60 and 10CFRS0.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Baundary set forth in 10CFR50, Appendix G and H.

The Salem Generating Station .Unit Nos. 1 and 2 responses to Generic Letter 92-01, Revision 1 are provided in Attachment l and 2, respectively.

Please do not hesitate to contact us it there are any questions regarding this submittal.

Sincerely, Attachments Affidavit

0 1

t

NLR N92081 Th8LC 12 ShLKK VNLT 2 The follo<LnQ information Mae taken from Salem gnlte 1 and 2 Reactor veaeel Meld Data CR Inc., Deelgn Input FLle T01.5 020 November 1985, and MChp 8824, Ntla co. 5alem Unit Ho. 2 Reactor Ve eel RadLatlon surveillance Program, january 1979.

ggggh~c Meld Curve Lllance Katerlal Meldment made from Lntermedlate

}~~c 132SX ahel1 platee 84712 1 and 84712-2

~>nd ILLnde

~

Lnde 1092, 1092, l,ot Ho. 3833 Lot. Ho. 3774 m 'dna 5L Ko F10 1.27 .DL7 .011 .29 ~ 71 .45 .22 .015 Tem ther ft<<lbe l shear Hil~ Lateral ta 100 4.5 2 1 100 11 6 2o5

-100 6 15 1 50 11 18 1~5 50 4 20 1'1

<<%0 35'5 29 27 48oS 52 42 72 52 36 6$ AS 62 $0 40 71 $9 56 40 SOTS 55 44 40 80.5 79 62 100 86 100 81 100 96e5 90 74 ~ 5 100 106 AS 100 80 210 112 98 82 210 111. 5 100 8C 210 111 ~ 5 100 8% ~ 5 Tem i t Dro Met hta NDT RTHDT VSE terformed b Ct <<40 t <<20~ t 111 ft"lbaeaMSTatmee -1150't for 40 houre 18 RDVioion 0

ATTACHHENT 4 (Reference 4) DIABLO CANYON POWER PLANT UNIT I Intermediate Shell Longitudinal Welds 2-442 A, B, and C Lower Shell Longitudinal Welds 3-442 A, B, and C 6223S/85K}}

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