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| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 5
| page count = 5
| project = TAC:62971
| stage = Approval
}}
}}


=Text=
=Text=
{{#Wiki_filter:b -
{{#Wiki_filter:b August 1,1988 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens Senior Vice President (RBNG)
        '.    ..                      August 1,1988 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens Senior Vice President (RBNG)
Post Office Box 220 St. Francisville, Louisiana 70775
Post Office Box 220 St. Francisville, Louisiana 70775


==Dear Mr. Deddens:==
==Dear Mr. Deddens:==
==SUBJECT:==
==SUBJECT:==
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
RIVER BEND STATION, UNIT NO. 1 (TAC N0. 62971)
RIVER BEND STATION, UNIT NO. 1 (TAC N0. 62971)
By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inscryice inspection program. The staff concluded that your program was acceptable and incompliancewiththerequirementsof10CFR50.55a(g)(4).                                     ,
By {{letter dated|date=October 20, 1987|text=letter dated October 20, 1987}}, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inscryice inspection program. The staff concluded that your program was acceptable and incompliancewiththerequirementsof10CFR50.55a(g)(4).
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that           '
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were determined to be impractical to perfonn at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its contractor, Idaho National Engineering Laboratory, met with GSU representatives i
were determined to be impractical to perfonn at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination             -
on February 17-18, 1988,at the River Bend Station to review the requests and the examination procedures for the reactor pressure vessel.
of Category B-A welds in the reactor pressure vessel. GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its           !
Based on its review, the staff concurs with the determination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.
contractor, Idaho National Engineering Laboratory, met with GSU representatives         i on February 17-18, 1988,at the River Bend Station to review the requests and           .
The requested relief from the ASME Code requireirents for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
the examination procedures for the reactor pressure vessel.
Sincerely, Josek(Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Based on its review, the staff concurs with the determination made by GSU that         .
ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.       The requested relief from the ASME Code requireirents for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
Sincerely, Josek(Calvo, Director Project Directorate - IV                     ,
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation


==Enclosure:==
==Enclosure:==
As stated cc w/ enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION Docket. File.    '
See next page DISTRIBUTION NRC & Local PDRs PD4 Reading L. Rubenstein Docket. File.
NRC & Local PDRs           PD4 Reading   L. Rubenstein J. Calvo               W. Paulson                 P. Noonan     F Litton                 :
J. Calvo W. Paulson P. Noonan F Litton E. Jordan Partlow ACRS (10)
E. Jordan             Partlow                   ACRS (10)       Plant File     OGC-WFN   i 1
Plant File OGC-WFN PDIV:D{l%
    *See previous concurrences:                                                               !
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4 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. -Deddens SeniorVicePresident(RBNG)
          .    ..                                                                                                                              1 4
Docket No. 50-458 Gulf States Utilities                                                                                                                       l ATTN: Mr. James C. -Deddens                                                                                                                 '
l SeniorVicePresident(RBNG)
Post Office Box 220 St. Francisville, Louisiana 70775
Post Office Box 220 St. Francisville, Louisiana 70775


==Dear Mr. Deddens:==
==Dear Mr. Deddens:==
==SUBJECT:==
==SUBJECT:==
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
RIVER BEND STATION,-UNIT NO. 1 (TAC N0. 629/1)                                                                                   l By letter dated October 20, 1987, th.. NRC staff forwarded                                     safety evaluation regarding the River Bend Station first ten-ye                                 inservice inspection program. The staff concluded that your pro am was acceptable and in compliance with the requirements of 10 CFR 50.55a                             (4).
RIVER BEND STATION,-UNIT NO. 1 (TAC N0. 629/1) l By {{letter dated|date=October 20, 1987|text=letter dated October 20, 1987}}, th.. NRC staff forwarded safety evaluation regarding the River Bend Station first ten-ye inservice inspection program. The staff concluded that your pro am was acceptable and in compliance with the requirements of 10 CFR 50.55a (4).
Gulf States Utilities (GSU) identified ASME Secti i 11 Code requirements that were determined to be impractical to perform at iver Bend Station. The NRC's October 20, 1987 Safety Evaluation did not gra                           relief for the examination                                         '
Gulf States Utilities (GSU) identified ASME Secti i 11 Code requirements that were determined to be impractical to perform at iver Bend Station. The NRC's October 20, 1987 Safety Evaluation did not gra relief for the examination of Category B-A welds in the reactor pressur vessel.
of Category B-A welds in the reactor pressur vessel. GSU requested reconsideration of these relief requests.                       cordingly, the NRC staff and its                                           j contractor, Idaho National Engineering La ratory, met with GSU representatives                                                             !
GSU requested reconsideration of these relief requests.
on February 17-18, 1988 at the River Ben Station to review the requests and                                                                 1 the examination procedures for the rea or pressure vessel.
cordingly, the NRC staff and its j
1 Based on its review, the staff concu s with the determination made by GSU that                                                             i ASME Code requirements for Category /B-A welds in the reactor pressure vessel                                                               !
contractor, Idaho National Engineering La ratory, met with GSU representatives on February 17-18, 1988 at the River Ben Station to review the requests and 1
are impractical to perform at the/ River Bend Station, Unit 1. The staff's                                                                 '
the examination procedures for the rea or pressure vessel.
supplemental Safety Evaluation 14 enclosed.
Based on its review, the staff concu s with the determination made by GSU that i
1 Sincerely,                                                                       !
ASME Code requirements for Category /B-A welds in the reactor pressure vessel are impractical to perform at the/ River Bend Station, Unit 1.
Jose A. Calvo, Director                                                         '
The staff's supplemental Safety Evaluation 14 enclosed.
Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Sincerely, Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
/


==Enclosure:==
==Enclosure:==
 
As stated
As stated         /
/
                          /
/
                      /
cc w/enclosur_e':
cc w/enclosur_e':
See next page
See next page
                /
/
DISTRIBUTION Docliet File f            NRC & Local PDRs                         PD4 Reading               L. Rubenstein J. Calyo               W. Paulson                               P. Noonan                 F. Litton E. Jo dan             Partlow                                 ACRS (10)                 Plant File                       OGC-WFN 1
DISTRIBUTION Docliet File NRC & Local PDRs PD4 Reading L. Rubenstein f
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1
1 August 1,1988 l
    .          .      ..                                        August 1,1988 l
Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)
Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)
Post Office Box 220 St. Francisville, Louisiana 70775
Post Office Box 220 St. Francisville, Louisiana 70775


==Dear Mr. Deddens:==
==Dear Mr. Deddens:==
==SUBJECT:==
==SUBJECT:==
FIPST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
FIPST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
RIVER BEND STATION, UNIT N0. 1 (TAC NO. 62971)
RIVER BEND STATION, UNIT N0. 1 (TAC NO. 62971)
By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).
By {{letter dated|date=October 20, 1987|text=letter dated October 20, 1987}}, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were determined to be impractical to perform at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its contractor, Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the examination procedures for the reactor pressure vessel.
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were determined to be impractical to perform at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel.
Based on its review, the staff concurs with the determination made by GSU that                                                     l ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1. The requested relief from the ASME Code requirerrents for the examination of Category B-A                                                         l welds in the reactor pressure vessel is granted pursuant to 10 CFR Section                                                         1 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its contractor, Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the examination procedures for the reactor pressure vessel.
Sincerely, l
Based on its review, the staff concurs with the determination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.
Jose k( Calvo, Director Project Directorate - IV Division of Reactor Projects - III,                                 l IV, V and Special Projects                                   i Office of Nuclear Reactor Regulation                                 l As stated cc w/ enclosure:
The requested relief from the ASME Code requirerrents for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
See next page DISTRIBUTION Docket File                   NRC & Local PDRs                           PD4 Reading     L. Rubenstein J. Calvo                     W. Paulson                                 P. Noonan       F. Litton E. Jordan                     Partlow                                   ACRS (10)       Plant File                     OGC-WFN
Sincerely, Jose k( Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation As stated cc w/ enclosure:
        *See previous concurrences:
See next page DISTRIBUTION Docket File NRC & Local PDRs PD4 Reading L. Rubenstein J. Calvo W. Paulson P. Noonan F. Litton E. Jordan Partlow ACRS (10)
PDIV:LA*                 PDIV:PM*                     C                 PDIV:D PNoenan                 Paulson:kb                                     JCalvo 07/12/88                 07/11/88                   0   /88           @7 /88
Plant File OGC-WFN
                                                                                  &I fif
*See previous concurrences:
PDIV:LA*
PDIV:PM*
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I
#o UNITED STATES g
                                          '*%#o     ..
I NUCLEAR REGULATORY COMMISSION g
g                                        UNITED STATES I
{
g                    NUCLEAR REGULATORY COMMISSION
wAsMNGTON, D. C. 20665
{                                               wAsMNGTON, D. C. 20665 August 1,1988
**g.....,/
                                    **g.....,/
August 1,1988 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)
Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens                                                                                                                             l SeniorVicePresident(RBNG)                                                                                                                     '
Post Office Box 220 St. Francisville, Louisiana 70775
Post Office Box 220 St. Francisville, Louisiana 70775


==Dear Mr. Deddens:==
==Dear Mr. Deddens:==
==SUBJECT:==
==SUBJECT:==
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -
RIVER BEND STATION, UNIT NO. 1 (TAC NO. 62971)
RIVER BEND STATION, UNIT NO. 1 (TAC NO. 62971)
By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).
By {{letter dated|date=October 20, 1987|text=letter dated October 20, 1987}}, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were detemined to be impractical to perfom at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requesteo reconsideration of these relief requests. Accordingly, the NRC staff and its contractor Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the exarr.ination procedures for the reactor pressure vessel.
Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were detemined to be impractical to perfom at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requesteo reconsideration of these relief requests. Accordingly, the NRC staff and its contractor Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the exarr.ination procedures for the reactor pressure vessel.
Based on its review, the staff concurs with the detemination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1. The requested                                                                           !
Based on its review, the staff concurs with the detemination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.
relief from the ASME Code requirements for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
The requested relief from the ASME Code requirements for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.
Sincerely, g, bb Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Sincerely, g, bb Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation


==Enclosure:==
==Enclosure:==
As stated cc w/ enclosure:
As stated cc w/ enclosure:
See next page
See next page
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Mr. James C. Deddens Gulf States Utilities Company           River Bend Nuclear Plant cc:
Mr. James C. Deddens Gulf States Utilities Company River Bend Nuclear Plant cc:
Troy B. Conner, Jr. , Esq.               Mr. J. E. Booker Conner and Wetterhahn                   Manager-River Bend Oversight 1747 Pennsylvania Avenue, NW             P. O. Box 2951 Washington, D.C. 20006                   Beaumont, TX 77704 Mr. Les England                         Mr. William H. Spell, Administrator Director - Nuclear Licensing             Nuclear Energy Division Gulf States Utilities Company           Office of Environmental Affairs P. O. Box 220                           P. O. Box 14690 St. Francisville, LA 70775               Baton Rouge, Louisiana 70898 Richard M. Troy, Jr. , Esq.
Troy B. Conner, Jr., Esq.
Assistant Attorney General in Charge     Mr. J. David McNeill, Ill State of Louisiana Department of Justice William G. Davis, Esq.
Mr. J. E. Booker Conner and Wetterhahn Manager-River Bend Oversight 1747 Pennsylvania Avenue, NW P. O. Box 2951 Washington, D.C.
234 Loyola Avenue                       Department of Justice New Orleans, Louisiana 70112             Attorney General's Office 7434 Perkins Road Resident Inspector                       Baton Rouge, Louisiana 70808 P. O. Box 1051 St. Francisv111e, Louisiana 70775       H. Anne Plettinger 3456 Villa Rose Drive Gretchen R. Rothschild-Reinike           Baton Rouge, Louisiana 70806 Louisianians for Safe Energy, Inc.
20006 Beaumont, TX 77704 Mr. Les England Mr. William H. Spell, Administrator Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Company Office of Environmental Affairs P. O. Box 220 P. O. Box 14690 St. Francisville, LA 70775 Baton Rouge, Louisiana 70898 Richard M. Troy, Jr., Esq.
2108 Broadway Street New Orleans, Louisiana 70118-5462       President of West Feliciana Police Jury Regional Administrator, Region IV       P. O. Box 1921 U.S. Nuclear Regulatory Commission       St. Francisville, Louisiana 70775 Office of Executive Director for Operations                         Mr. Frank J. Uddo 611 Ryan Plaza Drive, Suite 1000         Uddo & Porter Arlington, Texas 76011                   6305 Elysian Fields Avenue Suite 400 Philip G. Harris                         New Orleans, Louisiana 70122 Cajun Electric Power Coop. Inc.
Assistant Attorney General in Charge Mr. J. David McNeill, Ill State of Louisiana Department of Justice William G. Davis, Esq.
234 Loyola Avenue Department of Justice New Orleans, Louisiana 70112 Attorney General's Office 7434 Perkins Road Resident Inspector Baton Rouge, Louisiana 70808 P. O. Box 1051 St. Francisv111e, Louisiana 70775 H. Anne Plettinger 3456 Villa Rose Drive Gretchen R. Rothschild-Reinike Baton Rouge, Louisiana 70806 Louisianians for Safe Energy, Inc.
2108 Broadway Street New Orleans, Louisiana 70118-5462 President of West Feliciana Police Jury Regional Administrator, Region IV P. O. Box 1921 U.S. Nuclear Regulatory Commission St. Francisville, Louisiana 70775 Office of Executive Director for Operations Mr. Frank J. Uddo 611 Ryan Plaza Drive, Suite 1000 Uddo & Porter Arlington, Texas 76011 6305 Elysian Fields Avenue Suite 400 Philip G. Harris New Orleans, Louisiana 70122 Cajun Electric Power Coop. Inc.
10719 Airline Highway P. O. Box 15540 Baton Rouge, LA 70895}}
10719 Airline Highway P. O. Box 15540 Baton Rouge, LA 70895}}

Latest revision as of 05:32, 11 December 2024

Forwards Supplemental Safety Evaluation Accepting Util Proposed Ten Yr Interval Inservice Insp Program.Staff Concurs W/Determination Made by Util That ASME Code Requirements Impractical to Perform at Facility
ML20151Q443
Person / Time
Site: River Bend 
Issue date: 08/01/1988
From: Calvo J
Office of Nuclear Reactor Regulation
To: Deddens J
GULF STATES UTILITIES CO.
Shared Package
ML20151Q445 List:
References
TAC-62971, NUDOCS 8808110161
Download: ML20151Q443 (5)


Text

b August 1,1988 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens Senior Vice President (RBNG)

Post Office Box 220 St. Francisville, Louisiana 70775

Dear Mr. Deddens:

SUBJECT:

FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -

RIVER BEND STATION, UNIT NO. 1 (TAC N0. 62971)

By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inscryice inspection program. The staff concluded that your program was acceptable and incompliancewiththerequirementsof10CFR50.55a(g)(4).

Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were determined to be impractical to perfonn at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its contractor, Idaho National Engineering Laboratory, met with GSU representatives i

on February 17-18, 1988,at the River Bend Station to review the requests and the examination procedures for the reactor pressure vessel.

Based on its review, the staff concurs with the determination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.

The requested relief from the ASME Code requireirents for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.

Sincerely, Josek(Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION NRC & Local PDRs PD4 Reading L. Rubenstein Docket. File.

J. Calvo W. Paulson P. Noonan F Litton E. Jordan Partlow ACRS (10)

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4 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. -Deddens SeniorVicePresident(RBNG)

Post Office Box 220 St. Francisville, Louisiana 70775

Dear Mr. Deddens:

SUBJECT:

FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -

RIVER BEND STATION,-UNIT NO. 1 (TAC N0. 629/1) l By letter dated October 20, 1987, th.. NRC staff forwarded safety evaluation regarding the River Bend Station first ten-ye inservice inspection program. The staff concluded that your pro am was acceptable and in compliance with the requirements of 10 CFR 50.55a (4).

Gulf States Utilities (GSU) identified ASME Secti i 11 Code requirements that were determined to be impractical to perform at iver Bend Station. The NRC's October 20, 1987 Safety Evaluation did not gra relief for the examination of Category B-A welds in the reactor pressur vessel.

GSU requested reconsideration of these relief requests.

cordingly, the NRC staff and its j

contractor, Idaho National Engineering La ratory, met with GSU representatives on February 17-18, 1988 at the River Ben Station to review the requests and 1

the examination procedures for the rea or pressure vessel.

Based on its review, the staff concu s with the determination made by GSU that i

ASME Code requirements for Category /B-A welds in the reactor pressure vessel are impractical to perform at the/ River Bend Station, Unit 1.

The staff's supplemental Safety Evaluation 14 enclosed.

Sincerely, Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

/

Enclosure:

As stated

/

/

cc w/enclosur_e':

See next page

/

DISTRIBUTION Docliet File NRC & Local PDRs PD4 Reading L. Rubenstein f

J. Calyo W. Paulson P. Noonan F. Litton E. Jo dan Partlow ACRS (10)

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Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)

Post Office Box 220 St. Francisville, Louisiana 70775

Dear Mr. Deddens:

SUBJECT:

FIPST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -

RIVER BEND STATION, UNIT N0. 1 (TAC NO. 62971)

By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).

Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were determined to be impractical to perform at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel.

GSU requested reconsideration of these relief requests. Accordingly, the NRC staff and its contractor, Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the examination procedures for the reactor pressure vessel.

Based on its review, the staff concurs with the determination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.

The requested relief from the ASME Code requirerrents for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.

Sincerely, Jose k( Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation As stated cc w/ enclosure:

See next page DISTRIBUTION Docket File NRC & Local PDRs PD4 Reading L. Rubenstein J. Calvo W. Paulson P. Noonan F. Litton E. Jordan Partlow ACRS (10)

Plant File OGC-WFN

  • See previous concurrences:

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August 1,1988 Docket No. 50-458 Gulf States Utilities ATTN: Mr. James C. Deddens SeniorVicePresident(RBNG)

Post Office Box 220 St. Francisville, Louisiana 70775

Dear Mr. Deddens:

SUBJECT:

FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM -

RIVER BEND STATION, UNIT NO. 1 (TAC NO. 62971)

By letter dated October 20, 1987, the NRC staff forwarded its safety evaluation regarding the River Bend Station first ten-year inservice inspection program. The staff concluded that your program was acceptable and in compliance with the requirements of 10 CFR 50.55a(g)(4).

Gulf States Utilities (GSU) identified ASME Section 11 Code requirements that were detemined to be impractical to perfom at River Bend Station. The NRC's October 20, 1987 Safety Evaluation did not grant relief for the examination of Category B-A welds in the reactor pressure vessel. GSU requesteo reconsideration of these relief requests. Accordingly, the NRC staff and its contractor Idaho National Engineering Laboratory, met with GSU representatives on February 17-18, 1988 at the River Bend Station to review the requests and the exarr.ination procedures for the reactor pressure vessel.

Based on its review, the staff concurs with the detemination made by GSU that ASME Code requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Station, Unit 1.

The requested relief from the ASME Code requirements for the examination of Category B-A welds in the reactor pressure vessel is granted pursuant to 10 CFR Section 50.55a(g)(6)(1). The staff's supplemental Safety Evaluation is enclosed.

Sincerely, g, bb Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page


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Mr. James C. Deddens Gulf States Utilities Company River Bend Nuclear Plant cc:

Troy B. Conner, Jr., Esq.

Mr. J. E. Booker Conner and Wetterhahn Manager-River Bend Oversight 1747 Pennsylvania Avenue, NW P. O. Box 2951 Washington, D.C.

20006 Beaumont, TX 77704 Mr. Les England Mr. William H. Spell, Administrator Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Company Office of Environmental Affairs P. O. Box 220 P. O. Box 14690 St. Francisville, LA 70775 Baton Rouge, Louisiana 70898 Richard M. Troy, Jr., Esq.

Assistant Attorney General in Charge Mr. J. David McNeill, Ill State of Louisiana Department of Justice William G. Davis, Esq.

234 Loyola Avenue Department of Justice New Orleans, Louisiana 70112 Attorney General's Office 7434 Perkins Road Resident Inspector Baton Rouge, Louisiana 70808 P. O. Box 1051 St. Francisv111e, Louisiana 70775 H. Anne Plettinger 3456 Villa Rose Drive Gretchen R. Rothschild-Reinike Baton Rouge, Louisiana 70806 Louisianians for Safe Energy, Inc.

2108 Broadway Street New Orleans, Louisiana 70118-5462 President of West Feliciana Police Jury Regional Administrator, Region IV P. O. Box 1921 U.S. Nuclear Regulatory Commission St. Francisville, Louisiana 70775 Office of Executive Director for Operations Mr. Frank J. Uddo 611 Ryan Plaza Drive, Suite 1000 Uddo & Porter Arlington, Texas 76011 6305 Elysian Fields Avenue Suite 400 Philip G. Harris New Orleans, Louisiana 70122 Cajun Electric Power Coop. Inc.

10719 Airline Highway P. O. Box 15540 Baton Rouge, LA 70895