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{{#Wiki_filter:-                                          . - .    -  -.          _.        --
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              ,    Dave Morey                 Siuthern Nucle r C   -'
Dave Morey Siuthern Nucle r C
Vice President             Op: rating C:mpany Farley Project             RO Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 September 11, 1998 SOUTHERN COMPANY Energy ro Serve YourWorld"         l l
Vice President Op: rating C:mpany Farley Project RO Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 September 11, 1998 SOUTHERN COMPANY Energy ro Serve YourWorld" Docket Nos.: 50-348 10 CFR 50.90
Docket Nos.: 50-348                                                                 10 CFR 50.90                 )
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50-364 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk                                                                                     ;
50-364 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555-0001 l
Washington, DC 20555-0001 l
Joseph M. Farley Nuclear Plant Technical Specifications Change Request Intermediate Rance Nectron Flux Reactor Trio Setnoint Ladies and Gentlemen:
Joseph M. Farley Nuclear Plant Technical Specifications Change Request                                       l Intermediate Rance Nectron Flux Reactor Trio Setnoint l
By {{letter dated|date=December 31, 1997|text=letter dated December 31,1997}}, Southern Nuclear Operating Company (SNC) proposed to amend the Farley Unit I and Unit 2 Technical Specifications by changing the Nuclear Instrumentation System (NIS) Intermediate Range (IR) neutron flux reactor trip setpoint and allowable value. During SNC/NRC conference calls on July 23 and 29,1998, it was concluded that the reference to WCAP 12733, " Protection System Diversity Design Bases," on page 6 of Westinghouse report NSA-SSO 524, Rev.1, " Joseph M. Farley Nuclear Plant Safety Analysis Intermediate Range Neutron Flux Reactor Trip Setpoint Change," was not appropriate. The attached report has been revised by referencing topical report WCAP-7306, " Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors."
Ladies and Gentlemen:
Revised reports NSA-SSO-96-524, Rev. 2, (Westinghouse proprietary class 2C) and NSA-SSO 525, Rev. 2 (Westinghouse class 3 non-proprietary) are attached. Also attached is Westinghouse authorization letter CAW-98-1278 with accompanying affidavit, proprietary information notice, and copyright notice. Since NSA-SSO-96-524, Rev. 2, contains information proprietary to Westinghouse Electric Company, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.790 of the Commission's regulations. Correspondence with respect to the I
By letter dated December 31,1997, Southern Nuclear Operating Company (SNC) proposed to amend the Farley Unit I and Unit 2 Technical Specifications by changing the Nuclear Instrumentation System (NIS) Intermediate Range (IR) neutron flux reactor trip setpoint and allowable value. During SNC/NRC conference calls on July 23 and 29,1998, it was concluded that the reference to WCAP 12733, " Protection System Diversity Design Bases," on page 6 of Westinghouse report NSA-SSO               524, Rev.1, " Joseph M. Farley Nuclear Plant Safety Analysis Intermediate Range Neutron Flux Reactor Trip Setpoint Change," was not appropriate. The attached report has been revised by referencing topical report WCAP-7306, " Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors."
Revised reports NSA-SSO-96-524, Rev. 2, (Westinghouse proprietary class 2C) and NSA-SSO               525, Rev. 2 (Westinghouse class 3 non-proprietary) are attached. Also attached is Westinghouse authorization letter CAW-98-1278 with accompanying affidavit, proprietary information notice, and                 1 copyright notice. Since NSA-SSO-96-524, Rev. 2, contains information proprietary to Westinghouse Electric Company, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.790 of the Commission's regulations. Correspondence with respect to the                       i I
copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-98-1278 and should be addressed to H. A. Sepp, Manager of Regulatory and Licensing Engineering, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-98-1278 and should be addressed to H. A. Sepp, Manager of Regulatory and Licensing Engineering, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
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U. S. Nuclear Regulatory Commission                                             Page 2 SNC has determined that the revision to NSA-SSO-96-524, which provides the technical bases for the proposed Technical Specifications change, does not impact the conclusions of the significant hazards evaluation previously submitted.
U. S. Nuclear Regulatory Commission Page 2 SNC has determined that the revision to NSA-SSO-96-524, which provides the technical bases for the proposed Technical Specifications change, does not impact the conclusions of the significant hazards evaluation previously submitted.
If you have any questions, please advise.
If you have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY bM Dave Morey Sworn to andsubscribe before me t 's /       dayof 0 rl1...lqi998 Notaiy 'ub(d h
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY bM Dave Morey Sworn to andsubscribe before me t 's /
My Commission Expires:                    _,c@0/
dayof 0 rl1...lqi998 h
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MGE/maf:NISIRTS6. doc Attachments cc:     Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman. NRR Project Manager Mr. T. P. Johnson, FNP Senior Resident Inspector I                                                                                                                 ;}}
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My Commission Expires:
l MGE/maf:NISIRTS6. doc Attachments cc:
Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman. NRR Project Manager Mr. T. P. Johnson, FNP Senior Resident Inspector I
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Latest revision as of 04:17, 11 December 2024

Forwards Proprietary & non-proprietary Versions of Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change, in Support of Util 971231 Proposed TS Amend.Proprietary Info Withheld,Per Encl W Affidavit
ML20151V783
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 09/11/1998
From: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138K955 List:
References
NUDOCS 9809150074
Download: ML20151V783 (2)
v • d • e


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Dave Morey Siuthern Nucle r C

Vice President Op: rating C:mpany Farley Project RO Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 September 11, 1998 SOUTHERN COMPANY Energy ro Serve YourWorld" Docket Nos.: 50-348 10 CFR 50.90

)

50-364 U. S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555-0001 l

Joseph M. Farley Nuclear Plant Technical Specifications Change Request Intermediate Rance Nectron Flux Reactor Trio Setnoint Ladies and Gentlemen:

By letter dated December 31,1997, Southern Nuclear Operating Company (SNC) proposed to amend the Farley Unit I and Unit 2 Technical Specifications by changing the Nuclear Instrumentation System (NIS) Intermediate Range (IR) neutron flux reactor trip setpoint and allowable value. During SNC/NRC conference calls on July 23 and 29,1998, it was concluded that the reference to WCAP 12733, " Protection System Diversity Design Bases," on page 6 of Westinghouse report NSA-SSO 524, Rev.1, " Joseph M. Farley Nuclear Plant Safety Analysis Intermediate Range Neutron Flux Reactor Trip Setpoint Change," was not appropriate. The attached report has been revised by referencing topical report WCAP-7306, " Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors."

Revised reports NSA-SSO-96-524, Rev. 2, (Westinghouse proprietary class 2C) and NSA-SSO 525, Rev. 2 (Westinghouse class 3 non-proprietary) are attached. Also attached is Westinghouse authorization letter CAW-98-1278 with accompanying affidavit, proprietary information notice, and copyright notice. Since NSA-SSO-96-524, Rev. 2, contains information proprietary to Westinghouse Electric Company, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.790 of the Commission's regulations. Correspondence with respect to the I

copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-98-1278 and should be addressed to H. A. Sepp, Manager of Regulatory and Licensing Engineering, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

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U. S. Nuclear Regulatory Commission Page 2 SNC has determined that the revision to NSA-SSO-96-524, which provides the technical bases for the proposed Technical Specifications change, does not impact the conclusions of the significant hazards evaluation previously submitted.

If you have any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY bM Dave Morey Sworn to andsubscribe before me t 's /

dayof 0 rl1...lqi998 h

Notaiy 'ub(d l

_,c@0/

My Commission Expires:

l MGE/maf:NISIRTS6. doc Attachments cc:

Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman. NRR Project Manager Mr. T. P. Johnson, FNP Senior Resident Inspector I

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