ML20080H832

Application for Amend to Licenses NPF-2 & NPF-8, Incorporating NRC Suggested Tech Spec Changes Contained in Generic Ltr 83-43 Re Reporting Requirements of 10CFR50.72 & 10CFR50.73

ML20080H832
Person / Time
Site:	Farley
Issue date:	02/03/1984
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20080H834	List: ML20080H832 ML20080H850
References
GL-83-43, NUDOCS 8402140342
Download: ML20080H832 (5)

Text

Mzliing Addrats Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham. Alabama 3529i Te:ephone 205 780-6081 F. L Clayton, Jr.

%%$'C79 AlabamaPower February 3,1984 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Consnission Washington, D.C. 20555 Attention: Mr. S. A. Yarga Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Generic Letter 83-43, Reporting Requirements of 10CFR Part 50, Section 50.72 and 50.73 Gentlemen:

NRC Generic Letter 83-43,. dated December 19, 1983, informed Alabama Power Company of recent changes to Title 10 of the Code of Federal Regulations. A revision was made to Section 50.72 of Title 10 and a new Section 50.73 was added, both of which become effective January 1,1984.

Section 50.72 revises the immediate notification requirements for operating nuclear power reactors, and the new Section 50.73 provides for a revised Licensee Event Report System.

The NRC provided model technical specification showing the revisions which should be made in the " Administrative Control" and " Definitions" sections of the Farley Nuclear Plant Technical Specifications to incorporate these regulation changes. Attachment 1 contains a response to each of the NRC suggested technical specification changes given in Generic Letter 83-43. Attachment 2 contains the proposed technical specification changes for Farley Nuclear Plant, Units 1 and 2.

The proposed changes do not involve a significant hazards consideration as defined in 10CFR50.92. These changes are similar to example (vii) of

" Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6, 1983. These changes are similar in that a change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keeping with the regulations, it involved. Additionally, the proposed changes are in accordance with the NRC guidance contained in Generic Letter 83-43 including-the renumbering of the appropriate paragraphs of:Section 6.9.1.

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i Mr. S. A. Varga February 3,1984 U. S. Nuclear Regulatory Commission Page 2 The Plant Operation Review Committee has reviewed this proposed change. The Nuclear Operations Review Board will review this change at a i future meeting. Alabama' Power Company requests NRC approval for these technical specification changes as soon as practicable in order to eliminate 4~ the inconsistency between 10CFR50.72 and 10CFR50.73 and the. existing ,

technical specifications. ,

Because this change is a_ clarification to 93 technical specificatior.s and made at the request of' the NRC, Generic lett;- 83-43 states that a '

j license fee is not required for this change.

1 In accordance with 10CFR50.90,- three (3) signed originals and forty

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- (40) additional copies of this proposed change.are enclosed. As noted by the distribution, a copy of this letter is being sent to the Alabama State Dcsignee in ac ordance with 10CFR50.91(b)(1).-

If you have any questions, please advise.

Yours very truly,

'k NF. L. Cl ayton, Jr. ,

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FLCJr/BHW:ddr-036 SWORN TO AND SUBSCRIBED BEFORE ME .:

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Attachments s cc: Mr. R. A. Thomas 1THIS M DAY OF 984 l.

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3:;:MsF Mr. E. A.' Reeves AAm Notary Public 4

Mr.-W. H. Bradford -

Dr. I.~L. Myers My Commis'ston Expires: 1:A641 '

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Attachment 1 RESPONSE TO ENCLOSURE 10F GENERIC LETTER 83-43 1.0 DEFINITIONS NRC Guidance:

Delete the term, " REPORTABLE OCCURRENCE". Add the term, "REPORTA9LE EVENT" with the following definition:

"A REPORTABLE EVENT" shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

APCo Response:

In accordance with NRC guidance, the proposed Technical Specification is included in Attachment 2.

6.5.1.6 RESPONSIBILITIES NRC Guidance:

Revise (f) to read as follows: " Review all REPORTABLE EVENTS."

APCo Response:

In accordance with NRC guidance, the proposed Technical Specification is included in Attachment 2. Note that NRC Standard Technical Specification paragraph 6.5.1.6(f) is the same as Farley Technical Specification 6.5.1.6(h).

6.5.2.7 REVIEW l i

NRC Guidance:

Revise (g) to read as follows: "ALL REPORTABLE EVENTS" APCo Response:

In accordance with NRC guidance, the proposed Technical Specification is included in Attachment 2. Note that NRC Standard Technical Specification paragraph 6.5.2.7(g) is the same as Farley Technical Specification paragraph 6.5.2.7(e).

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o Attachment 1 Page 2 6.6 REPORTABLE OCCURRENCE ACTION NRC Guidance:

Revise title to read as follows: " REPORTABLE EVENT ACTION."

Revise 6.6.1 to read as follows:

The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10CFR l Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the (URG), and the results of this review shal' be submitted to the (CNRAG) and the (Vice President - Nuclear Operations).

APCo Response:

In accordance with NRC guidance, the proposed Technical Specification is included in Attachment 2. Note that the l appropriate review group titles have been substituted for the NRC  !

I guidance titles.

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6.9 REPORTING REQUIREMENTS NRC Guidance:

Delete the following:

6.9.1 "AND REPORTABLE OCCURRENCES" 6.9.1.9 " REPORTABLE OCCURRENCES" 6.9.1.10 " PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP" 6.9.1.11 " THIRTY-DAY WRITTEN REPORTS" Change 6.9.1.12 " RADIAL PEAKING FACTOR LIMIT REPORT" to 6.9.1.9 APCc Response: -

In accordance with NRC guidance, the proposed' Technical Specification is included in Attachment 2. ~ Note that the appropriate paragraph numbers have been substituted for the NRC guidance paragraph numbers.  ;>-

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i 6.10 RECORD RETENTION NRC Guidance:

6.10.I Revise (c) to read as follows: "ALL REPORTABLE EVENTS" t

APCo Response:

i In accordance with NRC guidance, the proposed Technical i Specification is included in Attachment 2.

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