ML20093E032

Application for Amend to Licenses NPF-2 & NPF-8,changing Tech Specs to Reflect Administrative Changes & Incorporate Info Per Generic Ltr 84-13, Tech Spec for Snubbers. Justification Encl

ML20093E032
Person / Time
Site:	Farley
Issue date:	07/06/1984
From:	Mcdonald R ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20093E036	List: ML20093E032 ML20093E042
References
GL-84-13, NUDOCS 8407170354
Download: ML20093E032 (4)

Text

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~ * - ~0 Mailing Address h orm 18 h S t Post Omce Box 2641 TI hone 2'O 7834 R. P. Mcdonald Semor Vice President Flintndge Boilding , gghgg))g gg t w ur w nt.e W::, '

July 6, 1984 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr.' S. A. Yarga Joseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Administrative Te:hnical Specification Change Gentlemen:

Recent reviews of the Farley Nuclear Plant - Units 1 and 2 Technical Specifications have identified some administrative changes which need to be made. Additionally, on May 3,1984, the NRC issued Generic Letter 84-13

" Technical Specification for Snubbers." The Generic Letter indicated that licensees may request to have the tabular listing of snubbers removed from their technical specifications. This administrative change to the Joseph M. Farley Nuclear Plant Units' Technical Specifications incorporates these changes.

Attachment 1 contains a discussion of the proposed administrative changes to both Units 1 and 2 Technical Specifications and provides supporting background information and justifications.

Attachment 2 lists the changed Technical Specification pages and includes the proposed changed pages. The proposed changes do not involve a '

significant hazards cor. sideration as defined in 10CFR50.92. These changes are similar to example (1) of " Examples of Amendnents That Are Considered Not Likely To Involve Significant Hazards Considerations" listed in 48FR14870 dated April 6, 1983. These changes are similar, in that these changes are adt.inistrative, in order to correct errors and implement NRC Generic Letter 84-13.

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• a Mr. S. A. Varga July 6, 1984 Nuclear Regulatory Commission Page 2 The Plant Operations Review Committee has reviewed this proposed change and the Nuclear Operations Review Board will review this proposed change in a future meeting. In accordance with the ' Alabama Power Company Licensing Plan, it is requested that this change be approved by January 1,1985.

Pursuant to 10CFR170.21, the new rule on License Fees, the required License Anendment Application Fee of $150.00 was included in check number 904209 which was transmitted to the NRC by letter dated June 25, 1984.

In accordance with 10CFR50.90 three (3) signed originals and 40 copies of this proposed change are enclosed. Pursuant to 10CFR50.91 (b) we have provided a copy of this letter and the proposed technical specification changes to Mr. Dan Turner, the designated representative of the State of Alabama.

If you have any questions, please advise.

Yours very tru ,

7V L R. P. Mcdonald RPM /CSJ:ddr-D36 SWORN TO AND SUBSCRIBED BEFORE ME Attachments THIS /, d DAY OF . 4 4 , 1984 cc: Mr. L. B. Long s Mr. J. P. O'Reilly [l/ d. r/m erh Mr. E. A. Reeves ' - ~ ' ' Notary 7uTHc Mr. W. H. Bradford jj Mr. G. F. Trowbridge My Connission Expires: jefs fjfas-Mr. D. Turner ' -

Attachment-1 Proposed Adninistrative Technical Specification Changes

1) Change to Technical Specification 4.4.6.5.c and Table 4.4-2. (Both Units 1 and 2)

The existing specification required a prompt report to the NRC pursuant to Technical Specification 6.9.1. With the issuance of the new Licensee Event Reporting (LER) Rule. (10CFR50.73) the Technical Specification section for prompt reports (6.9.1.12) has been superseded. Specification 4.4.6.5.c and Table 4.4-2 have been updated to reflect the issuance of the new LER Rule.

2) Change to existing Technical Specification 3.6.5.4 and 4.6.5.4. (Both Units 1 and 2)

The existing specification was numbered improperly. This was an error in adapting the Westinghouse Standard Technical Specifications to the Farley Nuclear Plant. The specifications have been corrected to 3.6.4.4 and 4.6.4.4 respectively.

3) Change to existing Technical Specification 4.7.4.b.2. (Both Units 1 and 2)

The existing specification could be erroneously interpreted to require plant shutdown to perfonn the required inspection of buried service water piping which only entails a visual examination of the surrounding-ground area. In order to clarify the surveillance requirement, Specification 4.7.4.b.2 has been changed to Specification 4.7.4.c. so that a requirement for plant shutdown to inspect buried pipe is not implied.

4) Change to Technical Specification 3/4.7.9, "S,nubbers".- (Both Units 1 and 2)

Pursuant to NRC Generic Letter 84-13, " Technical Specification for-Snubbers" dt.ted May 3,1984,' Alabama Power Company hereby requests the deletion of the hydraulic and mechanical snubber listings from the Farley:- Units 1 and-2 Technical Specifications. In addition, several footnotes, indicating temporary tech 11 cal specification conditions which no lo1ger are in effect, have been deleted. Alabama Power

. Company recognizes that there is currently on file with the NRC a request to <nodify the Farley - Unit 2 Hydraulic Snubber Table. Rather than have t1e Snubber Table updated and then deleted from the . Technical Specifications, Alabama Power Company hereby withdraws the Proposed Technical Specification Change dated December 8,1983 and will include -

the snubbers listed in that change request in the snubber surveillance program. ,

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D Attachment 1 Page 2

5) Change to Existing Technical Specification Table 3.7-5. (Unit 2 only)

The existing Table is numbered improperly. The Table has been corrected to Table 3.7-6 as required by Technical Specification 3.7.11.4 and 4.7.11.4. In addition, 3 typographical errors in the Table have been corrected.

6) Change to Technical Specification Table 3.7-8. (Unit 2 only)

Items 2e and 2f of the subject Table had an inappropriate temperature limit of 150"F. The Battery Charger Room A and B air temperature limits are actually 120*F based on vendor equipment information and twenty-four hour room temperature surveillance required by Technical Specification 4.7.13. The Table has been corrected to reflect the appropriate air temperature limits.

7) Change to Technical Specification Bases 3/4.7.9, " Snubbers". (Both Units 1 and 2)

Consistent with change number 4 above, the Bases of Technical Specification 3/4.7.9 has been revised. Specifically, reference to the manual which is a comprehensive tabulation of the snubbers within the scope of Technical Specification 3/4.7.9 has been added. The Unit 1 Bases page was revised to define the term "c", which was omitted as a result of an administrative oversight in Amendment Number 26.

8) Change to Technical Specification 6.5.2.8.n and 6.5.3.1. (Both Units 1 and 2)

! The existing specification could be misinterpreted to require the Manager-Safety Audit and Engineering Review to write a summary report of each NORB meeting. The actual intent is for the Manager - Safety l Audit and Engineering Review to present a sumary of the Audit and i

Review responsibilities at each NORB meeting. Technical Specification 6.5.2.8.n has been corrected in order to reflect the Manager's intended i responsibilities. In addition, reference to "the Assistant Plant Manager" in Technical Specification 6.5.3.1 has been replaced with "an l Assistant Plant Manager" to reflect a recent change in the facility organization. The Plant Manager also has the authority to change contingency implementing procedures and this has been clarified in the same section.

9) Change to Technical Specification 6.10.2.n. (Both Units 1 and 2) l This specification has been revised to delete reference to the hydraulic and mechanical snubber listings. This change is required to complete the implementation of change 4 listed above, m