ML20084K173

Application for Amend to Licenses DPR-71 & DPR-62,revising Tech Spec Section 3/4.7.5 to Eliminate Table 3.7.5-1 Re safety-related Hydraulic Snubbers.Class I & III Amend Fees Encl

ML20084K173
Person / Time
Site:	Brunswick
Issue date:	05/07/1984
From:	Cutter A CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20084K175	List: ML20084K173 ML20084K182
References
NLS-84-107, NUDOCS 8405110132
Download: ML20084K173 (2)

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CD&L Carolina Power & Light Company SERIAL: NLS-84-107 MAY 7 1984 Director of Nuclear Reactor Regulation Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELEC7AIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT HYDRAULIC SNUBBERS

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP),

Unit Nos. I and 2. The proposed change revises Section 3/4.7.5 to eliminate Table 3.7.5-1 (Safety-Related Hydraulic Snubbers) and conform with guidance recently provided by the Commission, and to incorporate miscellaneous administrative changes to Sections 3/4.7.6 and 3/4.7.7.

DISCUSSION Deletion of Table 3.7.5-1 from the Brunswick-1 and Brunswick-2 TS eliminates the need for frequent TS amandments to incorporate changes in the snubber listing. This list of individual snubber location, size, and system affected will be maintained in the plant procedures as required by Section 50.71(c) of 10 CFR 50. The reformatted TS Section 3/4.7.5 includes essentially the same requirements as the current Brunswick TS. The Limiting Condition for Operation remains the same in bath cases. Major differences include: (1) the additional requirement of a Tranaient Event Inspection (Section 4.7.5.d), and (2) altered sample plans (Section 4.7.5.e) used to determine the number of snubbers required to be functionally tested. The Basis for Section 3/4.7.5 is also revised to reflect the changes made to Section 3/4.7.5. Similar TS requirements have recently been approved by the Commission for Washington Public Power Supply System for WNP-2 and provided as guidance for Long Island Lighting Company to be incorporated in their draft TS for the Shoreham facility. Certain purely administrative changes have been made to Section 3/4.7.6 and 3/4.7.7. A summary list of these changes is provided in Enclosures 1 and 2.

SIGNIFICANT HAZARDS ANALYSIS The Commission has provided guidance concerning the application of its standards set forth in 10 CFR 50.92 for no significant hazards considerations by providing certain examples published in the Federal Register on April 6, gf'I 411 Fayctievolle Street

• P. O. Box 1551

• Raleign, N. C. 27602 0 8405110132 040507 L lh PDR ADOCK 05000324 P PDR

D. B. V scllo MAY 7 1984 1983 (48 FR 14870). Examples of an amendment likely to involve no significant hazards consideration include: (i) a purely administrative change; and (ii) a change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications. Section 4.7.5.d, Transient Event Inspection, represents an additional control to snubber inspections. All other changes are administrative in nature in that they do not affect the criteria used to establish safety limits, the bases for limiting safety system settings, or Limiting Conditions for Operation.

Therefore, CP&L has determined that this proposed amendment falls under the criteria of examples (i) and (ii) and as such involves no significant hazards consideration.

ADMINISTRATIVE INFORMATION The proposed Brunswick-1 and Brunswick-2 TS pages are included in Enclosure 1 and Enclosure 2. A complete summary of the changes made to each proposed TS page is included to assist in determining what revisions have been made.

Carolina Power & Light Company has evaluated this request in accordance with the provision of 10 CFR 170.22 and has determined that a Class III and a Class I license amendment fee are required. A check for $4,400 is enclosed in payment of these fees.

Should you have any questions concerning this submittal, please contact our Licensing Staff.

Yours yry tru ,

/ $

A. B. Cutter - Vice President Nuclear Engineering & Licensing MAT /ccc (9628 MAT) cc: Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

Mr. M. Grotenhuis (NRC)

Mr. Dayne H. Brown ,

Radiation Protection Branch Division of Facility Services Department of Human Resources A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his informatipa,are..

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