ML17301A121

Application to Amend License DPR-67,revising Tech Specs to Supply Flow Rates & Tolerances for Each of Two Sodium Hydroxide (Naoh) Sources.Fee Paid.No Significant Hazards Evaluation Encl

ML17301A121
Person / Time
Site:	Saint Lucie
Issue date:	09/10/1984
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17301A122	List: ML17301A121 ML17301A124
References
L-84-237, NUDOCS 8409140191
Download: ML17301A121 (3)

Text

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-LORlop ow ~ 5 L-'lr cob!pANv September I'0, 884'-84-237 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regvlatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: St. Lvcie Unit No. I Docket No. 50-335 Proposed License Amendment Sodium H droxide Flow Rate and Pressure Test In accordance with IO CFR 50.90, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating License DPR-67.

This amendment is proposed to supply flow rates and tolerances for each of the two Sodium Hydroxide (NaOH) sources. This submittal is in accordance with the commitment of Amendment No. 49.

The proposed amendment is described below and shown on the accompanying Technical Specification pages.

Pa e 3/46-l6b The flow rates and tolerances and test pressures are provided.

The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 8 Light Company Nuclear Review Board.

In accordance with 10 CFR 50.9I(b)(l), a copy of the proposed amendment is being forwarded to the State Designee for the State of Florida.

In accordance with IO CFR I 70. I2(c), a check for $ 150.00 is attached.

Attachment I provides an evaluation of the proposed action in light of the three standards contained in 10 CFR 50.92 (No Significant Hazards).

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/R JS/cab ~.oO Attachment 84'Q 91-46-~~~~

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Office of Nuclear Reactor Regulation Mr. Darrell C. Eisenhut, Director Page 2 cc: J. P. OReilly, Region ll Harold F. Reis, Esquire

. Lyle Jerrett, Ph.D., Director Office of Radiation Control Dept. Health 8 Rehabilitative Services l3 l7 Winewood Boulevard Tallahassee, FL 3230 I

i ATTACHMENT I NO SIGNIFICANT HAZARDS EVALUATION The St. Lucie Unit I Technical Specification includes a requirement to periodically test the Spray Additive System. The requirement was approved with a commitment by FPL to provide the actual flow rates following testing.

The proposed changes provide those values.

The proposed change meets both exanple (i) and (ii) of the Exanples of Amendments that are considered Not Likely to Involve Significant Hazards Considerations as presented in the Federal Register notice of April 6, 1983.

Exan le i " "A purely administrative change to the Technical Specification's: For exanple. a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."

In that the proposed change merely adds a test value to a system previously designed, installed, reviewed and approved by the NRC, the change meets this example.

Exanple ii: "A change that institutes an additional limitation restriction or control not presently included in the technical specifications: for exanple, a more stringent surveill ance requi rement."

In that the proposed change adds additional testing requirements, it meets thi s ex apl e.

Therefore, since this change only incorporates additional testing values into an existing technical specification, we have concluded, in accordance with 10 CFR 50.92, that the proposed change does not involve a significant hazard in that it does not:

(I) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or di fferent kind of accident from any accident previously evaluated; or

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(3) Involve a significant reduction in a margin of safety.