ML17345B356

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Safety Evaluation Supporting Amends 97 & 91 to Licenses DPR-31 & DPR-41,respectively
ML17345B356
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 10/26/1983
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17345B355 List:
References
NUDOCS 8311210501
Download: ML17345B356 (4)


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UNITED STATfs NUCLEAR REGULA'TORY COIVIMISSION WASHINOTON, O. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT HO.

97 TO FACILITY OPERATING LICENSE NO.

DPR-31 AHD AMENDMENT NO.

91..

TO FACILITY OPERATING LICENSE NO.

DPR-41 FLORIDA POMER AHD LIGHT COMPANY TURKEY POINT 'PLANT UNIT HOS.

3 AND 4" DOCKET HOS. 50-250 AND 50-251 I.

Introduction By letter to the NRC dated May 13, 1983, Florfda Power and Light Company (the licensee) has proposed changes to the Technical'Specfffcatfons for Turkey Point Unfts 3 and 4 whfch wfl 1 tncorporate an addftfonal requirement for a monthly walkdown of all accessible safety-related flowpaths to verify the flowpaths exfzt to assure the safety-related systems can perform their function.

The proposed changes require that each valve (manual, power operated or autbmatfc) fs fn ft's correct posttfon and verify the availability of power to those components required for operab4Tfty of the desfgnated flow-paths.

These requfrements will be fncluddd fn Section 4.18 "Safety Related System Flowpaths."

Table 4. 18-"1 fdentfffest the systems, specfffes the frequency and the applicable operational mode of the reactor.

II.

Evaluation Me have reviewed the fnformatf'on submitted by the licensee requesting that Appendix A to Facility Operating License DPR-31 and DPR-41 be amended to include a requirement for A.monthly walkdown of all safety-related flowoaths to verify correct valve position and have concluded the proposed Technical Spec)ffcations are acceptable.

Our conclusion fs based on the fol lowing:

1.

Technical Specification fTS1 4. 18 including Table 4.18 This orooosed chanqe will suppot t a recent commttment made to the NRC by which all safety systems as shown on Table 4. 18-1 will be verfffed to ensure proper line-ups and avaflabflfty of flowpaths at monthly intervals.

These additional TS changes are consistent with the Standard Technical Specifi-cations for Westinghouse Pressurized Mater Reactors, NUREG-Q452, Revision 4, paragraph 4.5.2.6.2.

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814.18 - lhis section describes the basis, including the needs and purpose, for veri'fyi'ng tfie avatlahtltty of safety systems flowpath wh'ich will provide additional assurance that the systems will perform as designed.

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Administrative Procedure 0103.19.,

dated August 18, 1983, monthly Yerification of Safety Related Systems Plowpaths, 'has been reviewed by NRC Region II staff and adequately tmplements the proposed TS

4. 18.

III.

Environmental Consideration l

We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.

Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of envtronmental impact and, pursuant to 10 CFR S51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.

IY.

Concl us ion We have concluded, based on the constderattons discussed above, that:

(1) these is reasonable assurance that the health and safety of the public will not be endangered by operation tn the proposed

manner, and (2) such activities will be conducted Cn compliance with the Commission's regulations and the issuance of the amendments

<11 not he tntmtcal to the comaon defense and security or to the health and safety of the public.

Date:

October 26, 1983

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