ML18227C729

From kanterella
Jump to navigation Jump to search
Referring to Letter of 1/3/1977 Which Requested for Action, Letter Advising, on the Basis of Preliminary Review, Modification of Facility Will Not Be Required
ML18227C729
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/18/1977
From: Lear G
Office of Nuclear Reactor Regulation
To: Robert E. Uhrig
Florida Power & Light Co
References
Download: ML18227C729 (4)


Text

Docket Vds. 50-260 d1 JAN 1 8 )977 Distribution HRC PDR Local PDR ORB 83 TJCarter GLear CParrish DElliott

Attorney, OELD OIBE (3)

DEisenhut TBAbernathy BRBuchanan Gentlemen:

ACRS (16)

RE:

TURKEY POIHT HUCLEAR GENERATING UNITS HOS.

3 AtlD 4 Enclosed for your fnfomat$ on is. a copy of a 1etter dated January 3, 1977 from Robert D. Pollard, which is being considered as' Request for Action pursuant to 10 CFR 2.206, regarding your License Nos.

DPR-31 and DPR-41 and others.

A copy of the Notice we are filing >fifth the Office of the Federal Register relating to this request is also enclosed for your information.

The letter fran Hr. Pollard, artong other things, states that a refueling accident inside the containnIent buildfng raay not have been adequately considered during the licensing review of your facility.

As you are a>~are, Me recently contacted nenbers of your staff to obtain fnfomatfon for an independent assessment of such a postulated accident at your facility.

Based on our prelinfnary review, potential site boundary radiation exposures due to such an accident at your facility would be relatively low and wel 1 >>fthfn 10 CFR Part 100 guidelines even assuming no contafnnent fso'lation or effluent filtration.

On the basis of this prelfnfnary review we expect,- that vodfffcations to your facility will not be required.

In order to conffrn these results and to document the factors involved in the eValuation,

>~e request that you provide a detailed evaluation of the potential consequences of such an accident at your facility within 60 days of receipt of this letter.

Your analysis should utilize assunptfons co~parable to those given fn Regulatory Guide 1.25, MAssunptfons Used for Evaluating the Potential Radiolog'ical Consequences of a Fuel Hand1ing Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized lfater Reactors" and

consider, in a conservative nanner, any nfxing in the containE~ent.

OPPIC4&

dVRNAM4&

DAT4&

FOtIR hEC-318 (RdT. 9 53) hECM 0240 Q U, dI OOV4RNM4NT PRINTINO OPPIC4I IOT4 52d Idd

fl A

S

Florida Power 8 Light Company 48 g 8 ig7P aerosphere>>hfch>>ould delay release of naterfal, any filtration of effluent >>hich>>ould reduce releases and any automatic isolation of the containment >>hfch Mould lfnft releasesR Your evaluation should consist of t>>o parts:

(1) a canservatfve analysis using parameters (e.g.,

s!axfnun allowable valve closure tires) as limited by the technical specifications and (2) an analysis using parar!eters associated with current, known facility operating conditions (e.q.,

actual valve closure tines).

Clearly indicate the envfromaent for >>hfch the equfpr!ent is qualified, including sefsnfc,'nd

>>hether the equipment can withstand a sfngle failure.

Sincerely,

Enclosures:

1.

Letter dtd. 1/3/77 free A. D. Pollai d 2.

Federal Aegfster Wotfce cc >>/enclosures:

Hr. Jack R. 4!e!L!an, Esquire Louenstein, HeNman, Reis 8 Axelrad 1025 Connecticut

Avenue, W.

W.

Suite 1214 Washington, D.

C.

2O036 Envirot!mental 5 Urban Affairs Library Florida Internatfonal University V<fanf,-Florida" 33'199 Original signed by C~eorge Lear, Chief Operating Reactors Branch 83 Dfvfsion of Operating Reactors OPPICEIP dURKAME~

DATE~

4 U, OI OOVERNMENT PRIKTINO OPPICEI IOT4 42d Idd Porm hEC-518 (Rdv. 9.5b) AECM 0240

-.ORB-!t'3---"----'-DOR--------"- -"ORB"43---------.-----

-"DE:1 1 iott---" " '-TJCarter-- --" GLear----------------

- 1/---- "77- ----- - '-1 ----.77--------

1 "--- 7"7-- ----"-----

'h