ML17340A808

Application for Amend to App a of Licenses DPR-31 & DPR-41 Changing Tech Specs to Conform W/Reg Guide 1.14 & Section XI of ASME Boiler & Pressure Vessel Code

ML17340A808
Person / Time
Site:	Turkey Point
Issue date:	03/05/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17340A809	List: ML17340A808 ML17340A810
References
L-81-98, NUDOCS 8103110510
Download: ML17340A808 (6)

Text

REGULAT 'NFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:8103110510 DOC DATE: 81/03/05

~ NOTARIZED: YES DOCKET ¹ FACIL:50 250 Turkey Point Planti Unit 3i Floi ida Power and Light C O5000250

~

50-251 Turkey Point BYNAME Planti Unit 4p Florida Power and Light C AUTH AUTHOR AFFILIATION UHRI6 R E~ ~ F orica Power 8 Light Co 1 ~

RECIP NAME

~ RECIPIENT AFFILIATION EISENHUT~D.G. Division of Licensing

SUBJECT:

Application for amend to App A of Licenses DPR-31 L DPR 41 changing Tech Specs to conform w/Reg Guide 1, 14 L Section XI of ASME Boiler 4 Pressure Vessel Coae<

DISTRIBUTION CODE; A001S COPIES RECEIVED:LTR $ ENCL 9 SIZE!. g+N TITLE: General Distribution for after Issuance of Operating License NOTES:

RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL-ACTION'ARGAiS ~ 04 13 INTERNALS D/OIRiHUM FACOB 1 1 DIReDIV OF I IC 18E 06 2 2 NRC PDR 02 OELO 11 1 0 OH ASSESS BR 10 01 1 1 EXTERNAL: ACRS 09 ib 16 LPDR 03 NSIC 05 1 1 v/c~

g </eo MAR12 )g)

TOTAL NU4!BER OF COPIES REQUIRED: LTTR 39 ENCL 37

rg FLORiDA POWcR h LIGHT Coa1PANY March 5, 1981 Office of Nuclear Reactor Regulation L-81-98 Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing LA U.S- Nuclear Regulatory'ommission Washington, D. C. 20555 f~~p

Dear Mr. Eisenhut:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendment RCP Fl wheel Ins ection In accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41 .

The proposed amendment is described below and shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.

Table 4.2-1 Item 7.1 is changed to conform with Regulation Guide 1.14 and Section XI of the ASME Boiler and Pressure Vessel Code.

We have determined that this request is a Class I and TI Amendment pursuant to 10 CFR 1 70, since it is a dual request and it has no safety or environmental significance. Accordingly, a check for $ 1,600 is enclosed.

The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 6 Light Company Nuclear Review Board.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/PLP /ras Attachment cc: Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire P GPLS,, ScRV<gG PcOo> c

STATE OF FLORIDA )

) ss COUNTY OF DADE )

Robert E. Uhrig, being first duly sworn, deposes and says:

That he is a Vice President of Florida Power a Light Company, the Applicant herein:

That he has executed the foregoing document; that the statements made in this said document, are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Applicant.

Robert E. Uhrig Subscribed and sworn to before me this S day of , l9 5'/

NOTARY PUBLIC, State of Florida i nd for the County of Dade, Rotary Pub!ic. State ot Flocida t Larqe hky CommIa"!oo Expires Cctober 30, 1983 Ny commission expires: 8ondeo thru M Ira'ro p

. Co 6-

.Q ku TABLE 4.2-1 (CONTINUED C) ~

Extent of Examination Extent of Examination Examination Components and Parts (Percent in 10 Year Percent in 5 Year Ie N . ~Cat r To be Examined Method Interval) Interval) . Remarks 6.5 C-2 Pres>>uro-retaining Visual and IOOX 33X Exception is taken for valves which are boIL Volumetric not accessible.

6.6 K-1 Integrally-welded Not Applicablc Not Applicable supports 6.7 Supports and Hangers Visual 100X 33X Exception is taken for supports and hangers which are not accessible.

7.1 Reactor coolant pump flywheel 100X(2) In-place at bore Inscrvice inspection shall be perform<<d on, and keyway (1),each reactor coolant pump flywheel during the refueling or maintcnante shutdown poinciding with the In-Service Inspection schedule as required by Section XI of thc AMSE Boiler and Pressure Vessel Code:

(1) An in-plape ultrasonic volumetrip examination of thc area of higher stress gonpentration at the bore and keyway at approximately 3-year intervals.

(2) A surface examination of all exposed surfases and complete ultrasonic examination at or near the end of each 10-year interval.

7.2 Irradiation Tensile and Sce Remarks See Remarks Capsule 1 shall be removed and examined at Speciment Schedule Charpy V the first region replacement. Capsule 2 Notch (IIcdgc shall be removed and examined at the fourth Open Loading) region replacement. Capsule 3 shall bc removed and examined after twenty years of oporation. Capsule 4 shall bc removed and examined after thirty years of operation.

Capsule 5 shall be removed and examin<<d after forty years of operation.

3/5/81

0 SAFETY EVALUATION RE: Turkey Point Unit Nos. 3 & 4 Docket Nos. 50-250 and 50-251 Pro osed Tech S ec Amendment Introduction This evaluation supports a proposal to revise Specification 4.2.1, "Reactor Coolant System In-Service Inspection", Table 4.2-1, Item No. 7. 1 Reactor Coolant Pump Flywheel Inservice Inspection, to conform to the the requirements of Regulatory Guide No. 1. 14, Revision 1, August 1975, and Section XI of the ASME Boiler and Pressure Vessel Code.

I I. Di scussi on The proposed revision to Technical Specification 4.2.1, Table 4,2.1, Item No. 7.1 is necessary to conform Specification 4.2.1 to the requirements of Regulation Guide No. 1.14 and Section XI of the ASME Boiler and Pressure Vessel Code. This proposed revision does not alter the design philosophy for In-Service Inspection discussed in FSAR Section 4.4. 1 and as such will continue to ensure that as a mimimum, the assumptions used in the safety analyses are met and the operability of the reactor coolant pump flywheels are maintained.

III. Conclusion We have concluded, based on the considerations discussed above, that:

{1) the amendment does not involve a significant increase in the probability or-consequences of accidents previously considered arid does not involve a significant decrease in a safety margin, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment, will not be inimical to the common defense and security or to the health and safety of the public.