ML17341B644

Advises That Project Has Escalated to Approx 60 to 70% of Current Billings

ML17341B644
Person / Time
Site:	Diablo Canyon, Humboldt Bay, 05000000
Issue date:	02/23/1982
From:	Cloud R ROBERT L. CLOUD ASSOCIATES, INC.
To:	Miraglia F Office of Nuclear Reactor Regulation
References
P-105-4, NUDOCS 8202250171
Download: ML17341B644 (6)

Text

ACCELERATED DISTRIBUTION DEMONSTPWTION SYSTEM REGULAT(O INFORMATION DISTRIBUTIONOISTEM (RIDE) f ACCESSION /BR:9202250171 DOC.DATE: 92/02/13 NOTARIZED: NO DOCKET g FACIL:50"-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power a Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards updated estimate of RT PTS & beltline matls data, per NRC 910515 issuance of rev to 10CFR50.61(b)(l) requirements. Updated estimate demostrates adequate margins of safety to screening criterion for circumferential welds.

DISTRIBUTION CODE: A049D COPIES RECEIVED:LTR / ENCL / SIZE:

TITLE: OR Submittal: Thermal Shock to Reactor Vessel NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 1 1 AULUCKFR 2 2 INTERNAL: AEOD/DOA 1 1 NRR/DET 8H3 1 0 NRR/DST SE2 1 0 NRR/DST/SPLB SD 1 1 NRR/DST/SRXB SE 1 0 1 0 OGC/HDS3 1 0 REG FIL 01 1 1 RES DE 1 1 RES DE/MEB/MES 1 1 RES/DSIR/EIB 1 1 RES/DSIR/RPSIB 1 1 RES/DSR/RPSB 1 1 RGN1 ADMSTR 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LIKES FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 14

.0. Box 029100, Miami,

~ ~ FL, 33102-9100 L-92-27 FEB 18 1992 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 10 CFR 50.61 b 1 Re ort By letter L-86-09 dated January 23, 1986, Florida Power and Light Company (FPL) submitted the projected values for Reference Transition Temperature, Pressurized Thermal Shock (RT,) for Turkey Point Units 3 and 4, in accordance with the requirements of 10 CFR 50.61 (b)(1). On May 15, 1991, the NRC issued a revision to 10 CFR 50.61. In accordance with the revised 10 CFR 50.61 (b)(1), an updated estimate of the RT, for Turkey Point Units 3 and 4 is provided in Table 1; Table 2 provides the beltline materials data for Turkey Point Units 3 and 4. The critical beltline materials, initial properties, chemistry data of the critical beltline materials, and the limiting circumferential weld (SA 1101) specified in L-86-09 remain unchanged.

The fluence reduction program, implemented by FPL and verified by the NRC per NRC letter dated February 27, 1985, remains unchanged. The fluence reduction program consists of low-leakage fuel loading patterns coupled with part-length burnable absorbers, located so as to reduce the neutron flux to the pressure vessel circumferential weld from high importance core locations.

The RT, calculations were performed using equation 1 of 10 CFR 50.61 (b) (2) . An M value of 34 was used for forgings and an M value of 56 was used for welds. Initial properties based on drop weight and Charpy tests were used for both forgings and welds.

The updated estimate of the RT, for Turkey Points Units 3 and 4 provided in Table 1 demonstrates adequate margins of safety to the screening criterion for circumferential welds of 300'F, as specified in 10 CFR 50.61.

Should there be any questions, please contact us ~

Very truly yours, O

!AM Pl AIA wOQ T. F Plunkett AIO ~

OO AIIA Vice President O'0 Turkey Point Nuclear TFP/OIH

~ vQ OA le+ Attachments Al Al OQ.'IR cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC O'Q.Q. Senior Resident Inspector, USNRC, Turkey Point Plant an FPI. Group company P(19j t 0

",J 1

r ~ 1

TABLE 1 CURRENT AND PROJECTED RT TURKEY POINT UNIT 3 Fluence (x 10 )

neutrons/cm~ Intermediate Lower Girth Date (E > 1.0 MeV) Shell ('F) Shell ('F) Weld ('F)

August 24i 1992 1.501 115 121 April 27, 2007 2.342 120 127 287 July 19, 2012 2.641 121 128 293 TURKEY POINT UNIT 4 Fluence (x 10 )

neutrons/cm'E Intermediate Lower Girth Date > 1.0 Mev) Shell ('F) Shell ('F) Weld ('F)

October 15, 1991 1.366 121 112 262 April 27, 2007 2.210 125 117 285 April 10, 2013 2.533 126 118 291

TABLE 2 MATERIALS DATA FOR TURKEY POINT UNITS 3 AND 4 BELTLINE MATERIALS UNIT LOCATION HEAT NO. LOT NO. SCu %Ni INITIAL RTHDT ('F)

Intermediate shell 123 P 461 VA-1 N/A 0.058 0.70 40 Lower shell 123 S 266 VA-1 N/A 0.079 0.68 30 Intermediate to lower girth weld 71249 8445 0.26 0 '0 10 Intermediate shell 123 P 481 VA-1 N/A 0.054 0.71 50 Lower shell 122 S 180 VA-1 N/A 0.056 0.70* 40 Intermediate to 71249 8445 0.26 0.60 10 lower girth weld

• Changed from 0.71%; typographical error on the January 23, 1986 submittal.

h ~

4 p

~ ~ h a

\

~v