ML17216A411

Notifies That Max RT (Pressurized Thermal Shock) of 171 F Will Be Experienced by Intermediate Plate Matl at End of OL, Per 10CFR.61(b)(1).Value Well Below 270 F Screening Criterion for Plate Matl.Supporting Documentation Encl

ML17216A411
Person / Time
Site:	Saint Lucie
Issue date:	01/23/1986
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	Miraglia F Office of Nuclear Reactor Regulation
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR 10CFR50.61, L-86-25, NUDOCS 8601290113
Download: ML17216A411 (11)

Text

DOCKET O 05000389

SUBJECT:

Notifies that max RT (pressurized; thermal shack) of 171 F

will be experienced bg intermediate plate matl at end of OLP per 10CFR. 61(b) (1). Value well below 270 F screening criterion for plate matl. Supporting documentation encl.

DIBTRIBUTION CODE:

AOAVD COPIEB RECEIVED: LTR J ENCL i SIZE:

TITLE:

OR Submittal:

Thermal Shock to Reactor Vessel REGULATORY FORNATION DISTRIBUTION SY N (RIDS)

(,,

I ~

~

ACCESSION NBR: 8601290113 DOC. DATE: 86/01/23 NOTARIZED:

NO FACIL:50-389't.

Lucie Planti Unit 2P Florida Power 5 Light Co.

AUTH. NANE AUTHOR AFFILIATION 4lOODYP C. O.

Florida Power Zc Light Co.

REC IP. NANE RECIPIENT AFFILIATION NIRAGLIAiF. J.

Division of Pressurized Mater Reactor Licensing B (post 8

NOTES:

OL: 04/06/83 05000389 RECIPIENT ID CODE/NANE PNR-B ADTS SELLS' COP IES LTTR ENCL 1

1 1

1 RECIPIENT ID CODE/MANE PNR-B PDS PD 01 COPIES LTTR ENCL 5

5 INTERNAL: ACRS ELD/HDS2 NRR ERi C REG FILE RGN1 ADNSTR 10 12 05 6

6 0

1 1

1 1

1 1

ADN/LFNB NRR LOISe L NRR VISSINQP G04 RES RANDALLzP RGN2 0

1 1

1 1

1 1

1 1

EXTERNAL: 24X NRC PDR 02 1

1 1

1 LPDR NSIC 03 06 9W TOTAL NUNBER OF COPIEB REQUIRED:

LTTR hfdf" ENCL

l,rr

~ ll l h HI

<<3 <<,Ptlt>>,H r H

<> <<gh<<h

~ g I f)

'l/ t<<

H,

(

r H

~ Ht t

K

, Vf. Q<<ttl h

t P.o, BOX 029100 MIAMI,FL 33102

+yYlAg~

+i'AA+

FLORIDAPOWER & LIGHT COMPANY

~ 2 S 1()ee L-86-25 Mr. Frank 3. Miraglia, Director Division of PWR Licensing - B U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Miraglia:

Re:

St. Lucie Unit 2 Docket No. 50-389 10 CFR 50.61 (b)(1) Re rt 10 CFR 50.61 (b)(1) requires the submittal of projected values of RT (PTS) for the end of the operating license for St. Lucie Unit 2. The requirement arises from the concern over reactor vessel embrittlement and pressurized thermal shock.

FPL has recently removed a surveillance capsule from St. Lucie Unit 2 which well defines vessel fluence.

The results of the analysis of this capsule was utilized in the plant specific fluence projections.

Beltline properties are well defined for reactor vessels in new plants such as St. Lucie Unit 2.

St. Lucie Unit 2 reflects the industry's increased understanding of vessel embrittlement as evidenced by the low concentrations of copper and nickel in the materials of fabrication.

The highest RT (PTS) expected at St. Lucie Unit 2 is 171OF at end of license.

This will be experienced by the intermediate plate material and is well below the 270 F screening criterion for plate material.

Should you or your staff have any questions on this information, please contact us.

Very truly yours, C. O. Wood Group V resident Nuclear Energy Department SAC/cac CC:

Dr. 3. Nelson Grace, Region II USNRC Harold F. Reis, Esquire PNS-LI-86-16

~Dp ~+Oiga egOg OCg SSO OSOOO389 I'DII i AD D

CRDTCIIPIELD (LTR ONLY)

EB (N. JONNSTON)

RSB (TIIONAS)

EICSB.(PARR)

POB (N RECAN)

PEOPLE... SERVING PEOPLE

C' 1

h

{'

ATTACHMENT1 Reactor Vessel Beltline Materials Descri tion The St. Lucie Unit 2 reactor pressure vessel was designed and fabricated by.

Combustion Engineering, Inc.

The reactor vessel beltline, as defined by 10 CFR 50, Appendix H, consists of the six plates usedto form the lower and intermediate shell courses in the

vessel, the included longitudinal seam welds and the lower to intermediate shell girth. seam weld.

The plates were manufactured from SA533 Grade B Class 1 quenched and tempered plate.

The longitudinal and girth seam welds were

'abricated using E3018-C3 manual arc electrodes and Mil B-O submerged arc weld wire with Linde 120 R 0091 flux.

The beltline materials are listed in Table l.

Calculations for present and end of license RT (PTS) are based on equation 1 of 10 CFR 50.61 (b)(2)..All materials data for these calculations are listed in Table l.

Fluence data is listed in Table 2 with the required calculated values oif RT (PTS).

Since actual values for all materials were available, the "M" value of 08 F was used for all calculations.

Bases for all materials data can be found in the references.

Fluences are projected to end of license based on previous cycle-specific computer modeling predicitions reported by Babcock and V/ilcox (1) and extrapolated to the end of license based on calculated power distributions.

l D

TABLE 1 ST. LUCIE 2 REACTOR VESSEL BELTLINEMATERIALPROPERTIES Location Lower shell Plate Lower Shell Plate Lower Shell Plate Intermediate Shell Plate Intermediate Shell Plate Intermediate Shell Plate Girth Weld Lower Shell Long Seam Welds Intermediate Shell Long Seam Weld Code Number M-0116-1 M-0116-2 M-0116-3 M-605 M-605-2 M-605-3 101-171 101-102 A 101-102B

'01-102C 101-120A 101-120 B 101-120C Residual(2)

Cu96 0.06 0.07 0.07 0.11 0.13 0.11 0.07 0.00 0.05 0.00 0.00 0.03 0.00 Chemistry(2)

Ni96 0.57 0.60 0.60 0.61 0.62 0.61 0.08 0.10 0.09 0.09.

0.06 0.06 0.07 RT(NDT)o(2)

+20

+20

+20

+30

+10

-70

-50

-50

-50

-50

-50

-50

j

TABLE 2 FLUENCE AND RTPTS 1986 and 2023 ST. LUCIE UNIT 2 Location Code Number Fluence n/cmZ Jan 1986 RT PTS OF 3an 1986 Fluence n/cm2~Ar 2023 RT PTS OF

~Ar 2023 Intermediate Shell Intermediate Shell Intermediate Shell Lower Shell Lower Shell Lower Shell Intermediate Shell Longi-

.tudinal Seam Intermediate Shell Longi-tudinal Seam M-605-1 M-605-2 M-605-3 M-0116-1 M-0116-2 M-0116-2 101-120 A 101-120 B 3.p6 x lpl8 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x lpi8 125 116 95 90

'95 0.79 x 1019 177 0.79 x 1019 179 0.79 x 1019 0.79 x 1019 0.79 x 1019 0.79 x 1019 125 125 13 0.79 x 1019 0.79 x 1019 107 Intermediate Shell Longi-tudinal Seam Lower shell Longitudinal Seam Lower Shell Longitudinal Seam Lower Shell Longitudinal Seam Intermediate to Lower Girth Seam 101-120 C 101-102 A 101-102 B 101-102C 101-171 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x 1018 3.06 x 1018 0.79 x 1019 0.79 x 1019 0.79 x 1019 0.79 x 1019 0.79 x 1019 13 21 13 16

REFERENCES l.

A. Lowe 3r. et al "Analysis of Capsule W-83, Florida Power and Light Co.,

St. Lucie Unit No. 2", BAW-1880 September 1985.

2.

FPL Company, St. Lucie Plant Unit 2, Updated Final Safety Analysis Report, Vol. 6.

4'>

4

~

A