ML17342A366
| ML17342A366 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/23/1986 |
| From: | Woody C, Woody C FLORIDA POWER & LIGHT CO. |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR 10CRF50.61, L-86-09, L-86-9, NUDOCS 8601290065 | |
| Download: ML17342A366 (10) | |
Text
ACCESSION NBR:
FAC IL'0-250'0-251 AUTH. NAME WOODY'. P.
RECIP. NAME THOMPSON'. R.
REGULATORY RMATION DISTRIBUTION SYS (RIDS) 8601290065 DOC. DATE: 86/01/23 NOTARIZED:
NO DOCKET 0 Turkey Point Planti Unit 3i Florida Power and Light C 05000250 Turkey Point Planti Unit 4i Florida Power and Light C
05000251 AUTHOR AFFILIATION Florida Power h Light Co.
RECIPIENT AFFILIATION Division of Pressurized Water Reactor Licensing A (post 8
SUBJECT:
Forwards proJected values for RT'Pressurized thermal shock) at termination of OLS in 070427i per 10c fr50. 61(b) (1). Results indicate that limiting value will'e 263 Fi comparing favorably to screening criterion for circumferential welds.
DISTRIBUTION CODE:
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TITLE:
OR Submittal:
Thermal Shoe k to Reactor Vessel NOTES:
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Dear Mr. Thompson:
Re: Turkey Point Units 3 R 0 Docket Nos. 50-250, 50-251 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 Turkey Point Units 3 and 0.
This requirement arises from the concern over reactor vessel embrittlement and pressurized thermal shock.
FPL has responded vigorously to the PTS issue.
We continue to monitor the results of the programs enacted at Turkey Point Units 3 R 0 to reduce the rate of neutron fluence exposure to the reactor vessel through modified core loading design.
We have also documented more comprehensive data on the chemical composition and initial material properties of the reactor vessel.
Our efforts in all these areas have been reviewed by your staff and the results are summarized in the attached Tables 1
- 2.
The results of our work to date demonstrate that the limiting RT (PTS) at the termination of the Turkey Point Units 3 and 0 operating license (April 27, 2007) willbe 263O F for both units.
These values compare favorably to the screening criterion for circumferential welds of 300O F as given in 10 CFR 50.61.
The supporting information for these values is included in Attachment 1.
FPL is committed to maintaining the reactor fluence reduction program to ensure that the Turkey Point reactor vessels willnot exceed the screening criterion.
Therefore, FPL concludes'hat there is no longer any basis for concern regarding pressurized thermal shock at either Turkey Point Units 3 or 0, as evidenced by the significant margin between our projections and the'screening criterion.
Should you or your staff have any questions on this information, please contact us.
Very truly yours, C. O. Woo Group Vi resident Nuclear Energy Department
'1 COW/3EM:ss Attachment cc:
Dr. 3. Nelson Grace - Region 11, USNRC Harold F. Reis, Esquire PNS-LI-W, ns 8601290065 860i23 PDR ADOCK 05000250 P
PDR pL AD J. Knight (ltr only)
EB (BALLARD)
EICSB (ROSA)
PSB (GAbÃXLL)
RSB (BERLINGER)
FOB (BENAROYA)
PEOPLE... SERVING PEOPLE
ATTACHMENT1 Re:
Turkey Point Units 3 4 0 Docket Nos. 50-250, 50-251 10 CFR 50.61 (b)(1) Re rt Pursuant to the requirements of 10 CFR 50.61 the following material is submitted:
o AllBaseline materials listing o
Copper and Nickel concentration o
Initial RT(NDT) o Neutron fluence as of 3anuary, 1986 o
Neutron fluence as of April 2007 (termination of license) o Calculated RT (PTS) for 3anuary 86 and April 07 o
References for all bases for the above Beltline Descri tion Both vessels were fabricated by Babcock and Wilcox for Westinghouse.
The beltline consists of two ring forgings joined by an automatic submerged arc weld.
The forgings are ASME SA508 Grade B material.
The welds for both units are designated as SA 1101 which is a copper coated Page welding'wire using a Linde 80 weld flux.
Table 1 lists the beltline materials, heat numbers for the forgings and weld wire and weld flux lot numbers.
Also included in Table 1 are the copper and nickel concentrations and initial RT(NDT) for each material.
It has been con'eluded by the USNRC in Secy.82-065 that the high copper circumferential, Linde 80 welds are the critical beltline materials in both Turkey Point Units 3 and 0.
In addition, spjety evaluations have been performed by the USNRC staff on both the materials properties and flux reduction programs(2~ previously mentioned.
Actual initial RT (NDT) and more representative values of copper and nickel were approved.
Low leakage core loading was evaluated and verified that Turkey Point 3 and 0 would remain below the screening criterion for 32 EFPY.
Fluence Determinations FPL's flux reduction programs have been reviewed by the NRC staff in enclosure 2 of reference 2.
A topical report on fluence determinations is being prepared and will be submitted in the first quarter of 1986.
Fuel management, quantification of vessel flux and methodology to verify the estimated fluences used in this submittal have been discussed with the NRC and are reviewed in reference 7.
Table 2 gives vessel wall fluence for both units.
Calculations Calculations for present and end of license RT(PTS) are based on equation 1 of 10CFR 50.61 (b)(2) which gave a lower value than equation 2 for both units.
All data used for these calculations are presented in Tables 1 and 2.
RT(PTS) for both units is presented in Table 2.
Source material for all data is listed in the references.
Both welds use actual values for initial RT (NDT) and 08oF is used for "M". Forgings use an "M"factor of 59oF.
TABLE I MATERIALSDATAFOR TURKEY POINT BELTLINEMATERIALS UNIT LOCATION HEAT NO.
LOT NO.
96 Cu 96 Ni RT(NDT)o Intermediate shell Lower shell Intermediate to Lower girth weld Intermediate shell Lower shell Intermediate to lower girth weld 123 P 161 VA-1 123 S266 VA-1 71209 123 P 081 VA-1 122 S 180 VA-1 71249 N/A N/A 8005 N/A N/A 8005 0.058(3) 0.079(3) 0.26(1) 0.05'<<)
0.056<<)
0.26(1) 0 70(3) 00oF(6) 0.68(>>
. 30oF<<)
0.60(1) 10oF(1) 0.71<<)
50oF(>>
0.71(")
00oF(>>
0.60(l) 10oF(l)
TABLE2 TURKEY POINT FLUENCE DATAAND RT(PTS)
FOR BELTLINEMATERIALSONNER WALL)
UNIT LOCATION FLUENCE(7) 3AN 1986 (n/cm2J FLUENCE(7)
APRIL 2007 3AN $6
APRIL 2007 3
Intermediate shell 3
Lower shell 3
Intermediate to lower girth weld Intermediate shell Lower shell Intermediate to lower girth weld 1.27 x 1019 1.27 x 1019 1.27 x 1019 1.19 x 1019 1.19 x 1019 1.19 x 1019 133oF 138oF 236oF 139oF 131oF 233oF 2.15 x 1019 2.15 x 1019 2.15 x 1019 2.16 x 1019 2.16 x 1019 2.16 x 1019 138oF.
105oF 263oF 100oF 136oF 263oF
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REFERENCES l.
USNRC Letter, Evaluation of Reactor Vessel Materials Data for Turkey Point Plant Units 3 and 0 Reactor
- Vessels, S. A. Varga to 3.W. Williams, April 26, 1980.
2.
USNRC Letter, Near Term Flux Reduction Program, Turkey Point Plant Units 3 and 0, S. A. Varga to 3. W. Williams, February 27, 1985.
3.
S.
E. Yanichko, Florida Power and Light Company, Turkey Point Unit 3 Reactor -Vessel Radiation Surveillance Program, WCAP 7656, Westinghouse Electric Corp., Pittsburgh, PA, May 1971.
0.
S. E. Yanichko, Florida Power and Light Company, Turkey Point Unit 0 Reactor Vessel Radiation Surveillance Program, WCAP 7660, Westinghouse Electric Corp., Pittsburgh, PA, May 1971.
5.
FPL Letter, L-77-326, Turkey Point Unit 3 and 0 Reactor Vessel Material Information, R. E. Uhrig to George Lear, October 21, 1977.
6.
S. E. Yanichko, 3. H. Phillips, S. L. Anderson, Analysis of Capsule T, Turkey Point Unit 3 Surveillance Program Reactor Vessel Radiation Surveillance Program, Westinghouse Electric corp., Pittsburgh, PA. December 1975.
7.
USNRC Letter, Summary of Meeting held with FPL, October 3,
- 1985, Regarding Reactor Vessel Flux Reduction Fluence Calculations, D.
G.
McDonald to FPL, December 0, 1985.
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