ML18059B068
| ML18059B068 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/21/1994 |
| From: | Rogers D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18059B069 | List: |
| References | |
| NUDOCS 9406270166 | |
| Download: ML18059B068 (12) | |
Text
(t consumers Power POW ERi Nii MICHlliAN'S PROliRESS Palisades Nuclear Plant:
27780 Blue Star Memorial Highway, Covert, Ml 49043 June 21, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 David W. Rogers Plant Safety and Licensing Director DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE TEST REPORT In compliance with 10CFR50, Appendix H, paragraph III, this letter submits a report of the test results from the analysis of material from reactor vessel material surveillance capsule W-110.
Capsule W-110 was removed from the reactor on June 21, 1993 during the 10th refueling outage. Westinghouse Electric Corporation performed the analysis of the material from capsule W-110 and has published the results in WCAP-14014 dated May 1994.
No changes to the plant technical specifications resulted from the analysis. contains a summary technical report of the results of the analysis of material from surveillance capsule W-110. is the Westinghouse report WCAP-14014.
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David W. Rogers Plant Safety and Licensing,Manager CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment
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ATTACHMENT 1 Consumers Power Company Pali sades Pl ant Docket 50-255
SUMMARY
TECHNICAL.REPORT PALISADES REACTOR VESSEL SURVEILLANCE*CAPSULE TEST REPORT FOR CAPSULE W-110 June 21,' 1994 9 Pages
PALISADES REACTOR VESSEL SURVEILLANCE CAPSULE TEST REPORT FOR CAPSULE W-110 The Palisades reactor vessel surveillance capsule located in location W-110 was removed on June 21, 1993 during the 10th refueling outage. Westinghouse has tested the surveillance material and supplied the report WCAP-14014 (Attachment 2).
No changes are required to the plant technical specifications.
As noted previously to the NRC, the surveillance program weld material is not considered representative of the Palisades reactor vessel beltline welds.
The surveillance program weld was fabricated approximately three years later than the Palisade~ reactor vessel with weld wire procured solely for the purpose of fabricating this weld and with welding equipment no longer in use.
Fluence The fluence information for the reactor vessel beltline material has been updated in this report and is detailed in Table 1 for the critical locations.
Projecting future fluence accumulation at a rate no greater than received during operation of Cycle 9, the limiting material is a beltline axial weld fabricated with weld wire heat number W~214. Assuming a capacity factor of 75%, this weld is projected to exceed the pressurized thermal shock (PTS) screening criteria during the year 2004.
TABLE 1 PALISADES REACTOR VESSEL CRITICAL FLUENCE LOCATIONS Location Fluence @ EOC 10 Fl uence/EFPY (E19 n/cm 2 )
Cycle 9 rate1 oo 1.22 0.066 16° 1.68 0.097 30° 1.25 0.063 Standard Reference Material Surveillance cap~ule W-110 is the first capsule removed from the Palisades reactor vessel which contains standard reference material.
ARTNor versus fluence for this material falls within the uncertainty bounds (2a = 34°F) of the trend ~urve in Figure 1 for A533B reference material.
The ARTNor for the HSSTOI material in the W-110 capsule was 148°F. This value was adjusted by the ratio *Of-the chemistry factors (CFHssro2 = 128°F and CFHssro1. = 136.1°F) to derive an adjusted ARTNor of 139°F and plotted versus the trend curve as shown in Figure 2 of NUREG/CR-4947.
1Slade (CPCo) to NRC, "Docket 50-255 -
License DPR 10CFR50.61 Pressurized Thermal Shock -
Reactor Vessel Neutron Fluence -
Additional Information", June 10, 1993, Attachment 1, Table 2.
260 240 220 200 180
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160 Q)
'O 140
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+J 120
'I-s::.
Ul 100 I-0 z 80 I I-a:
60 40 20 0
0 Palisades Reactor Vessel Standard Re~erence Material 2
3 Fluence (E19 n/sQ cm)
V W110 Figure 1 4
Reactor Vessel Surveillance Plate Material s
Three chemical analyses were performed on the reactor vessel surveillance plate material. Adding these measurements to those previously reported2
- results in a slightly modified chemistry for re.actor vessel beltline plate D-3803-1 as shown in Table 2.
2Slade (CPCo) to.NRC, "Docket 50-255 - License DPR Palisades Plant -
10CFR50.61 Pressurized Thermal Shock - Revised Projected Values of RTPTs for Reactor Beltline Materials", June 5, 1992, attachment Table 2-13.
2
TABLE 2 PALISADES* REACT-OR VESSEL SURVEILLANCE PLATE CHEMISTRY I
I I
Material COEEer {%}
Nickel {%}
0-.3803-1 0.22 0.49 0.25 0.48 0.24 0.53 0.24 0.53 0.215 0.52 0.215 0.523 0.215 0.496 0.495 Best Estimate 0.23 0.51 Using this best estimate chemistry in Table 2 of 10CFR50.61 results in a chemistry factor {CF) of 154°F for the surveillance plate material.
The chemistry factor may also be determined per the guidance of Regulatory Guide 1.99, Rev. 2, paragraph C.2.1.
The plate material results from the three surveillance capsules removed from the Palisades reactor vessel are listed in Table 3.
6.0E19 n/cm 2 is the best estimate fluence for capsule A-240. 3 TABLE 3 PALISADES REACTOR VESSEL SURVEILLANCE PLATE LONGITUDINAL MATERIAL RESULTS I
Capsule Fluence {El9 n/cm 2 )
fiRTNoT. { o F)
W-290 1.09 175 W-110 1.779 180 A-240 6.0 205 I
Using the guidance of Regulatory Gui de I. 99, Rev. 2, paragraph C. 2.1 to determine CF yields a value of 153°F for the longitudinal surveillance plate material. The results are plotted along with the specified uncertainty of u =
17°F.
Note that the results do not fall within +/-lu of the mean curve in Fig.ure 2.
3Slade (CPCo) to NRC, June 5, 1992, Attachment 4, p. 17.
3
e e
Pa Ii sades Reactor Vessel Survel I lance Plate CL-T) 250 240 230 220 210 (L'
0 200 (I)
'O
. 190 u
~
'I-180
.c
(/)
170 I-0 z 160 I I-a:
150 140 130 1
3 5
2 4
6 Fluence (E19 n/sq cnQ I!.
A240 x
W290 v
W110 Figure.Z TABLE 4 PALISADES REACTOR VESSEL SURVEILLANCE PLATE TRANSVERSE MATERIAL RESULTS Capsule I Fluence (E19 n/cm 2 )
I
'1RT NOT ( ° F)
I W-290 I
1.09 I
155 A-240 6.0 205 Using the guidance of Regulatory Guide 1.99, Rev. 2, paragraph C.2.1 to determine CF yields a value of 146°F for the transverse plate material.
The results are plotted in Figure 3 along with plots of the specified uncertainty of u = 17°F. A CF of 146°F for material oriented in.the transv~rse dir~ction is conservatively bound by the value used in the Palisades PTS evaluations (CF = 165°F).
Surveillance weld material Three c~emical analyses were performed on the Palisades surveillance weld material.
The copper and nickel measurements for welds fabricated with weld wire heat number 3277 with nickel addition are shown in Table 5.
Chemistries for these welds were previously submitted Johnson (CPCo) to Denton (NRC),
4 I
e e
Pa I i sades Reactor Vessel Surve1 I lance Plate (T-L) 240 230 220 210
~
200 0
190 Ql
'O u..,
180
?:::
~
170 l/J I-160 c z I I-150 a:
140 130 120 1
3 5*
2 4
6 Fluence (E19 n/sq en\\)
6 A240 x
W290 Figure 3 "Docket 50-255 - License DPR Palisades Plant - Test Report of Reactor Vessel Specimen Capsules T-330 and W-290 Removed During the 1983 Refueling Outage", October 31, 1984, Attachment I, pp. 4-4 and 5-7i and VandeWalle (CPCo) to NRC, "Docket 50-255 - License DPR Palisades Plant - Palisades Reactor Pressure Vessel Pressure/Temperature Limits", June 14, 1985, Attachment III Addendum.
5
Weld Palisades surveillance weld Palisades HAZ weld TABLE 5 CHEMISlRY FOR WELDS FABRICATED WITH RACO 3 WELD WIRE HEAT NUMBER 3277 WITH Ni200 NICKEL ADDITION Copper (%)
Content 0.26 0.22 0.25 0.30 0.239 0.231 0.233 0.25 0.20 0.26 0.25 0.26 0.27 0.26 0.23 0.27 0.23 0.22 0.22 0.28 0.22 0.27 0.28 0.27 0.23 0.27 0.26 0.21 0.22 0.27 0.23 Mean 0.25 0.25 Nickel (%)
Content 0.63 1.27 1.60 1.38 1.617 1.502 1.494 0.43 1.28 1.22 1.09 1.25 0.98 1.27 1.09 0.90 1.18 1.28 1.27 1.02 1.10 1.22 0.. 94 1.18 0.89 0.92 1.15 1.29 1.31 1.02 1.12 I Best Estimate ltl fflJjJ*!I 0.25 6
Mean 1.36 1.10 1.23
e Tabl~ 1 of 10CFRS0.6~ not inclusive of welds containing a nickel content in
~xcess of 1.2 weight percent, but CF is expected to be greater than 272°F.
The weld material results from the three surveillance capsules -removed from the Palisades reactor vessel are.listed below in Table 6.
TABLE 6 PALISADES REACTOR VESSEL SURVEILLANCE WELD MATERIAL RESULTS Capsule
.Fluence (E19 n/cm 2 )
ART NOT (OF)
W-290 1.09 290 W-110
- 1. 779 314 A-240 6.0 350 Pa I i sades Reactor Vessel Sirver I lance we Id 410 400 390 390 370 360 350 CL' 340 0
330 CIJ 320 u
- u 310
+'
300
- c 290 Ul I-280 0
270 z
I 260 I-a:
250 240 230 220 1
3 5
2 4
6 Fluence (E19 n/sq cm) ti.
A240 x
W290 v
W110 Figure 4 Using the guidance of Regulatory Guide 1.99, Rev. 2, paragraph C.2.1, CF is calculat.ed to be 261°F.
The results are plo_tted in Figure 4 along with the specified uncertainty of a = 28°F.
7
Upper Shelf Energy I
The accumulated fl uence of 1. 779El9 n/cm 2 received by the W-110 capsule is greater than the peak of l.615El9 n/cm 2 expected at ~T at end of plant life. 4 None of the materials tn capsule W-110 had an irradiated Charpy upper shelf energy (USE) less than 50 ft-lbs. The limiting reactor vessel beltline material is plate D-3804-1, which is projected to remain above 50 ft-lbs through the licensed end of plant life. 5 The reduction in USE for the HSSTOl material was 26%.
This is less than the 31% predicted for a metal with a copper content of 0.18% irradiated to a fluence of l.779El9 n/cm 2
- Pertinent surveillance program results are plotted on Figure 2 of Regulatory Guide 1,99, Revision 2.
4Hsia (NRC) to Fenech (CPCo), "Generic Letter (GL) 92-01, Revision 1,
'Reactor Vessel Structural Integrity,' Palisades Plant (TAC No. M83491), April 25, 1994.
5Slade (CPCo} to NRC, 'Docket 50-255 - License DPR Upper Shelf Energy of Material in Reactor Beltline", August 31, 1990.
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FIGURE 2 Predicted Decrease in Shelf Energy as a Function of Copper Content and Fluence
+ T-L 0 L-T D Weld t.. SRM Figure 5
ATTACHMENT 2 Consumers Power Company Palisades Plant*
Docket 50-255 ANALYSIS OF CAPSULE W-110 Prepared by Westinghouse Electric Corporation June 21, 1994