ML20127L967
| ML20127L967 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/16/1985 |
| From: | Britt R WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20127L970 | List: |
| References | |
| TAC-60596, NUDOCS 8505230141 | |
| Download: ML20127L967 (4) | |
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W P0iWR COMPANY
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' \\ ' 231 W. MICHIGAN, P.0; BOX 2046, MILWAUKEE, WI 53201 -
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May 16,:1985 o
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.[ ~ JMr.1H'IR.;Dento'n,[ Director.
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- OfficefofeNuclear Reactor Regulation
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- U.' S. : NUCLEAR ' REGULATORY COMMISSION S Washington,-D. C.
20555
'Mr.-J..RL Miller, Chief
- Attention:1 Operating: Reactors,-Branch 3
[ Gentlemen::
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. DOCKET NO. 50-266.
. REACTOR-VESSEL-MATERIALS SURVEILLANCE CAPSULE: TEST REPORT.
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POINT: BEACH NUCLEAR PLANT, UNIT 1 4-Ourlletter;of April-22,.1985 requested an extension Huntil June;1,S1985;to: submit the' Unit 1 surveillance Capsule T-1summaryKtest report to allowjus-time to. satisfactorily, resolve
,ouricomments on the' draft. report with the testing: contractor.
We.
"h'velnow resolved'all comments and'the capsule? testing results-a
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mQ l'are being submitted in-Westinghouse'. Electric Corporation report WCAP-10736' Five copies of'this' report.are' enclosed herewith
- for:your1information.
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, A summary;of thecresults of.this. capsule testLis.provided:
- % lin Attachment ~A.;_Th'ese;results indicate a temperature shift
- of-less-than~that. predicted,by Regulatory Guide 1.99 and Westinghouse trend curves'and, therefore,',supportothe, continued-use.of operating.
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! Pressure-temperature limits:specified.in the plant Technical'
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tSpecifications.
The Capsule;T data alsoisupport-the concept.!of.
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Ysaturation'of1 irradiation-induced.embrittleme~nt, changes'seen previously-
.in: Unit lireactor.vesselimaterials testing.
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. _ Theiwedge: opening ~ loading- (WOL)'~ specimens-from Capsule T <
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were not~ tested.- At the pre'sent. time, we ' have WOL l specimens from :
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- Capsules,S,;R,
- and.T for Unit-1 and. Capsules V and T for Unit -2 in.
storage'.'.;Although Westinghouse and EPRI have developed a test
' method 1that:-modifies the 1XWOL' specimens to obt'ain-valid ~J-R curves, f lW"ENe' 4
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d-LMr.'H. R. Dentoni May,16, 1985 we'do not plan.on t'esting the'WOL' specimens in storage until a.
specific need for.these-data arises and, in'any case,.-until acceptable criteria for performing this testing are agreed upon.
Also enclosed.with this letter is.a check for'$150.
- This fee is remitted, as requested in Ms. R. M. Diggs letter
-dated May 8, 1985,-pursuant to 10 CFR Part 170.
Very-truly yours, l
l President
- R.. W. Britt '
Enclosures (Check No. 8473.50 )
1 Copy,.to NRC Resident Inspector
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1 1
. h 05/16/85 Attachment A
SUMMARY
OF CAPSULE T REACTOR VESSEL MATERIALS TESTING POINT BEACH NUCLEAR PLANT, UNIT 1 WCAP-10736:
Analysis of Capsule T From the Wisconsin Electric Power Company Point Beach Nuclear Plant Unit No. 1 l
Reactor Vessel Radiation Surveillance Program I
Unit 1 was shut down on September 30, 1983 for steam generator replacement and for its twelfth refueling.
Capsule T was removed from the reactor vessel on March 27, 1984.
It has resided in the reactor vessel for approximately nine effective full-power years of operation.
This capsule represents about 60% of reactor vessel life for radiation embrittlement considerations.
Capsule T received an average fast fluence of 2.11 x 10 ' n/cm 1
2 18 2
(E > 1 Mev) versus a predicted value of 2.18 x 10 n/cm (E > 1 Mev).
Effectively, Capsule T was irradiated to the same fluence as.
that received by the last capsule tested from Unit 1, Capsule R.
Capsule T did not receive as much fast neutron fluence as projected in the Technical Specifications due to the implementation of low leakage cores in 1980-1981 and to the reduced power / reduced temperature operations utilized from 1980-1983 to slow the rate of steam generator tube degradation in Unit 1.
The dosimetry analysis of surveillance Capsule T yielded correction factors to adjust the measured activities of previous surveillance capsules to the respective capsule centers.
The revised measured fluences of previously tested Unit 1 surveillance capsules are as follows:
2 Capsule Fluence (n/cm )
V 5.44 x 10 18 S
7.55 x 10 18 R
2.08 x 10 18 The evaluation of the thermal monitors contained within the capsule indicated that the maximum-temperature to which the test specimens were exposed was less than 579 F.
The average upper shelf energy of the weld metal charpy impact specimens decreased from about 65 ft-lbs (unirradiated) to 53 ft-lbs.
This test result is consistent with previous capsule upper shelf energy test results and indicates that no additional irradiation-induced embrittlement is occurring beyond that seen in previous capsules..
4 l Irradiation to 2.'11~x 1018 2
'n/cm produced an increase'in the 30 ft-lb' transition temperature of the intermediate shell' plate,. lower'shell plate, and weld metal of 100, 50, and 180'F, re spectively.-
A
. temperature shift comparison of the weld metal' specimens tested in the last two.' capsules (30 ft-lb transition temperature shift of 165'F)~
. indicates that a minimal increase has occurred in capsule T;'however, this transition. temperature increase is lower than predicted by; NRC Regulatory Guide 1.99 Revision 1.-
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