ML19345G506
| ML19345G506 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/31/1981 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TAC-43744, TAC-43745, TAC-TAC-43744, NUDOCS 8104070404 | |
| Download: ML19345G506 (12) | |
Text
.
Whconsin Electnc eaaracoursur .
231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 March 31 ',1981 s
wr. uroid R. maton., otracter 'g eM M /4g y nr9 z Office of W: lear. Reactor Angulation RgO 3 6J U. 5. HUCLEAR E GULATORY.CONNISSION 198A b~
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, Washington,:D. C. 2055$ C t Dear Mr. Danten .
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DOCK;T N05. 50-246 AND 50-301 TECHNICAL 5P (CIF CATIFCHANGEREQUITINO.66
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POINT- BEA6i k ' 100T. UNIT 5 1 AND 2 In accordance with 2 action 50.59 of 10' CFR Part 50 Wisconsin
. Electric Power Company (Licensee)'hereby applies for amendments to FFacility Operating Licerses DPR-M and DPR-27 fu the Point Beach Nuclear Plant Units 1 and 2 respectively. The: purpose f these license amendments
. is to incorporate changes into the Point Beach Nuclear Plant Technical .
. Specifications; These changes consist of updated reactor coolant' system
-E temperature and pressure operating curves and revised mactor vessel .
antarials surveillance capsule' removal schedules.
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< . Technical shification L15 3 .1.8.4 requires that revised reactor' coolant system tagerature and pressure operating curves.shall be submitted to the Nuclear Angulatory Commission'at least ststy days before the cal- ~
culatea espesure of. the reactor, vessel exceeds the exposere fbr which the ; . ,-
entsting temperature and pressure curves are appitcable; The present figures for unit 2 (Technical.Spectfication F1 pre 15.3.1-3 fbr hentup ,
, s limitations;end Figure?15.3.1-4 for.ceeldsun,1< mitettens):are appitcable to seves effective full power year:1(EFPY).. It is predicted.that' Point -
Seach hit 2 will reach and exceed seven EFPY during-the month of June 1981.
JAccordingly, wa are eeclesing revised temperatum and pressure curves which
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'will te applicable' fler Point Beach Unit 2 operetion'through 14 EFPY. :It is'.
- estimated that these ' curves ~ will remain l applicable .to Unit 2 operation until ,
. 5eptenhor 1990. . The curves.were developed in the.same menner as previous: n '
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revistens to tha'es figures,'using 3the methods and data prrvided in Westing . ;
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nouse' Electric Corporetion Topical Report WCAP-6738. i This report was
- subedsted to thej NaC.with Licensee's letter dated. March 4,1977.. -
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Hr. Harold R. Denton March 31, 1981
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Licensee also proposes in this application to revise and extend the applicability of the Point Beach Unit I temperature and pressure curves (Figures 15.3.1-1 and 15.3.1-2). Although the present Unit I curves are applicable through July 1985, it is desirable, for plant operational reasons, that the temperature and pressure curves and heatup and cooldown limitations for both units be identical. As a result of the difference in the copper content of the reactor vessel beltline weld mtals between the Unit 1 reactor vessel and the Unit 2 reactor vessel and the resulting difference in the correlation between reactor vessel radiation exposure and RTND7 shift, tha tesperature and pressura limitations developed for Unit 2 for : 4 EFpY are applicable to Unit 1 for 21.5 2FPY of operation. The attached proposed revisions to Figures 15.3.1-1 through 15.3.1-4 have been labeled accordingly.
The attached proposed Technical Specification revisions for Point Beacn Nuckar Plant Units 1 and 2 also include changes to the reactor vessel surveillance specian capaule removal schedules as listed in Tables 15.3.1-1 and 15.3.1-2. These changes reflect both the actual capsule renovals to data and revise the predicted removal dates for the remaining surveillance specim ns. The Bases at page 15.3.1-8a have also been changed to reflect the predicted reactor vessel exposure which the surveillance specimens will represent at the time of their renoval. These changes were initiated during a revie,# of the revision to the surveillance capsule lead factors which were previously reported to the f4RC in WCAP-9635 provided as an attachment to Licensee's letter to Mr. Denton dated April 16, 1930.
The attached revised teuparature and pressure operating curves include corrections for possible temNrature and pressure instrumentation inaccuracies. The tenperature and pressure instrumentation errors have been revised to 24'F based on the wide-range temperature instrumentation and 64 psi based on the wida-range reactor coalant system pressure instru-
, menta tion. These calculated r.uximum instrumnt errors include additional I conservatisms and reflect all sources of potential error in both the signal l transmitter and signal processing and display equipmnt. The Bases at I page 15.3.1-7 have been changad to include these more conservative error corrections.
The NRC has previously determined ja a letter to Licensee dated
( Decemaer 20, 1978 that a license amendment application for revision of the
- reactor coolant system heatup and cooldown limitation curves requires a %
Class III amndment approval fee. Accordingly, we are enclosing a check in the amount of $8,000 for the Facility Operating Licenses DPP-24 and DPR-27 Class III license amendment approvals requested in this application.
We have included three signed originals and forcy additional copies of this amendaent request. Attached to each copy of the request are l
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Mr. Harold R. Denton March 31,1981 proposed Technical Specification pages which reflect the changes discussed in this letter. Please contact us if you have any questions regarding this satter.
Very tru1y yours, eo
/
Sol Surstein Executive Vice President
Enclosures:
Check Ho. 611269
. Subscribed and sworn to before se This G e eL 3 /, / (81 rW2PMYG APWmeJLA-Notary Putlic, State of Wisconsin
& Commission expires A.fo h / 47 7-v Copy to NAC Resident Inspector -
Point Beach Nuclear Plant-l
nsutron exposure of tha vessel is computed to be 3.9 x 1019 neutrons /cm2 for 40 years of operation at 1518 MWt and 80 percent load factor. (2) This is the exposure expected at the inner reactor vessel wall. However, the neutron fluence used to predict the ARTNDT shift is the one quarter shell thickness neutron exposure. The relationship between fluence at the vessel ID wall and a
the fluer.ce at the one-quarter and three-quarter shell thickness locations has been calculated and is presented in References 3 and 4 as a function of Effective Full Power Years. These curves are used to determine the fluence at the location of interest when the heatup and cooldown curves are to be revised.
Once the fluence is determined, the temperature shif t used in revising the heatup and cooldown curves is obtained from the temperature versus fluence curves (the 0.25% Copper Base, 0.20% Weld line for Unit 1 and the 0.30% Copper base, 0.25% Weld line for Unit 2) also contained in References 3 and 4. These curves are used because they are based upon a substantial amount of experimental data and represent the results of the chemical analysis of the weld metal in the reactor vessels.
The heatup and cooldown curves presented in Figure 15.3.1-1 and 15.3.1-2 (Unit 1) and 15.3.1-3 and 15.3.1-4 (Unit 2) were calculated based on the above information and the methods of ASME Code Section III (1974 Edition)
Appendix G, " Protection Against Nonductile Failure", and are applicable up to the operational exposure indicated on the figures. Corrections for possible instrtmentation inaccuracies have een incorporated into these curves. The temperature correction is made by adding the temperature error (24 *F) to the required temperature and the pressure correction is made by subtracting the pressure error (64 psi) from the required pressure. These corrections adjust the curves in the conservative direction.
15.3.1-7
.- . . - . . ~ . ...
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. . scheduled removal dates will provide materials data representative of about 4
lot, 20%, 50%, 70%, and 90% of the actual reactor vessel exposure anticipated during the vessel life.
References (1)~ FSAR, Section 4.1.5 (2) Westinghouse Electric Corporation, WCAP-8739
-(3) Westinghouse Electric Corporation, WCAP-8743 (4) Westinghouse Electric Corporation, WCAP-8738 f.
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15.3.1-8a u -
F. MINIMUM CCNDITIONS FOR CRITICALITY Specification _:
- 1. Except during low power physics tests, the reactor shall not be made critical unless the moderator temperature coefficient is negative.
- 2. In no case shall the reactor be made critical (other than for the purpose of low level physics tests) to the left of the reactor core criticality curve presented in Figures 15.3.1-1 for Unit 1 and 15.3.1-3 for Unit 2.
- 3. When the reactor coolant temperature is in a range where the moderator temperature coefficient is positive, the reactor shall be suberitical by an amount equal to or greater than the potential reactivity insertion due to depressurization.
- 4. 'The reactor shall be maintained suberitical by at least 1% until normal water level is established in the pressurizer.
Basis:
During the early part of the initial fuel cycle, the moderator temperature coefficient is calculated to be slightly positive at coolant temperatures
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below the power operating range.
(' The moderator coefficient at low temperatures will be most positive at the beginning of life of the initial fuel cycle, when the boron concentration in the coolant is the greatest.
Later in tha. life of the fuel cycle, the boron concentrations in the coolant will be lower and the moderator coefficients will be either less positive or will be negative. At all times, the moderator coefficient is negative in the
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power operating range. Suitable physics measurements-of moderator coefficient of reactivity will be made as part of the startup program to verify analytic predictions.
15.3.1-17 I
TABLE 15.3.1-1 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL SCHEIIJLE Capsule Approximate Istter . Removal Date*
V September 1972 (actual)
S December 1975 (actual)
R October 1977 (actual)
T Fall 1983 P Fall 1987 N Standby
- The actual removal dates will be adjusted to coincide with the closest scheduled plant refueling outage or major reactor plant shutdown.
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TABLE 15. 3.1-2 POINT BEACH NUCLEAR PIANT, UNIT NO. 2 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL SCHEDULE i
l Capsule Approximate letter Removal Date*
8 V November 1974 (actual)
T March 1977 (actual)
R April 1979 (actual)
P March 1986 S Spring 1991 N Standby
- The actual removal dates will be adjusted to coincide with the closest scheduled plant refueling outage or major reactor plant shutdown.
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