ML20069B975

Application for Amends to Licenses DPR-24 & DPR-27, Consisting of TS Change Request 171 Re Heatup & Cooldown Limit Curve Expiration Date Extension to 23.6 EFPY

ML20069B975
Person / Time
Site:	Point Beach
Issue date:	05/26/1994
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20069B979	List: ML20069B975 ML20069B994
References
CON-NRC-94-040, CON-NRC-94-40 VPNPD-94-056, VPNPD-94-56, NUDOCS 9405310243
Download: ML20069B975 (3)

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Wisconsin Electnc POWER COMPANY 231 W Mechgan, PO Box 2044 Mdwoukea WI 53201-2046 (414]221 2345 VPNPD-94-056 10CFR50.4 NRC-94-040 10CFR50.90 May 26, 1994 i

Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Ladies / Gentlemen:

DOCKETS 50-266 AND 50-301 TECHNICAL SPECIFICATIONS CHANGE REOUEST 17_1 HEATUP AND COOLDOWN LIMIT CURVE EXPIRATION DATE EXTENSION POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2

'l In accordance with the requirements of 10 CFR 50.59 and 50.90, Wisconsin Electric Power Company (Licensee) requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2, respectively. The proposed amend-ments extend the operation of both units with the current heatup and cooldown limit curves in the Technical Specifications to 23.6 effective full power years (EFPY). The Basis section for Technical Specification 15.3.1.B, " Pressure / Temperature Limits," is also being revised to reflect the methodology for curve compilation.

Marked-up Technical Specifications pages, a safety evaluation, and a no significant hazards consideration are enclosed.

DESCRIPTION OF CURRENT LICENSE CONDITION Technical Specifications Section 15.3.1, " Reactor Coolant System,"

specifies the limiting conditions for operation (LCOs) of the reactor coolant system which must be met to ensure safe. reactor operation.

Technical Specifications Figures 15.3.1-1, "Heatup Limitations,"

and 15.3.1-2, "Cooldown Limi;ations," indicate the acceptable operating range of pressures and temperatures to protect the reactor vessels against non-ductile failure.

DESCRIPTION OF PROPOSED CHANGES Technical Specifications Figures 15.3.1-1, "Heatup Limitations."

and 15.3.1-2, "Cooldown Limitations," are revised to reflect tneir applicability through 23.6 effective full power years (EFPY), or approximately January 1, 2001.

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Document Control. Desk May 26, 1994 Page 2 ,

1. The Basis section for Technical Specification 15.3.1.B is revised as follows:

E_ aces 15.3.1-6 and 15.3.1-7

...As a result of fast neutron irradiation, there will be an increase in the RTum with nuclear reactor operation. The maximum integrated fast neutron exposure of the vessel is computed to be 2.5x10" neutrons /cm for 40 years of operation at 1518 MWt and 80 percent load factor.A This maximum fluence is the exposure expected at the inner reactor vessel wall.

However, the neutron fluence used to predict the ARTum shift is the one-quarter shell thickness neutron exposure...

Pace 15.3.1-81 " References" (1) FSAR, Section 4.1.5 (2) Westinghouse Electric Corporation, WCAP-12794, Rev. 2/

12795, Rev. 2 (3) Westinghouse Electric Corporation, WCAP-8743 (4) Westinghouse Electric Corporation, WCAP-8738 (5) Babcock & Wilcox, BAW 1803 (6) Regulatory Guide 1.99, Revision 2 i

2. The headings on Figures 15.3.1-1 and 15.3.1-2 are revised to indicate the extended applicability to 23.6 effective full I power years (January 2001).

BASIS AND JUSTIFICATION Exposure of reactor vessel materials to neutron radiation throughout operating life results in a change in the reference temperature (RTmg) of the materials due to neutron embrittlement.

This change in reference temperature is calculated periodically and appropriate limits revised.

Wisconsin Electric implemented a Low Low Leakage Pattern (L4P) core with hafnium inserts in the guide tubes of peripheral assemblies in each unit in 1989 to reduce neutron fluence to the critical reactor vessel welds. With L4P reload cores and hafnium inserts installed, l we have achieved significant flux' reductions relative to previous. '

core loading patterns. The rate of neutron embrittlement of the Point Beach reactor vessels has been reduced significantly over what was projected when the heatup and cooldown curves were l

previously submitted on October ?, 1989.

We are monitoring reactor vessel fluence with a reactor cavity neutron measurement program. The results of this measurement program are recorded in Westinghouse Electric Corporation WCAP-12794, " Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company, Point Beach Unit 1," Revision 2, and WCAP-12795, " Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company, Point Beach Unit 2," Revision 2.

B Document Control Desk  ;

May 26, 1994 Page 3 Based upon these results, we have determined and documented in Calculation N-94-058 that the reactor vessel fluence will not reach the previously analyzed limit of 2.05 x 10" n/cm2 (E > 1 MeV) until l 23.6 EFPY, or approximately January 2001.

Point Beach Technical Specification 15.3.1.B.4 requires that we submit revised heatup and cooldown limit figures to the Commission at least sixty (60) days prior to the calculated exposure of the reactor vessel exceeding the exposure to which the figures apply.

The current Technical Specification cumulative thermal power limit of 18.1 EFPY will be reached by Point Beach Unit 2 in approximately August 1994. However, since the calculated neutron exposure associated with the present curves will not be reached until approximately January 2001, the heatup and cooldown curves provided herein remain unchanged from the curves presently contained in our Technical Specifications.

We have determined that the proposed amendments do not involve a significant hazards consideration, authorize a significant change in the types or total amounts of any effluent release, or result in any significant increase in individual or cumulative occupational exposure. Therefore, we conclude that the proposed amendments meet the requirements of 10 CFR 51.22 (c) (9) and that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared.

Please contact us if you have any questions regarding this submittal.

Sincerely, i

_sh Ltt/Gots l

i B L nk l Vice President  !

Nuclear Power DAW /jg Enclosures cc: NRC Regional Administrator NRC Resident Inspector l Public Service Commission of Wisconsin '

Subscribed and sworn to before me this d6A day of ~77)au , 1994. ,

o ortte JroEAryOPublic, State of Wisconsin C/ -

My Commission' expires 10-27-94 .

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