ML20151L450

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Safety Evaluation Supporting Amends 113 & 116 to Licenses DPR-24 & DPR-27,respectively
ML20151L450
Person / Time
Site: Point Beach  
Issue date: 04/14/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151L435 List:
References
NUDOCS 8804220060
Download: ML20151L450 (3)


Text

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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N05.ll3 AND ll6TO FACILITY OPERATING LICENSE N05. DPR-Z TAE OPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH hUCLEAR PLANT, UNIT N05. 1 AND 2 DOCKET N05. 50-266 AND 50-301 INTRODUCTION In a letter dated October 13, 1987, WisconsinElectricPowerCompany(the licensee) submitted an application for awndments of the Point Beach, Units 1 and 2. Technical Specifications (TS).

The proposed amendments would revise Technical Specification Table 15.4.1-1, "Minimum Frequencies for Checks, Calibretions and Test of Instrument Channels," Item 25. "Steam Generator Pressure," survoillance requirements. This TS identifies the requirements for the chocking, calibrating, and testing of steam generator pressure channels. Currently, TS Table 15.4.1-1 Item 25, requires, in part:

(1) that all three steam generator pressure channels (per steam generator) be checked on a shift basis, except during periods of refueling shutdowns if the steam generator vessel temperature is greater than 70'F, and (2) that a steam generator pressure channel test be performed on a monthly basis, except during periods of refueling shutdown if the steam generator vessel temperature is greater than 70*F.

In its October 13, 1987 letter, the licensee proposed revising these requirements, respectively, to require:

(1) that all three steam generator pressure channels be checked on a shif t basis, except during cold shutdown or refueling shutdown, when a check of one pressure channel per steam generator is required if the steam generator could be pressurized, and (2) that a steam generator pressure channel test be perforred on a monthly basis, except during periods of refueling shutdown; however, the test must be perforned prior to startup if it has not been perforred during the previous surveillance period.

The changes proposed by the licensee do not result in changes in the frequency of the required surveillances during power operation.

Instead, the proposed changes only affect the frequency of required surveillances during shutdowns, provided certain conditions are met. The actual amendment is not a revision to the surveillance frequencies, but a revision to the notes identified by asterisks for the steam generator pressure channel check and test.

8804220060 800414 PDR ADOCK 05000266 P

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. EVALVATION

%.hnical Specification 15.3.1.B.2, "Pressure Temperature Limits," requires 9at the steam generators not be pressurized above 200 psig whenever the steam generator vessel temperature is less than 70'F. The intent of this TS is to ensure that pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The surveillence specified in TS Table 15.4.1-1, Item 25 oetails the surveillance requirements applicable to the steam generator pressure channels. This surveillance is in place to (1) ensure that the plants are operated in conformance with TS 15.3.1.B.2 and (2) verify that the safety injection actuation alann and trip initiation are received when a test signal is injected through the steam generator pressure channels.

The licensee noted two problems with the current TS.

First, the steam generator vessels are not instrumented for temperature; therefore, it is not practical for operators to determine when the steam generator vessel temper-ature is less than 70'F.

Second, the currently required monthly channel test only verifies the steam generator pressure channels are operable by injecting a test signal which verifies that the alarm and trip functions of safety injection actuation are operable. When the plant is in the cold shutdown or refueling shutdown mode, the low-pressure alarm is in constant alarm (steam generator pressure is less than the alann setpoint) and automatic safety injection is not necessary (the plant is in cold shutdown or refueling shutdown). The licensee states that since the monthly test does not improve the operator's means of monitoring the steam generator pressure during periods when the limits of specification 15.3.1.B.2 could be violated, the test is useless.

The staff has reviewed the changes proposed by the licensee and concludes that these changes are acceptable.

ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as d& fined in 10 CFR Part 20 or changes in surveillance requirements. The staf f has detennined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that 1

there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in10CFR651.22(c)(9). Pursuantto10CFR51.22(b),noenvironmental impact statement or environmental assessnent need be prepared in connection with the issuance of these amendments.

,,Cf,NCLUSION The staff has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

D. Wagner Dated:

April 14, 1988