ML20137C833

Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure

ML20137C833
Person / Time
Site:	Point Beach
Issue date:	03/20/1997
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20137C825	List: ML20137C833 NPL-97-108, Provides Addl Info in Support of Suppl for TS Change Requests 188 & 189 Re Unit 2 Operations Following Replacement of SGs
References
NUDOCS 9703250143
Download: ML20137C833 (3)

Text

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15.2.2- SAFETY LIMIT, REACTOR COOLANT SYSTEM PRESSURE Applicability Applies to the maximum limit on Reactor Coolant System Pressure.

Obiective To maintain the integrity of the Reactor Coolant System.

Specification The Reactor Coolant System pressure shall not exceed 2735 psig with fuel assemblies installed in the reactor vessel.

Basis The Reactor Coolant SystemWserves as a barrier preventing radionuclides contained in the reactor coolant from reaching the atmosphere. In the event of a fuel cladding failure the Reactor Coolant System is the primary barrier against the release of fission products. By establishing a system pressure limit, the continued integrity of the Reactor Coolant System is assured. The maximum transient pressure allowable in the Reactor Coolant System pressure vessel under the ASME Code,Section III is 110% of design pressure. The maximtun transient pressure allowable in the Reactor Coolant System piping, valves and fittings under USAS Section B31.1 is 120% of design pressure.

Thus, the safety limit of 2735 psig (110% of design pressure) has been established.<23 The nominal settings of the power-operated relief valves (2335 psig), the reactor high-pressure trip (2385 psig) and the safety valves (2485 psig) have been established to assure never reaching the Reactor Coolant System pressure safety limit except for the hvoothetical locked rotor and rod election accidents which use the faulted condition stress limit acceptance criterion of 3105 nsig (3120 plia). The initial hydostatic test was conducted at 3110 psig to assure the integrity of the Reactor Coolant System.

Reference (1) FSAR, Section 4 (2) FSAR, Section 4.3 9703250143 POR ADOCK Q $$$66 PDR P

Unit 1 - Amendment No. 15.2.2-1 Unit 2 - Amendment No.

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G. OPERATIONAL LIMITATIONS I

b The following DNB related parameters shall be maintained within the limits shown during Rated Power operation: '

1. Ty shall be maintained belc." 578b557*F and <573.9 F.

2. Reactor Coolant System (RCS) pressurizer pressure shall be maintained:

. U.-it 1: 22205 psig during operation at 2250 psia, or 21955 psig during operation at 2000 psia.

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3. Reactor Coolant System raw measured Total Flow Rate (S : Bai) shall be  !

maintained >181.800 gpm..

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Unit 1 - Amendment No, M5 15.3.1-19 November ' 7, lo95 Unit 2 - Amendment No. M9 l

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e. Reactor coolant activity The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 15.3.1.C. The following information shall be included:

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the activity limit was exceeded;

2. Results of the last isotopic analysis for radioiodine analysis prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the ,

radioiodine activity was reduced to less then-lhan_the limit. l Each result should include the date and time of sampling and the radioiodine concentrations;

3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the activity limit was exceeded,

4. Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and I

5. The time duration when the specific activity of the primary coolant ex. eded 4-MULmicrocuries per gram DOSE EQUIVALENT l-131.

C. Monthly Operating Reports i

1. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis under the titles " Operating Data Report",

" Average Daily Power Levels" and " Unit Shutdowns" and " Power Reduction". In addition, the report shall contain a narrative summary of operating experience that describes the operation of the facility, including major safety-related maintenance for the monthly report period.

2. Completed reports shall be sent by the tenth of each month following the calendar month covered by the report.

51 FR 40303 Unit 1 - Amendment No. 15.6.9-3 January 5,1987 Unit 2 - Amendment Na,