ML19319D514

Forwards Request for Addl Info to Complete Evaluation Re FSAR Sections on Rcs,Engineered Safeguards, & Instrumentation & Control

ML19319D514
Person / Time
Site:	Crystal River
Issue date:	07/30/1973
From:	Schwencer A US ATOMIC ENERGY COMMISSION (AEC)
To:	Rodgers J FLORIDA POWER CORP.
References
NUDOCS 8003170641
Download: ML19319D514 (6)

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REQUEST FOR ADDITIONAL INFORMATION FLORIDA POWER CORPORATION CRYSTAL RIVER, UNIT 3 DOCKET No. 50-302 4.0 REACTOR COOLANT SYSTEM 4.39 Describe the procedures and results used to assure the operability of active pimps and valves under faulted plant conditions. The discussion should include a listing of all seismic Category I active pumps and valves, their safety functions (open or close),

test conditions, operational conditions, special tests, etc.

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- 6.0 ENGINEERED SAFEGU RDS 6.16-Section 6.2.2.1 of the FSAR states that "the sodium hydroxide raises the pH of the borated water into the alkaline range (app roximat ely ~ 9. 5)... " Supply the exact values of the pH as a function of time af ter the LOCA for the spray solution during injection, the sump solution, and the spray solution during -

recirculation. The calculations should be based on the following assumptions:

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a) All ECCS pumps are operating at run-out conditions.

b) Both reactor buildind spray pumps operating at run-out conditions.

c) Failure of one of the motor operated valves in the NaOH adtition line to open.

State the quantity of thiosulfate injected under these conditions.

6.17 Provide the P & I drawing which shows the piping connections from the sodium. hydroxide storage tank to the reactor building spray headers.

6.18 Describe the tests to be performed to verify that the design values for the pH and thiosulfate concentrations can he achieved with the system as installed. If the test fluids. differ from the actual solutions used af ter the LOCA, describe the fluids of similar viscosity and density to be used for the test, and

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the methods of correlating the test data with the design requirements.

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6.19-Describe the functional testing to be performed periodically to demonstrate the ' availability of the reactor building spray system, including ptunps, valves, and spray nozzles, as described in Table 6-8 of the FSAR, including the following information:

3 a) Frequency of the tests.

b) Source and flow path of all fluids used in the test.

s c) The method of ' verification of unobstry.ed flow through each of the 192 spray nozzles befog via iSility is impaired by accumulated smoke in the contaism q.

d) ' The method of verification of urchstructed. flew through the spray additive lines, and the spray headers up 'to @e isola-tion valves outside the. containment.

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6.20 Provide the drop size spectrum emitted from the spray nozzle.

State the type of distribution supplied (i.e., spatial or temporal), the source of the data, and discuss the accuracy and repeatability of the data.

6.21 List by type (epoxy, phenolic, zinc, etc.) and manufacturer's designation all known paints used in the containment.

In addition list the dry density and surface area covered by each paint. List the total surface area and estbnated volume covered by unknown paints.

Explicitly state the curing procedures applied or to be applied for each paint.

6.22 Insufficient details and design criteria of the reactor building sump and its intake screens are given.

6.22.1 Construction and layout details of the containment sump should include:

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the degree to which the corcept has been, or will be, proven sufficiently by experiencc, tests under simulated accident conditions, or conservative extrapolations from present knowledge; b.

how the system will function during the entire period required to accomplish its intended purpose (e.g., include consideration of component reliability, system interdependency, redundancy and separation of components or portions of system); and, c.

provisions made for initial and periodic testing and surveillance.

An analysis of the containment sump should be given which describes the flow path and restrictions (including sizes) which a particle would follow in circulating the diff erent systems which must use the sump as a source. An analysis describing the eventual fate of paint chips or other debris which may enter the sump should be '

presented.

6.25 Analyze each engineered safety features air filtration system (fuel handling building and control room) as to the positions in j

Regulatory Guide 1.52, " Design, Testing and liaintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants."

6.24 Provide plan and elevation drawings of the control room with a clear indication of the fresh air intakes.

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s 7.0 INSTRUMENTATION AND CONTROL 7.23 To assure the operability of seismic Category I instrumentation and electrical equipment under seismic disturbances, provide the following information:

a) Verify t' hat the responses of cabinet assemblies at the various instrument or device mounting locations due to the safe shutdown earthquake (SSE) are determined either by testing or dynamic analysis, b) Verify that the maximum response determined in (a) above of the instrument or device mounting locations are less than ig.

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