ML19261B097

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Responds to Requesting Status of Topical Rept SSCO-15215(NP), Containment Spray Nozzles for Nuclear Power Plants. Requests Addl Info to Complete Review & Schedule of Submittals
ML19261B097
Person / Time
Issue date: 09/07/1978
From: Baer R
Office of Nuclear Reactor Regulation
To: Gray E
SPRAYING SYSTEMS CO.
Shared Package
ML19261B094 List:
References
NUDOCS 7902090364
Download: ML19261B097 (6)


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UNITED STATES NUCLEAR REGULATORY COMMisslON

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l Mr. E. S. Gray Spraying Systems Company North Avenue at Schmale Road Wheaton, Illinois 60187

Dear Mr. Gray:

SUBJECT:

SPRAYING SYSTEMS COMPANY TOPICAL REFORT SSCO-152_15 (NP)

" CONTAINMENT SPRAY N0ZZLES FOR NUCLEAR POWER PLANTS" I am responding to your ;etter of August 16, 1978 in which you ask about the status of our reviert of the topical report referenced above.

Enclosed is a requ e t for hdditional information that has been developed as a 4

i result of our staff review. The staff review of your topical report will be complete once the issues raised in the Enclosure are resolved.

Please provide a schedule for submittal of your responses to the Enclosure i

so that we can schedule manpower to complete our review.

Sincerely, i

Robert L. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management

Enclosure:

Request for Additional Information q90209 9

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$CP 7 5p8 ENCLOSURE Request for Additional information Spraying Systems Company Containment Spray Nozzles for Nuclear Power Plants 1.

One purpose of the spray nozzle is to disperse the water in the spray system into drop sizes small enough to effectively remove heat from the containment atmosphere following a loss-of-coolant accident.

Therefore, we believe your topical report should relate the s 'atial -

drop distribution prodaced by the spray nozzles to the heat removal I

capabil ity.

t The discussion should include the following:

(a) How the spatial drop distribution produced by the spray nozzle varies with the pressure drop across them.

This should then be related to the heat removal capability of the spray pattern.

(b) Any experimental data to verify your conclusion regarding the efficiency of the spray pattern to remove heat.

It is our position that if you elect not to include this discussion in s

your topical report, this area be clearly stated as an interface requirement to be addressed by those applicants referencing your topical report.

2.

Following a loss-of-coolant accident, it is expected that a certain amount of debris may flow toward the sump.

Therefore, sump intakes are protected by using screens.

The size of the ooenings in these 4

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. screens are based on the minimum restrictions found in the systems

>served by the sumps.

Since the spray systems take suction from the

\\{ v' 6 ump during the recirculation phase of the accident, it is our position

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.that blockage and clogging of the spray nozzles be discussed in your f\\

topical report.

The discussion should include any experimental data

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used to determine the maximum size particles that can safely flow

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through your nozzle.

This should also be specifie_d as an interface a 7?;\\

c requirement to size the opening in the protective screens for sumps.

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Provide the design limits for the spray nozzle that must be met by the applicants referencing your topical report.

These limits should include the maximum operating temperature,, pressure and flow rate.

Also state other standards or codes that the nozzle design meets.

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SPRAYING SYSTDIS'CO.

September 20, 1978

SUBJECT:

SSCO Topical Report SSCO-15215 (NP) " Containment Spray Nozzles for Nuclear Power Plants"

REFERENCE:

NRC Robt. L. Baer - Letter 9/7/78 OBJECT:

Discussion of Request for Additional Information No. 1 SSCO has submitted a histrogram showing the spatial distribution on Page 9, Fig. A for the nozzle spraying at 40 PSI as required in Bechtel Design Specifications No.10466-M-155.

Also, information showing dis-tributions for various pressure drops is not readily available or is information showing heat removal capabilities, since this information was not required in the design spaifications. Therefore, it is our position to regard this request as an interface requirement and should be addressed to Bechtel.

No. 2 The maximum free passage diameter for the 15215-lC-304SS 6.3 Whirljet Nozzle is indicated to be 7/16 inch on Page 1,Section I of the Topical Report and shown in Drawing No. 15424, Page 6, which is in excess of the requirement of 3/8 inch as set forth in the Bechtel specifications.

This also shall be regarded as an interface requirement.

No. 3 The design limits specified by Bechtel Corp. are as follows:

Maximum temperatures:

Post loca injection phase 370-1000F 0

120 -2700F Post loca recirculation phase Flow rate on GPM at pressures up to 100 PSI is indicated on Page ll, Fig. 1 of the submitted Topical Report. The design condition to be met is 15.2 GPM at 40 PSI.

The maximum pressure the spray nozzle is to encounter:

Post loca injection phase:

Inlet pressure range, PSIG 40-100 Outlet pressure range, PSIG 0-60 Post loca recirculation phase:

Inlet pressure range, PSIG 40-70 Outlet pressure range, PSIG 0-30 Standards and codes which. the nozzle must meet include:

ASME Boiler and Pressure Vessel Code f action II, Material Specifications Part.A: SA 351 austenitic steel castings for high temperature service

i SPRAYING SYSTE3fS CO.

ASME Boiler and Pressure Vessel Code Section III, Nuclear Power Plant Components Class 2:

Articles NC 2000 (materials)

NC 2130 (certification of material)

NC 4000 (fabrication and installation)

NC 5000 (examination)

ASME - ANSI N 45.2 Quality assurance program requirements for Nuclear Power Plants N45.2.1 Cleaning of fluid systems and atsociated components during construction phase of Nuclear Power Plants N45.2.2 Packaging, snipping, receiving, storage end handling of items for Nuclear Power Plants.

N45.2.3 Ecusekeeping during the construction phase of Nuclear Power Plants.

N45.2.9 Requirements for collection, storage, and maintenance of quality assurance records for Nuclear Power Plants.

ASME - ANSI B.2.1 Pipe threads.

Atomic Energy Commission Regulation, " Quality Assurance Criteria for Nuclear Power Plants" - 10CFR50 Appendix B.

Licensing of production and utilization facilities.

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MEMORANDUM FOR:

TERA Corp.

FROM:

US NRC/TIDC/ Distribution Services Branch

SUBJECT:

Special Document Handling Requirements

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Please use the following special distribution list for the attached document.

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The attached document requires the following special considerations:

Do not send oversize enclosure to the NRC PDR.

Only one oversize enclosure was received - please return for Regulatory File storage.

Proprietary infornation - send affidavit only to the NRC PDR Other: (specify) t p(6 O LLIh

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cc: DSB Files TIDC/DS3 Authorized Signature

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