ML19308D802

Forwards App B, Sodium Hydroxide Injection During Recirculation, to Gilbert Associates,Inc Analytical mode1, Borated Water Storage Tank Drawdown Transient Analysis, Revision 1. Proposed FSAR Revision Encl

ML19308D802
Person / Time
Site:	Crystal River
Issue date:	07/09/1976
From:	Rodgers J FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19308D803	List: ML19308D802
References
NUDOCS 8003180742
Download: ML19308D802 (4)

Text

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NRC , r 4 195 u.s. NUCLEAR REGULATo3Y WISsioN DOCKET NUMBER 62-76) 50-302 NR.C DISTRIBUTION roR PART 50 DOCKET MATERI AL TO: FROM: DATE oF DOCUMENT Florida Power Corp. 7/9/76 Mr. John Stolz S t. Petersburg, Florida DATE RECEIVED J. T Rodccrs 7/12/76 MLETTEN ONoToRIZED PROP INPUT FORM NUMBER oF COPIES RECEIVED CoRiolNAL JEUNC LAssiriEo 20 signed Copies p oPY DE SC KIPTeoN ENCLOSURE Ltr. re 4IB/76 mee ting. .. ..trans the following: Appendix B, Sodium Hydroxide (Na OH)

Injection During Recirculation, to the previously submitted Gilbert Associates

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Mr. John Stolz Branch Chief Light Water Reactors Branch I Division of Project Management U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Florida Power Corporation Crystal River Unit #3 Docket No. 50-302

Dear Mr. Stolz:

Enclosed are 20 copics of Appendix B, Sodium Ilydroxide (Na OH)

Injection During Recirculation, to the previously puhmitted Gilbert Associates Analytical Model - Borated WaterV Storage Tank Drawdown Transient Analysis, Revision 1.

On April 8, 1976, representatives of Florida Power Corporation (FPC), Babcock 6 Wilcox Company (BEW) and Gilbert Associates, Inc. (GAI) met with the NRC staff in Bethesda, Maryland to discuss the Borated Water Storage Tank Drawdown Test for Crystal River Unit 3. It was derided at that meeting that FPC would revise the chemical addition system to permit continued addition of Na OH during the recirculation phase of ECCS operation.

The analysis contained in Appendix B indicates that the required quantity of sodium hydroxide can be injected within ninety (90) minutes after the beginning of the postulated accident, with no modifications to the system nor additional operator action during the recirculation phase.

Included in our submittal is a copy of a propo. sed FSAR revision stating our commitment to continue to inject sodium hydroxide during the recirculation phase for ninety (90) minutes af ter the beginning of the accident.T

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Mr. -John ' Stolz , Branch Chie f 2 July 9, 1976 Light Water Reactors Branch I Division of Project Management-U.~S. Nuclear Regulatory Commission

- RE: Crystal River Unit #3 Docket No. 50-302

This submittal, along with an acceptable retest of the revised BWST' drawdown test, should resolve all issues concerning the chemical addition' systems.

Please advise sh~ould additional information be required.

Very truly yours, J T. Rodgers Assistant Vice President JTR/nm Enclosures 4

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(PROPOSED FSAR REVISION FOR AMENDMENT NO. 49)

The pH of the solution as a function of time after the LOCA (and/or MHA) is shown in Figure 14A-3.3 for the spray solution and sump solution during injection and during the initial portion of the recirculation phase. The pH of the spray solution and sump solution after extended recirculation is shown in Figure 14A-4.6. These pH values are based on all equipment function-ing as designed. If all ECCS pumps and both reactor building spray pumps were assumed to be operating at their run-cut conditions, the injection phase would be about 28 minutes instead of the 37 minutes. If in addition, the mot'or operated valve in one of the NaOH addition lines failed to open, the pH of the spray solution in the header with the failed valve would be that of a 1.3 wt percent boric acid solution (pH 4.5), and the pH in the other header would be about 13.5 10.5. The effects of this are: .

f a. In the header with failed valve, the sodium thiosulfate solution 'T will be added to a boric acid solution with a pH of 4.5. Its total exposure time in this low pH envircament is only one to two minutes because the low pH solution being sprayed from the header with the failed valve will mix with the high pH spray solu-tion from the other header sometime af ter leaving the spray nozzles and before reaching the emergency sump. The rate of sulfur forma-tion slow (gysodiumthiosulfatesolutionsatapHof4.5isrelatively and no significant amount of sulfur is expected tc form during this brief exposure.

b. The spray header to which all the sodium hydroxide is being added will be spraying a high pH solution into the reactor building.

The effect of this high pH spray on materials in the reactor building is not expected to cause any significant problems because the exposure time will be very brief due to the neutralizing action of the low pH spray from the other header.

c. The transient effects described in (a) and (b) above will only exist during the initial injection phase which is only 28-37 minutes (depending on the reactor building's internal pressure and the amount of pump run-out) .

The amount of sodium thiosulfate injected under the conditions of pump run-out and the f ailure of one sodium hydroxide addition valve to open is 38,000 pounds, which is the same amount that would be added if the system functioned as designed. Likewise, the amount of sodium gydroxide added would be the same amount that would be added when the system functions as* designed, 22,350 pounds. In the event that one sodium hydroxide addiLlon vatve faiis to open following a postulated accident, the design quantity of sodium hydroxide will be injected by leaving the remaining addition valve open for a total of 90 minutes from the start of initial injection.

SPRA.0-1713A spray nozzles are used in the spray headers. They are ramp bottom

-swirl chamber type nozzles of one piece construction; they have a 3/8" orifice and deliver a hollow cone spray pattern. Each nozzle will deliver'15.7 gal / min at 40 psi with a spray angle of 63 . The drop size distribution used in the 6-11a ,

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