ML19308D670

Forwards Proposed FSAR Revision to Table 14-8 on Page 14-61, Summarizing Results of Several Initial Boron Concentration Conditions Examined by B&W.Results to Be Used as Basis for Lowering Refueling Boron Concentration in STS

ML19308D670
Person / Time
Site:	Crystal River
Issue date:	10/26/1976
From:	Rodgers J FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
NUDOCS 8003120743
Download: ML19308D670 (3)

Text

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50-302 fNC DISTRIBUTION FOR PART 50 DOCKET MATERI AL A.i T TO FSAR FROM: DATE OF DOCUMENT TO:

Florida Power Corp. 10/26/76 Mr. John Stolz St. Petersburg, Florida DATE RECElVED J. T. Rodgers 10/29/76 ILETTER ONOTCRIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED MontoiNAL KUNCLASSIFIED One signed OCoPY DESCRIPTION ENCLOSURE Ltr. trans the following: Proposed FSAR Change-Amendment No. 50 Table 14-8 Summary of Moderator Dilution Accident Analysis (1-P) (1-P) _ _

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Subject:

Crystal River Unit #3 Docket Nc. 50-302

Dear Str. Stol:

At the request of Floridt Power Corporation, Babcock 6 Wilcox ex-amined from a safety standpoint, 'mder the conditions of a Stoderator Dilution Accident, the feasibility of lowering the refueling boron concentration from the present value of 2270 ppm.

The Stoderator Dilution Accident during refueling is defined as the dumping of one full makeup tank of deborated water into a reactor vessel volume, at refueling conditons, and determining the change in core reactivity.

Attached is a proposed FSAR revision to Table 14-8 on Page 14-61 which summarizes under Iter C, Dilution at Shutdown, the results for several initial boron concentration conditions examined by Babcock 5 Wilcox. This revised FSAR page will be included in the next amend-ment to the CR#3 Final Safety Analysis Report.

The results identified in Table 14-8 will be used as the basis for lowering the refueling boron concentration contained in CR#3 Standard Technical Specification 3.9.1.b from the present value of 2270 ppm.

If you require additional discussion or clarification of our sub-mittal, please do not nesitate to contact this office.

Very truly yours, J. . Rodgers Asst. Vice President JTR/iw Attachment.

NA5N General Office 3201 Thirty-fourtn street soutn . P.O. Box 14042. St. Petersburg, F!onda 33733 813-866-5151

PROPO.c^9 FSAR CHANGE - AMENDMENT u 50 -

. . .- Tablo 14-8 Summary of Modarator Dilution Accident Anal,.5is Q uJk O dkg.b to- 2L6-16 A. Dilution at Power Average Reactor Dilution Water Reactivity Rate, Coolant System Condition Flow, gpm (zwk/k)/s Temp Change, *F/s Normal 70 +1.72 x 10-6 0,005 Low RCS 100 +2.45 x 10-6 0.008 Pressure Maximum 500 +1.227 x 10-5 0.034 Considered B. Dilution to Trip Dilution Water Peak Thermal Power, Peak Pressure Time to Flow, gpm Percent of Rated psia Trip 70 103.2 2440 111 500 106.3 2452 48 C. Dilution at Shutdown Initial Boron Initial Total Final Boron Final Total Concentration Subcriticality Concentration Subcriticality 1637 ppm -5% 1426 ppm -2.19%

1800 ppm -7.17% 1568 ppm -4.08%

2270 ppm -13.44% 1977 ppm -9.54%

The results are based on the following assumptions:

(a) cold (70 ), BOL, all rods out of the core ,

(b) emptying 1 full makeup tank volume of 600 ft. i Table 14-9 Pump Startup Accident Parameters Moderator Coefficient, (a k/k/ F -4.0 x 10-4 Doppler Coefficient, (6 k/k/ F -1.3 x 10-5 Table 14-10 Summary of Pump Startup Accident Analvsis Maximum Neutron Power (at 7 s), % 79 Maximum Thermal Power (at 8 s), % 65 Maximum Pressure Rise (at 12 s), psi 150 14-61