ML19308D672
| ML19308D672 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/12/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003120748 | |
| Download: ML19308D672 (4) | |
Text
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u.s. NUCLEAR 7.ECULATORY 8
' MISSIOld DOCKET NUMiEn 50-302 NHC Fonu 195 (2 7ty 4..
NRC DISTRIBUTION FoR PART 50 DOCKET MATERI AL oATE or occuuENT FROM:
To: Mr. John Stolz Flordia Power Corp.
11-12-76 St. Petersburg, Fla, 33733 DATE RECEIVEo J.T. Rodgers 11-(15-76 R ETTER C f40 TOR f 2 E D PROP 6NPUT FOHM NUMBER OF COPtES RECELVED tzD R IGIN A L DU NC L ASSIF I E D 1 Si ed Ocoev Proposed FSAR Change-Amdt #50 re ocsCReerson Ltr trans the following:
E NCLOSU RE Table 14-8 entitled Summary of Moderator Dilution Accident Analysis....
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Subject:
Crystal River Unit #3
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Docket No. 50-302
Dear Mr. Stolz:
On October 26, 1976, Florida Power Corporation (FPC) submitted a proposed FSAR revision to Table 14-8 on Page 14-61, which summarized under Item C, Dilution at Shutdown, the results for several initial boron concentration conditions examined by Babcock 4 Wilcox.
The results identified in Table 14-8 were to be used as the basis for lowering the refueling boron concentration contained
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in CR#3 Standardized Technical Specification 3.9.1.b from the present value of 2270 ppm.
Since our October 26, 1976 submittal, a new soluable boron level condition, corresponding to cold, Keff = 1.00, no CRA in, was defined.
Therefore, a reassessment of the refueling boron concentration was performed by Babcock 4 Wilcox.
The results of this assessment show that the core will remain subcritical if one makeup tank of demineralized water is emptied into the reactor vessel (Moderator Dilution Accident) initially at Keff =.95 with 1875 ppm boron concentration.
l'.L61b General Office 3201 Thirty-fourtn street soutn. P.O. Box 14042. St. Petersburg, F!crica 33733 e G13-866-5151 c
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2-November 12, 1976 Mr. John Stol:
Attached is Table 14-8 which has been revised under Item C, Dilution of Shutdown, to include the results of this latest B6W reassessment of the refueling boron concentration.
This revised FSAR page will be included in the next amendment to the CR# 3 Final Safety Analysis Report.
If you require additional discussion or clarification of our-submittal, please do not hesitate to contact this office.
Very truly yours,
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Ro gers Asst. Vice President JTR/iw Attachment.
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FRUPU5td> 1-bAR CHANGE - AMENDWENT NO. 50 Tablo 14-8 N *'2i f
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Summary of Modarator Dilution.Accidant.An:rlysis (tegui g. q v. -
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Dilution at Power ll 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
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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 Suberiticality Concentration Subcriticality
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1875 ppm
-5%
1633 ppm
-1.78%
2270 ppm
-10.26%
1977 ppm
-6.36%
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.3 Table 14-9 Pump Startuo Accident Parameters Moderator Coefficient, (a k/k/*F
-4.0 x 10-4 Doppler Coefficient, (4 k/k/ F
-1.3 x 10-5 Table 14-10 Summary of Pump Startuo Accident Analysis Maximum Neutron Power (at 7 s), %
79 Maximum Thermal Power (a t 8 s), %
65 Maximum Pressure Rise (a t 12 s), psi 150
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14-61