ML17263A213
| ML17263A213 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/08/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9304130387 | |
| Download: ML17263A213 (12) | |
Text
-, accmzawmo OoeVMKm" MSx mrOX SvsxKM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9304130387 DOC.DATE: 93/04/08 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Forwards info summarized from Design Analysis DA-NS-92-133-00 in response to 930303 telcon w/NRC re 921217 application for amend to License DPR-18,demonstrating margin available between min required BAST vol
& inventory.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR I ENCLI SIZE: 7 TITLE: OR Submittal: General Distribution D
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
/
05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR'NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N, Y. 14649-0001 ROBERT C. MECREDY Vice President Clnna Nudear Production April 8, 1993 TELERtONE AAEACOOE 7to 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:Allen R. Johnson PWR Project Directorate I-3 Washington, D.C.
20555
Subject:
Additional Information Request Elimination of High Concentration Boric Acid R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):
Application for Amendment to Facility Operating License for Revision to Technical Specification Section 3.2 and 3.3., letter dated Dec.
17, 1992.
Dear Mr. Johnson:
Reference (a) requested a revision to Technical Specifications to allow elimination of high concentration boric acid.
During the review process, by a
March 3,
1993 telephone
- call, the staff requested calculations to support the minimum required volumes presented on Table 3.2-1.
That information summarized from Design Analysis DA-NS-92-133-00, is attached.
The attachment demonstrates the margin available between the minimum required Boric Acid Storage Tank(s) volume and the inventory necessary to maintain the required shutdown margin.
Very~ ruly yours, Robert C.
ecredy RWEi271 Attachment xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA.
19406 U.S.
NRC Ginna Senior Resident Inspector 9304i30387 930408 PDR ADOCK,,05000244 P
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ATTACHMENT Calculation of Required Boric Acid Volumes
The discussion below provides the basis for the calculation of the required boric acid volumes in proposed table 3.2.
The calculations are based upon a
solution to the rate equation where the change in RCS boron concentration is a function of the amount and concentration of the boric acid solution being added.
The following calculations determine the amount of source mass required to achieve the desired concentration.
Additional mass is added to compensate for shrinkage during the cooldown process.
The following illustrates the calculation of the RCS mass hot and cold, and the corrections made to account for the density of the boric acid solution.
Calculation of Reactor Coolant S stem Mass Total RCS Volume Pressurizer Volume Steam Water (HFP 49~)
Water (HZP 19.54) r Volume Control Tank (VCT) 6245 cubic feet 800 cubic feet 320
- 480, 283 200 cubic feet UFSAR Table 1.3-1 UFSAR Table 5.4-7 UFSAR Table 9.3-7 The mass calculation will be performed at zero power temperatures for the
- RCS, saturation temperature for the pressurizer and at letdown temperature for the VCT (150 degrees F).
Density at 547 degrees and 2250 psia =
47.05 ibm/cft Density of saturated liquid at 2250 psia =
37.07 ibm/cft Density at 150 degrees and 50 psia =
61.20 ibm/cft The total RCS mass is-then calculated as follows:
RCS:
(6245-800) x 47.05
=
256,187 ibm VCT:
200 x 61.20 Total RCS Mass
=
Pressurizer:
283 x 37.07
=
10,491 ibm 12,240 ibm 278,918 ibm Note for the VCT volume liquid level is normally maintained at about 304.
The additional volume is added for miscellaneous piping volume and conservatism.
~ ~
Boric Acid Densit Correction Each mass of borated liquid will be corrected for the density change due to the boric acid concentration.
This correction factor is based on the ratio of the density of water with 21000 ppm boron to the density of pure water.
This ratio is 1.0416 and varies linearly with boron concentration Therefore each borated water density will be multiplies by a factor calculated as follows:
1.0 + (.0416 x boron concentration/21000)
Calculation of Re uired Source Mass The calculation are based on the solution of the following simplified system:
~cg C~
Vc7-MassR~
= mass of the RCS (lb. )
CR = boron concentration in RCS (ppm) m' letdown/charging rate (lbs/hr)
C = charging line concentration (ppm) x = flow rate of concentrated boric acid (lbs/hr)
SR = Boric acid tank boron concentration (ppm)
MassR~
dCR = m'C m'CR dt m'C = (m' x)
CR + x CRA MassR~
dCR = x (CRA CR) dt MassRcs integrating over the change in concentration C~t 4C dCR = x dt CRA CR C~
xt = Massa~
1n
[ CD-C~]
CGA (CR + ZC)
If the Required Source Mass
= xt then Required Source Mass
= MassR~ x ln (Sb RCS.)/(Sb RCS)
where:
S, = Source boron concentration RCS = Initial RCS concentration RCS = Final or desired RCS concentration Mass~~ = Total RCS Mass (corrected for RCS,;)
Calculation of Re uired Source Gallons The required source mass is divided by the boric acid corrected density and multiplied by the conversion factor to yield required source gallons.
For all calculations for proposed Table 3.2 a source temperature of 150 degrees was assumed.
Therefore the required source gallons would be calculated as follows:
(Required Source Mass)/(61.20 x BA Correction Factor) x 7.4805 Calculation of Re uired Makeu Gallons from HZP to Cold Shutdown The discussion above calculates the required gallons of boric acid to raise the RCS boron concentration to the level that maintains the shutdown margin during the cooldown from HZP.
The next step is to calculate the gallons of boric acid required to mix with makeup water to maintain the RCS volume and boron concentration as the mass in the RCS shrinks as temperature is reduced.
This is calculated by taking the difference in the RCS mass at hot and cold conditions and multiplying by the ratio of desired concentration to source concentration.
Total RCS volume (cold) is 6059 cft.
To this is added the 200 cft volume of the VCT.
The boric acid corrected density of the fluid is based on water at 200 degrees and 15 psia (60.10 ibm/cft).
(6059
+ 200) x 60.10
= 376,166 ibm Therefore the gallons required for cooling from hot to cold shutdown is calculated as follows:
RCS mass cold-RCS mass hot x RCS conc Source conc x 7.4805 Boric Acid corrected Source Density Where the mass hot and mass cold are corrected for final RCS boron concentration.
The attached table provides the results of this calculation for the maximum required change in boron concentration,
Re ired Chan e in Boron Concentration As noted in the basis of the proposed Technical Specification, the required change in boron concentration was determined based on limiting conditions that result in maximizing the required change in RCS boron concentration.
These limiting conditions are as follows:
1.
The change occurs early in core life where the difference between the RCS concentration and source concentration is minimized.
2 ~
3.
The initial RCS boron concentration assumes a reduction from the hot full power concentration sufficient for the reactor to be critical at peak xenon following a trip from full power.
The final RCS boron concentration is sufficient to maintain the reactor 2.45%
shutdown at cold (68'F) no xenon conditions.
The shutdown requirement is conservative assuming single loop operation during the
- cooldown, applying a
shutdown criterion more limiting than the minimum 14 cold shutdown requirement in Technical Specifications and using a
68'F reference temperature instead of 200 F.
These conditions resulted in identifying the required boron change as 772 to 1245 ppm for Cycle 22.
For comparison the figure from the Westinghouse Nuclear Design Report indicating required boron concentrations is attached.
Note that the 1245 ppm requirement is at least 50 ppm greater than the nominal requirement of the figure and the figure requirements already contain an additional 100 ppm for uncertainties in the calculation.
Each fuel cycle's requirements are reviewed against the Technical Specifications to insure compliance.
Significant margin remains between the Technical Specification required gallons and the gallons required for Cycle 22.
This is sufficient allowance for changes in fuel cycle requirements.
Densities and mass given below are without the BA correction Source Density (150 F,15 psia) 61.2 ibm/cft RCS Mass (547 F, 2250 psia)
RCS Mass (200 F, 15 psia) 278918 ibm 376166 ibm Source Conc Initial RCS Conc Final RCS Conc Hot Gal Cold Gal Total Gal 4700 5000 6000 7000 8000 9000 10000 11000 12000 13000 14000 15000 16000 17000 18000 19000 20000 21000 22000 772 772 772 772 772 772 772 772 772 772 772 772 772 772 772 772 772 772 772 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 1245 4341 4011 3200 2660 2275 1986 1762 1582 1435 1313 1210 1121 1044 977 918 865 818 776 737 3127 2938 2444 2090 1826 1620 1455 1320 1208 1113 1031 961 899 844 796 753 714 678 646 7468 6949 5644 4750 4100 3606 3216 2902 2643 2426 2241 2082 1943 1821 1714 1618 1532 1454 1384
12N 1000 800 CI I
UJ CP
~ 6N C)
CO 2.45/
N-1 Shutdown Naroln 1.88/
N-1 Shutdown Hargln
.88/
N-1 Shutdown Nar in 0
1000 2000 3000 4000 5000 60DD 7000 8NO 9NO 10000 CYCLE BURNUP (ND/QTU)
Shutdown Boron Concentrations vs. Cycle Burnup at Cold, No Xenon Conditions
'0