ML16314A521
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V17 Page 1 of 5 Southern Nuclear Design Calculation Plant: Vogtle Unit: 1&2 Calculation Number: X6CNA 14 Sheet: 46 Miscellaneous Design Inputs 21 . Iodine boiling point= 1B4 C = -363 F
Reference:
Page B-1 , "CRC Handbook of Chemistry & Physics"
- 22. Density of Refueling Cavity and Spent Fuel Pool Water@ 130 F = 61 .SS lbm/cu ft
Reference:
See Attachment C2 .
- 23. Density of CVCS letdown flow= 0.99 glee (Attachment C2)
Reference:
The density is used to convert the letdown activity from µCi/g to µCi/cc, which are the units used by the CVCS letdown rad monitor RE-4BOOO (Design Input #1 &
Attachment CS). Based on at-power CVCS letdown parameters from the Unit 1 and 2 IPCs (Attachment CS), the average temperature and pressure at the radiation measurement location are 9B.S F and 3BS psig .
24 . Average Decay Gamma Energies for RE-4BOOO principle isotopes (Attachment CB)
Isotope Average
Reference:
Brookhaven National Laboratory National Gamma Nuclear Data Center decay data Energy (httQ://www.orau.org/QtQ/PTP%20Librarv/librarv/DOE/bnl/nu (MeV) clidedata/table.htm )
Copies of web pages in Attachment CB 1-131 0.3B2 1-132 2.20 1-133 0.607 1-134 2.SO 1-135 1.SS Co-5B 0.97S Co-60 2.S1 Cs-134 1.SS Cs-136 2.12 Cs-137 O.S6S Cs-13B 2.31
V17 Southern Nuclear Design Calculation Page 2 of 5 Plant: Vogtle Unit: 1&2 Calculation Number: X6CNA 14 Sheet: 61 Recognition Category S: System Malfunctions Notice of Unusual Event SU4 : Fuel Clad Deg radation .
Operating Mode Applicability: Power Operation (Mode 1)
Startup (Mode 2)
Hot Standby (Mode 3)
Hot Shutdown (Mode 4)
Emergency Action Levels : 1 OR 2 SU4 EAL 1: CVCS Letdown radiation mon itor RE-48000 reading greater than 5 µCi/cc indicating fuel clad degradation greater than Technica l specification There are two Technical Specification limits on RCS coolant activity:
- SR 3.4 .16.1: Gross specific activity < 100/t= µCi/gm
- SR 3.4 .16.2: Dose Equivalent 1-131 (DE 1-131) < 1.0 µCi/g Per section B.3.4 .16, page 83.4.16-2 of VEGP Tech Spec Bases, noble gas activity in the reactor coolant assumes 1% failed fuel , which closely equals the LCO limit of 1001r; µCi/gm for gross specific activity.
The EAL threshold will be calculated for each Tech Spec limit condition .
Per pages 12 and 13 I I of X6AZ01 A, the ,_
principle detected isotopes by RE-I
_,....-....- --- : I i/ I i
48000 are 1-131 , 1- ) I 133, Co-58 , Co-60, I I
Cs-134 , and Cs-137. .I I I I
I However, per Section I i
I I I
B-12-3-2 and Figure
- ' I I
I B-12-2 of 1X6AZ01- l 10004 & 2X6AZ01- i j I'
10004, RE-48000 will detect gammas of I :I. I C. :l 0 .3 O.
- 0 . :5 o.*
0 .'T I
- J.a I
0 .!1 '
- 1. 0 ... 1. 2 energies down to (NCRGY t...EV£L. Uh \I )
-0.1 MeV.
Figure B-12-2 Thus the other I, Co, and Cs isotopes listed in FSAR Table 11 .1-2 should be included if their average decay gamma energies exceed 0.1 MeV.
V17 Southern Nuclear Design Calculation Page 3 of 5 Plant: Vogtle Unit: 1&2 Calculation Number: X6CNA 14 Sheet: 62 Per LTR-CRA-06-179 attached to WEC-SNC letter GP-18006 , the pre-MURPU coolant activities may be adjusted upward 2% to account for the increase in core thermal power from 3565 MWt to 3636 MWt. Thus , the Co and Cs MURPU 1% defect activity are equal to their pre-MURPU 1% Defect activities multiplied by 1.02 .
The Co and Cs activities corresponding to the 1.0 µCi/g DE 1-131 Tech Spec limit are the products of their MURPU 1% defect activities and the ratio of the 1-131 DE 1-131 concentration to its equilibrium concentration (0 .74/2 .91 ).
The activities, expressed in µCi/g are summed and then multiplied by the CVCS letdown flow density (0.99 glee) to convert them to µCi/cc.
The EAL threshold is the minimum of the 1% Defect and the 1.0 µCi/g DE 1-131 activities .
1.0 µCi/g MURPU Pre-MURPU DE 1-131 1% Defect 1% Defect Isotope Coolant Coolant Coolant Activity Activity Activity
(µCi/g) (µCi/g) (µCi/g) 1-131 0.74 2.91 1-132 0.75 2.96 1-133 1.41 5.56 1-134 0.18 0.69 1-135 0.69 2.72 Co-58 3.89E-03 1.53E-02 1.50E-02 Co-60 4.93E-04 1.94E-03 1.90E-03 Cs-134 5.97E-01 2.35 2.3 Cs-136 7.52E-01 2.96 2.9 Cs-137 3.89E-01 1.53 1.5 Total= 5.5 21 .7 µCi/g Total= 5.5 21.5 µCi/cc CVCS Letdown Density = 0.99 glee Given the RG 1.97 R2 required system accuracy (Acceptance Criterion 3) ,
the threshold is rounded down from 5.5 to 5 µCi/cc.
NOTE: SU4 EAL2 not determined in this calculation.
V17 Southern Nuclear Design Calculation Page 4 of 5 Plant: Vogtle Unit: 1&2 Calculation Number: X6CNA 14 Sheet: CS-1 Attachment C5 - VEGP 1&2 CVCS Letdown Radiation Monitor (RE-48000) Readings
V17 Southern Nuclear Design Calculation Page 5 of 5 I Plant: Vogtle Unit: 1&2 Calculation Number: X6CNA 14 Sheet: C5-2 I Attachment C5 - VEGP 1&2 CVCS Letdown Radiation Monitor (RE-48000) Readings I I
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V18 Page 1 of 3 RCS Specific Activity 3.4 .16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4 .16 The specific activity of the reactor coolant shall be within limits.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tav 9 ) ~ 500°F.
ACTIONS
N 0 TE--------------------------------------------------------
LCO 3.0.4c is applicable .
CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1-131>1.0 µCi/gm . EQUIVALENT 1-131 within the acceptable region of Figure 3.4 .16-1 .
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.
B. Gross specific activity of B.1 Perform SR 3.4 .16.2. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the reactor coolant not within limit. AND B.2 Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Tav9 < 500°F.
(continued)
Vogtle Units 1 and 2 3.4.16-1 Amendment No. 137 (Unit 1)
Amendment No. 116 (Unit 2)
l V18 I Page 2 of 3 RCS Specific Activity 3.4 .16 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Tavg < 500°F.
Time of Condition A not met.
OR DOSE EQUIVALENT 1-131 in the unacceptable region of Figure 3.4 .16-1 .
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4 .16.1 Verify reactor coolant gross specific In accordance with activity ~ 100/E µCi/gm . the Surveillance Frequency Control Program SR 3.4 .16.2 ----------------------------N 0 TE-----------------------------
0 nly required to be performed in MODE 1.
Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance with specific act i vity ~ 1.0 µCi/gm . the Surveillance Frequency Control Program Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of ~ 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period (continued)
Vogtle Units 1 and 2 3.4 .16-2 Amendment No. 158 (Unit 1)
Amendment No. 140 (Unit 2)
V18 Page 3 of 3 RCS Specific Activity 3.4 .16 250
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- 200 UNACCEPTABLE
~ OPERATION
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20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4.16-1 REACTOR COOLANT DOSE EQUIVALENT 1-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACITVITY >1 mCi/gram DOSE EQUIVALENT 1-131 Vogtle Units 1 and 2 3.4 .16-4 Amendment No. 96 (Unit 1)
Amendment No. 74 (Unit 2)
V19 Page 1 of 1 RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:
- a. No pressure boundary LEAKAGE;
- b. 1 gpm unidentified LEAKAGE;
- c. 10 gpm identified LEAKAGE; and
- d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A RCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LEAKAGE not within within limits.
limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR Pressure boundary LEAKAGE exists.
OR Primary to secondary LEAKAGE not within limit.
Vogtle Units 1 and 2 3.4.13-1 Amendment No. 144 (Unit 1)
Amendment No. 124 (Unit 2)
V20 Page 1 OF 1 ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 7)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- a. Manual 1,2,3 ,4 2 B SR 3.3.2.6 NA NA Initiation
- b. Automatic 1,2,3,4 2 c SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays
- c. Containment Pressure High - 3 1,2,3 4 E SR 3.3.2.1 ~ 22.4 psig 121 .5 psig I SR 3.3.2.4Q>Gl SR 3.3.2.7Ql01 (continued)
(i) If the as-found channel setpoint is outside its predefined as-found tolerance , then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service .
Gl The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance ; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in NMP-ES-033-006 , Vogtle Setpoint Uncertainty Methodology and Scaling Instructions .
Vogtle Units 1 and 2 3.3.2-10 Amendment No. 165 (Unit 1)
Amendment No. 147 (Unit 2)