ML16314A517

From kanterella
Jump to navigation Jump to search
Calculation SNC024-CALC-004, VEGP Determination of Emergency Action Level for Initiating Condition E-HU1
ML16314A517
Person / Time
Site: Hatch, Vogtle, Farley  Southern Nuclear icon.png
Issue date: 11/03/2016
From:
Enercon
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16314A191 List:
References
X6CNA15 SNC024-CALC-004
Download: ML16314A517 (8)


Text

X6CNA15 Attachment L ENERCON Calculation for E-HU1 SHEET L-6 v14 Page 1of3 CALC NO.

SNC024-CALC-004 VEGP DETERMINATION OF EMERGENCY ACTION LEVEL REV.

0 ENERCON FOR INITIATING CONDITION E-C.i<.t.'k... 't."..."

f.-..* *.~;.1:v,.;."t ~.~*/tJV";.

HU1 PAGE NO.

Page 6 of 8 5.0 Design Inputs

1. The contact dose rates from the HI-STORM 100 and HI-TRAC 125 cask system technical specification [2, Table 6.2-3] are provided below in Table 5-1. These source values are scaled to develop the emergency action levels for initiating condition E-HU1.

Table 5-1 Technical Specification (Neutron +Gamma) Dose Rate Limits for HI-STORM 100 and HI-TRAC 125 Location Number of Technical Specification Measurements Limit (mrem/hr)

HI-TRAC 125 Side - Mid - height 4

472.7 Top 4

102.4 HI-STORM 100 Side - 60 inches below mid-height 4

87 Side - Mid - height 4

88.9 Side - 60 inches above mid-height 4

54.8 Top - Center of lid 1

24.5 Top - Radially centered 4

29.2 Inlet duct 4

178.8 Outlet duct 4

64.5

X6CNA15 Attachment L ENERCON Calculation for E-HU1 SHEET L-7 V14 Page 2 of 3 CALC NO.

SNC024-CALC-004 VEGP DETERMINATION OF EMERGENCYACTIONLEVEL RE~

FOR INITIATING CONDITION E-0 ENERCON HU1 PAGE NO.

Page 7 of 8 6.0 Methodology The "on-contact" dose rates from the technical specification for the HI STORM-100 cask system are scaled by a factor of 2, as specified in NEI 99-01 Rev. 6 [1], for use in initiating condition E-HU1.

X6CNA15 Attachment L ENERCON Calculation for E-HU1 V14 SHEET L-8 Page 3 of 3 CALC NO.

SNC024-CALC-004 VEGP DETERMINATION OF EMERGENCY ACTION LEVEL REV.

FOR INITIATING CONDITION E-0 ENERCON HU1 PAGE NO.

Page 8 of 8 7.0 Calculations The dose rates in Table 5-1 are multiplied by 2 in order to calculate the EAL dose rate limits. These calculations are presented below in Table 7-1.

Table 7-1 Dose Rate Scaling Calculations for EAL Limits Technical Location Specification Scaling Calculated Value EAL Limit Factor (mrem/hr)

(mrem/hr)

(mrem/hr)

HI-TRAC 125 Side - Mid - height 472.7 2

945.4 950 Top 102.4 2

204.8 200 HI-STORM 100 Side - 60 inches below mid-height 87 2

174 170 Side - Mid - height 88.9 2

177.8 180 Side - 60 inches above mid-height 54.8 2

109.6 110 Top - Center of lid 24.5 2

49 so Top - Radially centered 29.2 2

58.4 60 Inlet duct 178.8 2

357.6 360 Outlet duct 64.5 2

129 130 8.0 Computer Software Microsoft WORD 2013 is used in this calculation for basic multiplication.

Approved By J. B. Stanley Effective Date Vogtle Electric Generating Plant Procedure 19200-C Page Number V15 Page 1 of 4 Version 24.2 7/25/12 F-0 CRITICAL SAFETY FUNCTION STATUS TREES 5 of 11 Sheet 1 of 1 F- 0.2 CORE COOLING NO

-+ CORE EXIT TCs LESS THAN 1200<>F Printed February 2, 2016 at 16:09 YES AT LEAST ONE RCP RUNNING RCS SUBCOOLING NO GREATER THAN 24'>F (3BoF)

YES RVLIS FULL NO RANGE GREATER THAN 41%

YES NO CORE EXIT TCs LESS THAN 711~F NO YES YES RVLIS FULL RANGE GREATER THAN41%

RVLIS DYNAMIC HD RANGE

>44%*4 RCP

>30% *3 RCP

>20% *2 RCP

> 13%

'+Q)

NO YES

.{9 r+Q)

NO YES

. {!;)

GOTO 19221-C GOTO 19221-C GOTO 19222-c GOTO 19222-C GOTO 19223-C GOTO 19222-C GOTO 19223-C CSF SAT

Approved By J. B. Stanley Effective Date 7/25/12 Vogtle Electric Generating Plant F-0 CRITICAL SAFETY FUNCTION STATUS TREES F- 0.3 HEAT SINK TOTAL AVAILABLE FEEDWATER FLOW TO SGs GREATER THAN 570 GPM NARROW RANGE NO NO YES V15 Page 2 of 4 Procedure Version 19200-C 24.2 Page Number 6 of 11 Sheet 1 of 1 GO TO 19231-C

---tlilll* LEVEL IN AT LEAST,__ _

ONE SG GREATER THAN 10% (32%)

  • .............. {9 GO TO 19232-C Printed February 2, 2016 at 16:09 YES PRESSURE IN ALL SGs LESS THAN 1240 PSIG NO YES

~GOTO Jl"'u 19233-C NARROW RANGE NO LEVEL IN ALL SGs,__ _

LESS THAN 82%

YES NO PRESSURE IN ALL SGs LESS THAN 1180 PSIG YES NARROW RANGE NO LEVEL IN ALL SGs GREATER THAN 10% (32%)

YES GO TO 19234-C GO TO 19235-C CSF SAT

V15 Page 3 of 4 Approved By J. B. Stanley Vogtle Electric Generating Plant Procedure 19200-C Version 24.2 Effective Date Page Number 7/25/12 F-0 CRITICAL SAFETY FUNCTION STATUS TREES 7 of 11 F- 0.4 INTEGRITY NO ALL RCS PRESSURE -

WR COLD LEG TEMPERATURE POINTS TO RIGHT OF LIMIT A YES

.-----.Q)

TEMPERATURE DECREASE IN ALL

... RCS COLD LEGS LESS THAN 100°F IN THE LAST 60 MINUTES NO YES ALL RCS WR COLD LEG TEMPERATURES GREATER THAN 265 °F NO YES ALL RCS WR COLD LEG NO TEMPERATURES GREATER THAN 295°F YES

,-+Q)

ALL RCS WR COLD LEG NO TEMPERATURES GREATER THAN 265 °F YES RCS PRESSURE LESS THAN COLD OVERPRESSURE LIMIT 465 PSIG NO YES

. :...* Q)

RCS WR COLD LEG NO TEMPERATURE GREATER THAN 220 °F YES Printed February 2, 2016 at 16:09 Sheet 1 of 1 GO TO 19241 -C GO TO 19241-C GO TO 19242 -C CSF SAT GO TO 19241 -C GO TO 19242-C CSF SAT CSF SAT

Approved By J. B. Stanley Vogtle Electric Generating Plant Effective Date 7/25/12 F-0 CRITICAL SAFETY FUNCTION STATUS TREES CONTAINMENT

-~ I PRESSURE LESS THAN 52 PSIG NO F- 0.5 CONTAINMENT YES AT LEAST ONE CONTAINMENT SPRAY PUMP RUNNING NO YES

......... (9 CONTAINMENT PRESSURE LESS THAN 21.5 PSIG NO YES r--+Q)

I CONTAINMENT SUMP LEVEL LESS THAN 106 INCHES NO YES CONTAINMENT NO RADIATION LESS THAN 750 MR/HR YES Printed February 2, 2016 at 16:09 V15 Page 4 of 4 Procedure Version 19200-C 24.2 Page Number 9 of 11 Sheet 1 of 1 GOTO 19251-C GOTO 19251-C GOTO 19251-C GOTO 19252-C GOTO 19253-C CSF SAT

V16 Page 1 of 1 l'I