ML030340043

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Submittal of Revisions to Emergency Plan and Implementing Procedures
ML030340043
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 01/24/2003
From: Izyk C
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
Download: ML030340043 (29)
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Text

ENTERGY NUCLEAR NORTHEAST JAMES A. FITZPATRICK NUCLEAR POWER PLANT P.O. BOX 110 LYCOMING, NY 13093 DOCUMENT TRANSMITTAL AND RECEIPT ACKNOWLEDGEMENT FORM DATE: JANUARY 24, 2003 CONTROLLED COPY NUMBER: 34 TO:

FROM:

U.S.N.R.C. Document Center/Washington, DC CATHY IZYK - EMERGENCY PLANNING DEPARTMENT

SUBJECT:

EMERGENCY PLAN AND IMPLEMENTING PROCEDURES Enclosed are revisions to your assigned copy of the JAFNPP Emergency Plan and Implementing Procedures. Please remove and DISCARD the old pages. Insert the attached, initial and date this routing sheet and return the completed routing sheet to Cathy izyk in the Emergency Planning Department within 15 days. If this transmittal is not returned within 15 days, your name will be removed from the controlled list.

V0 V

IVIF1H rlt I

iis Dae 2

2003 DOCUMENT PAGES REV. #

INITIALS/IDATE SECTION 4 REPLACE ALL 18 VOLUME 2 Update List Dated JANUARY 24, 200,3 DOCUMENT PAGES REV.#

INITIALS/DATE EAP-4.1 REPLACE ALL 15 1

1 V(31 IiMFI=

llnr1~t*_I itifl tAtd JANUARY 24. 2003 I

I I

ýOtf 5

EMERGENCY PLAN IMPLEMENTING PROCEDURES/VOLUME 2 UPDATE LIST I CONTROLLED COPY #

I Date of Issue:

January 24, 2003 Date of Ueo Procedure Procedure Revision Lat PoeUse of Number Title Number Procedure Review N/A TABLE OF CONTENTS REV. 19 02/98 N/A IAP-1 EMERGENCY PLAN IMPLEMENTATION REV. 28 08/02 Continuous CHECKLIST CLASSIFICATION OF EMERGENCY IAP-2 REV. 23 08/02 Continuous CONDITIONS EAP-1.1 OFFSITE NOTIFICATIONS REV. 46 08/02 Informational EAP-2 PERSONNEL INJURY REV. 26 01/03 Informational EAP-3 FIRE REV. 23 08/02 Informational EAP-4 DOSE ASSESSMENT CALCULATIONS REV. 31 08/02 Reference EAP-4.1 RELEASE RATE DETERMINATION REV.

15 01/03 Reference EAP-5.1 DELETED (02/94)

EAP-5.2 DELETED (04/91)

EAP11-5.3 ONSITE/OFFSITE DOWNWIND SURVEYS REV.

9 08/02 Informational AND ENVIRONMENTAL MONITORING EAP-6 IN-PLANT EMERGENCY SURVEY/ENTRY REV.

16 06/02 Informational EAP-7.1 DELETED (02/94)

EAP-7.2 DELETED (02/94)

EAP-8 PERSONNEL ACCOUNTABILITY REV. 59 12/02 Reference EAP-9 SEARCH AND RESCUE OPERATIONS REV.

10 08/02 Informational EAP-10 PROTECTED AREA EVACUATION REV.

16 08/02 Informational EAP-I1 SITE EVACUATION REV.

18 08/02 Informational DOSE ESTIMATED FROM AN ACCIDENTAL EAP-12 RELEASE OF RADIOACTIVE MATERIAL TO REV.

11 04/02 Reference LAKE ONTARIO EAP-13 DAMAGE CONTROL REV.

14 06/02 Informational EAP-14.1 TECHNICAL SUPPORT CENTER REV. 22 04/02 Informational ACTIVATION EAP-14.2 EMERGENCY OPERATIONS FACILITY REV. 20 04/02 Informational ACTIVATION EAP-14.5 OPERATIONAL SUPPORT CENTER REV.

14 03/00 Informational ACTIVATION AND OPERATION Page 1 of 2

EMERGENCY PLAN IMPLEMENTING PROCEDURES/VOLUME 2 UPDATE LIST Date of Issue:

January 24, 2003 Procedure Number r

.Y.

Procedure Title,

Revision Number Date of Last Review Use of Procedure EAP-14.6 HABITABILITY OF THE EMERGENCY REV.

14 10/98 Informational FACILITIES EAP-15 EMERGENCY RADIATION EXPOSURE REV.

11 06/02 Informational CRITERIA AND CONTROL EAP-16 PUBLIC INFORMATION PROCEDURE REV.

6 02/98 Informational EAP-16 2 JOINT NEWS CENTER OPERATION REV. 0 02/02 Informational EAP-17 EMERGENCY ORGANIZATION STAFFING REV. 103 12/02 Informational EAP-18 DELETED (12/93)

EAP-19 EMERGENCY USE OF POTASSIUM IODINE REV. 21 04/01 Informational (KI)

EAP-20 POST ACCIDENT SAMPLE, OFFSITE REV.

9 06/02 Reference SHIPMENT AND ANALYSIS EAP-21 DELETED (12/85)

EAP-22 DELETED (02/98)

EAP-23 EMERGENCY ACCESS CONTROL REV. 11 06/02 Informational r --

EAP-24 V

VEHICLE AND PERSONEL 9

06/02 Informational DECONTAMINATION EAP-25 DELETED (02/94)

Page 2 of 2

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A.

FITZPATRICK NUCLEAR POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE RELEASE RATE DETERMINATION EAP-4.1 REVISION 15 REVIEWED BY:

PLANT OPERATING REVIEW COMMITTEE MEETING NO.

N/A DATE:

APPROVED BY:

I-,

DATE:

i-RESPONSIBLE PROCEDURE OWNER EFFECTIVE DATE:

94wim W

Z 63 FIRST ISSUE El FULL REVISION 01 LIMITED REVISION El INFORMATIONAL USE ADMINISTRATIVE CONTROLLED #

PERIODIC REVIEW DATE:

N/A TSR JUNE 2007

-k 41 -)1 4- -k -k + -k * * * * * * * * * * * * * * * * * * * *

  • RELEASE RATE DETERMINATION EAP-4.1 REVISION

SUMMARY

SHEET REV.

NO.

15 a On Attachment 3 in the Note section changed the following items:

added (1298 cc/sec) after 1.5% per day and changed RO-13 to RO-15 and changed the containment leak rate from -

1,437 to -1,569.

  • Also, on attachment three deleted reference to Tech Spec's per section 3.2.a, volume 1B because of implementation of the ITS Program and a referenced the document Offsite Dose Calculation Manual (ODCM).
  • Also in attachment three in the box Attachment 4 Location on Graph -

containment volume was changed to 7.4.8E-9cc.

14 0 Added wording to note in attachment 3

  • Made editorial corrections from (Hr) to (hr),

(MI/HR) to (MPH) and bolded THEN's

  • Changed reference from page 8 to page 7 on attachment
2.

13 0 Changes are made due to Improved Technician Specification (ITS) program.

  • On Attachment 1, page one added words "([CTS]

Technical Specifications, Appendix B, Section 3.2.a.1

[ITS] 5.5.4)"

12 0 On Attachment 11, page 1 of 2 and 2 of 2, changed Noble Gas Vent release to 1432 and changed Noble Gas Stack release to 333.

On page 24, added step 3 to show determination-for obtaining setpoint release rates that are described in the ODCM.

Rev.

No.

15 Page 2

of 26

RELEASE RATE DETERMINATION EAP-4.1 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE................................................

4

2.0 REFERENCES

4 3.0 INITIATING EVENTS......................................

4 4.0 PROCEDURE...............................................

5 4.1 Release Rate Determination.............................

5 4.2 Default Accident Source Terms.........................

12 4.3 Unmonitored Release...................................

13 5.0 ATTACHMENTS...........................................

13

1.

FLOW CHART TO DETERMINE RELEASE RATE FROM LOW RANGE EFFLUENT MONITORS..........................

14

2.

FLOW CHART TO DETERMINE RELEASE RATE FROM HIGH RANGE EFFLUENT MONITORS (HREM)....................

15

3.

WORK SHEET TO DETERMINE RELEASE RATE FROM CONTAINMENT RAD MONITORS.........................

16

4.

FITZPATRICK HRCRM READINGS.......................

17

5.

1.5% LEAKAGE SOURCE TERM ESTIMATE.................

18

6.

10% LEAKAGE SOURCE TERM ESTIMATE.................

19

7.

25% LEAKAGE-SOURCE TERM ESTIMATE.................

20

8.

50%-LEAKAGE SOURCE TERM ESTIMATE...................

21

9.

100% LEAKAGE SOURCE TERM ESTIMATE.................

22

10.

CATASTROPHIC LEAKAGE SOURCE TERM ESTIMATE........

23

11. CALCULATION METHOD FOR DETERMINING PERCENT OF TECHNICAL SPECIFICATION FOR NRC EVENT NOTIFICATION WORKSHEET...........................

24

12.

ANALYZED ACCIDENT TYPES..........................

26 Rev. No.

15 Page 3

of 26

RELEASE RATE DETERMINATION 1.0 PURPOSE This procedure provides instructions for manually estimating release rates in the event of an accidental release of radioactivity to the environment.

2.0 REFERENCES

2.1 Performance References None 2.2 Developmental References 2.2.1 EAP-5.3, ONSITE/OFFSITE DOWNWIND SURVEYS AND ENVIRONMENTAL MONITORING 2.2.2 EAP-42, OBTAINING METEOROLOGICAL DATA 2.2.3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.2.4 JAF FSAR Chapter 14 2.2.5 EAP-4, DOSE ASSESSMENT CALCULATIONS 2.2.6 High Range Containment Monitor Response to Post Accident Fission Product Releases -

James A.

FitzPatrick Nuclear Power Plant, SL-4370, Sergeant

Lundy, May 1985 3.0 INITIATING EVENTS 3.1 An emergency classification has been declared as defined in IAP-2, and 3.2 A release of radioactivity exceeding technical specifica tions is suspected or underway.

Page 4

of 26 EAP-4. 1 Rev. No.

15

RELEASE RATE DETERMINATION 4.0 PROCEDURE 4.1 Release Rate Determination NOTE:

Use Attachment 11 to calculate the percent of Tech.

Spec.

in order to determine if the Tech. Spec.

release rate has been exceeded and for completion of the NRC Event Notification Worksheet, EAP-I.I,.

4.1.1 Low Range Effluent Monitor calculation A.

Record date, time and name of individual performing calculations in upper right-hand corner of Attachment 1.

B. Record observed gross cdunt rate with appropriate units for the Reactor Building (RxB),

Refuel Floor (RF),

Radwaste (RW),

Turbine Building (TB) and/or Stack.

This data may be obtained from-the EPIC computer.

IF computer points are unavailable, Control Room AND/OR local monitors can be used for this data.

NOTE:

For stack releases, it is important to determine whether any dilution fan is operating.

C. For Building Vent Releases, multiply the gross count rate (cpm) by the default K factor listed in table on following page, until updated K factors are available based on recent chemistry sample data.

Rev. No.

15 Page 5

of 26 EAP-4.1

RELEASE RATE DETERMINATION D. For Stack Releases, multiply the-gross count rate (cps) by the default K factor listed below, unless an updated K factor is available based on recent Chemistry sample data.

Monitor K Factor Normal Flow RatesBased on (cfm)

Reactor 3.2E-1 61,000 Bldg. (Pt. 3337) pCi/sec/cpm Refuel 3.7E-1 70,000 Floor(Pt. 3338) pCi/sec/cpm Radwaste 1.7E-1 32,500 Bldg.(Pt. 3340) pCi/sec/cpm Turbine 5.6E-1 107,000 Bldg. (Pt. 3339) pCi/sec/cpm Stack(Pt. 3336) 6.OE-*

6,600

_Ci/sec/cps I

IF flow rates differ from the Normal Flow Rates listed above, THEN a correction to the K factor is necessary as follows:

K(corrected)

= F New Flow Rate X fK Factor (liste L Normal Flow Rate Page 6

of 26 EAP-4. 1 Rev.

No.

15

RELEASE RATE DETERMINATION NOTE:

The accuracy of ventilation flow rate indications at the low end of an instrument range should be confirmed with appropriate instrument calibration procedures.

E.

An estimate of the iodine release rate can be obtained by multiplying the I/NG ratio from a chemistry sample by the NG release rate.

IF a chemistry sample is not available, THEN the iodine release rate can be estimated by multiplying a default I/NG ratio by the NG release rate.

For default release rates and I/NG ratio, refer to Attachment 12.

F.

IF the low range effluent monitors are inopera tive or off-scale, THEN the appropriate high range effluent monitor must be used.

4.1.2 High Range Effluent Monitor (HREM)

Calculation A. Record date, time and individual performing calculation in upper right-hand corner of B.

Record observed dose rate for the Stack, Turbine Building (TB) and/or Radwaste (RW).

This data may be obtained from the EPIC computer.

IF computer points are unavailable, THEN Control Room monitors can be used for this data.

NOTE:

For stack releases, it is important to determine whether any dilution fan is operating.

C. Multiply the dose rate by the K factor listed below.

No.

15 Page 7

of 26 Rev.

EAP-4.1

RELEASE RATE DETERMINATION NOTE: These conversion constants are based on normal flow rates listed below.

A conversion factor of 0.45 (pCi/cc)/(mR/hr) was applied to the normal flow rate.

This value is given by General Electric and is based on the monitor response to Xe-133.

HREM K FACTOR NORMAL FLOW RATES (cfm)*

STACK One SGT train 1.40 (Ci/sec)/(mR/hr) based on 6,600 operating One SGT train and one stack 2.54 (Ci/sec)/(mR/hr) based on 12,000 dilution fan operating TURBINE BLDG 22.6 (Ci/sec)/(mR/hr) based on 107,000 RADWASTE BLDG 6.85 (Ci/sec)/(mR/hr) based on 32,500

  • IF flow rates differ from the Normal Flow Rates listed
above, THEN a correction to the K factor is necessary as follows:

[ Factor (listed]

K(corrected)

=

New Flow Rate1 x

[Normal Flow Rate I Rev.

No.

0. An esfimate of the iodine release rate can be obtained by multiplying the I/NG ratio from a chemistry sample by the NG release rate.

IF a chemistry sample is not-available, THEN the iodine release rate can be estimated by multiplying a default I/NG ratio by the NG release rate.

For default release rates and I/NG ratios, refer to Attachment 12.

E. A back calculated release rate may be estimated from field survey data in lieu of or in addition to the estimate from low and high range effluent monitors.

15 Page 8

of 26

" EAP-4. 1

RELEASE RATE DETERMINATION EAP-4.1 4.1.3 Back Calculations from Downwind Survey Dose Rate Data using EDAMS A. Start the EDAMS program and from the EDAMS icons, select "EDAMS".

NOTE:

The mouse does NOT work in this DOS Sub routine.

B. Select "Release Rate Calculations".

C. Select "James A. FitzPatrick".

D. Select "Back calculate".

E. Enter the time survey data was obtained (24-hour format).

F. Enter a number representing one of the accident types listed-G. Enter the wind-speed (MPH).

H. Enter "E" for elevated/stack or "G" for ground/vent release.

I.

Enter the stability class (A -

G).

J. Enter the three (3) foot closed window reading from the ion chamber (mR/hr).

K. Enter the downwind distance that the above reading was obtained.

(Use 0.87 miles if the reading is taken at the site boundary.)

L. Hit the F9 key to calculate.

Record or print the results.

Page 9

of 26 Rev. No.

15S

RELEASE RATE DETERMINATION 4.1.4 Release Rate Estimation Using Containment High Range Radiation Monitor Data A. Record date, time and individual performing calculations in upper right-hand corner of.

B. Record containment rad monitor I.D. (i.e.,

either 27-RE-104 A or B) in Column 1 or an average of the two.

C. Record the containment rad monitors average reading (dose rate) or the individual monitor reading (dose rate) in Column 2.

Obtain readings from EPIC.

D. Record the time the containment rad monitor dose rate was observed in Column 3.

E.

Record the time of-shutdown in Column 4.

F. Determine the time in hours after shutdown that the containment radiation monitor reading was taken (Column 4 - Column 3) and record in Column

5.

No.

15 Page 10 of 26 Rev.

EAP-4.1

RELEASE RATE DETERMINATION NOTE:

Ensure that credit is taken for any dilution provided to the value calculated in step 4.1.4.G prior to it entering the effluent pathway to the environment (i.e. dilution by Reactor Building volume, etc.).

G. Determine and record in Column 6 the calculated concentration in containment for the time after shutdown reading using the curves in Attachment 4 and the following core damage estimates:

H. Determine the expected flow rate (cc/sec) to the environment and record in Column 7.

Assistance from TSC engineering staff may be necessary in determining flow rates.

I.

Determine the estimated release rate by multiplying Column 6 by Column 7.

Record in Column 8.

Rev. No.

15 Page 11 of 26 Calculated Concentration* Location on Graph (Ci/cc)

Area above Case #1 5.20E-2 Area between Case #1 and Case #2 3.45E-2 Area between Case #2 and Case #3 1.09E-2 Area between Case #3 and Case #4 3.30E-4 Area between Case #4 and Case #5 1.91E-5 Area between Case #5 and Case #6-1.91E-6 Area below Case #6 Normal

  • Concentrations derived using EAP-44 estimates of core inventory and a containment volume of 7.42E+9cc (i.e. drywell and torus gas space volume).

EAP-4.1

RELEASE RATE DETERMINATION NOTE:

EPIC provides release rates based on default K factors and normal flow rates.

4.1.5 Obtaining Release Rate Using EPIC A. Call up the Radioactivity Release Control (RRC) display on EPIC.

B. Obtain and record release rate data from RRC display for release pathway of concern.

4.2 Default Accident Source Terms 4.2.1 Various types of design basis accidents have been analyzed and source terms estimated.

Refer to 2 for estimated values.

4.2.2 In addition, source term estimates have been developed based on differing amounts of core damage for accidents resulting in leakage of activity through the drywell boundary.

A. Attachments 5 through 10 provide correlation between stack source term estimates for given containment leak rates and containment high range radiation monitor readings.

B. These attachments can be used to project what a release rate may be given a break in containment and containment failure imminent.

C. These source terms are only estimates and should be input with the understanding of the assumptions used-in their development.

D. The source terms correspond to test cases in the Sergeant Lundy study "I4igh Range Containment Monitor Response to Post Accident Fission Product Release" and are plotted on Attachments 5 through 10. These graphs are based on calculation [[::JAF-89-003|JAF-89-003]] filed in the original procedure EAP-4 master file.

Rev. No.

15 Page 12 of 26 EAP-4.1

RELEASE RATE DETERMINATION 4.3 Unmonitored Release All likely release pathways are monitored.

If there is a

release through an unmonitored pathway, the release should be evaluated based on a source term (area monitors, process monitors, and/or local grab samples, as appropriate) or back calculations from downwind readings as described in Section 4.1.3 of this procedure.

5.0 ATTACHMENTS

1.

FLOW CHART TO DETERMINE RELEASE RATE FROM LOW RANGE EFFLUENT MONITORS

2.

FLOW CHART TO DETERMINE RELEASE RATE FROM HIGH RANGE EFFLUENT MONITORS (HREM)

3.

WORK SHEET TO DETERMINE RELEASE RATE FROM CONTAINMENT RAD MONITORS

4.

FITZPATRICK HRCRM READINESS

5.

1.5% LEAKAGE SOURCE TERM ESTIMATE

6.

10% LEAKAGE SOURCE TERM ESTIMATE

7.

25% LEAKAGE SOURCE TERM ESTIMATE

8.

50% LEAKAGE SOURCE TERM ESTIMATE

9.

100% LEAKAGE SOURCE TERM ESTIMATE

10.

CASTASTROPHIC LEAKEAGE SOURCE TERM ESTIMATE

11. CALCULATION METHOD FOR.DETERMINING PERCENT OF TECHNICAL SPECIFICATION FOR NRC EVENT NOTIFICATION WORKSHEET
12.

ANALYZED ACCIDENT TYPES Rev.

No.

15 Page -

13 of 26 EAP-4.1

FLOW CHART TO DETERMINE RELEASE RATE FROM LOW RANGE EFFLUENT MONITORS DATA Rx B (cpm)

Stack (cps)

Rx B EPIC (cpm)

Pt I D

. (cpm) 3337 Refuel EPIC Floor Pt I D (cpm)

(cpm) 3338 Radwaste EPIC (cpm)

Pt I D (CPM) 3340 RF (cpm)

TB (cpm) x (

x x (

x (

x (

x Turbine EPIC Building Pt I D (CPm) x (cpm) 3339 x

Stack EPIC (cps)

Pt I D (cps) x

(

3336 x___

X RW (cpm)

) =

RR (pCI/s)

) = _

) =

RR (pCi/s)

) = RR (pCi/s)

) = RR (pCi/s)

) =

) = RR (pCi/s)

Refer to Section 4.1 1 C~and D for additional guidance Monitor K Factor Normal Flow Rates Based on (cfm)

Reactor Bldg (Pt. 3337) 3.2E-1 ijCi/sec/cpm 61,000 Refuel Floor (Pt 3338) 3.7E-1 pCi/sec/cpm 70,000 Radwaste Bldg (Pt. 3340) 1.7E-1 pCi/sec/cpm 32,500 Turbine Bldg. (Pt. 3339) 5.6E-1 pCi/sec/cpm 107,000 Stack (Pt. 3336) 6.0E-1 pCi/sec/cps 6,600 IF flow rates differ from the Normal Flow Rates listed above, THEN a correction to the K factor is necessary as follows:

"NNew Flow Rate K (corrected)

=

N al Flow Rate X [ K Factor (hsted NOTE: -The accuracy of ventilation flow rate indications at the low end of an instrument range should be confirmed with appropriate instrument calibration procedures.

DATE TIME NAME Actual Iodine Release Rate (RR)

(Actual lI/NG Ratio) x RR(NG) = RR(lodine) Ci/sec x

=

Ci/sec Estimated Iodine Release Rate (RR)

R

) sex RR(NG)

= RR(Iodine)

Ci/sec x

Cilsec Noble Gas Re~easeRa~e-RR(NG)

RR (pCi/sec)

+

1 0E6 = RR(NG)

Ci/sec 1.0E6

=

Cilsec Iodine / Noble Gas Ratio Loss of Coolant Accident Control Rod Drop Refueling Accident Steam Line Break Single Phase Steam Line Break Two Phase Containment Design Basis

' Accident RATIOS **

2.98E-03 9.93E-03 1.24E-04 1.79E+01 1.79E+01 2.13E-02 RELEASE RATE DETERMINATION 15 ATTACHMENT 1 Page 14 of 26 EAP-4.1 Rev.

No.

Page 1 of 1

(

FLOW CHART TO DETERMINE RELEASE RATE FROM HIGH RANGE EFFLUENT MONITORS (HREM)

Page 1 of 1 DATA: Stack (mR/hr)

TB (mR/hr)

RW

. (mR/hr)

Stack (HREM),

1 SBGT Train (mR/hr)

I Stack (HREM) 1 SBGT I Fan (mR/hr)

TB (HREM)

(mR/hr)

Radwaste (HREM)

(mR/hr)

EPIC Pt. I.D.

1191 EPIC Pt. I D.

1191 ERIC Pt.LI D.

1194 EPIC Pt. I.D.

1195 (mR/hr)

(mR/hr)

(1 40)*-. =

RR (Ci/s)

(1.40)

=

(2.54)I (2.54)

=

(22.6)=

"(mR/hr)

H1 (mR/hr)

(22 6) =

r" T

(6.85)

=

(6 85)

=

RR (Gu/s)

DATE:

TIME, NAME:

Noble Gas Release Rate RR (NG)

-o (Ci/sec)

Actual Iodine Release Rate (RR)

(Actual IING Ratio) x RR(NG)

RR(lodine) Cilsec x

Estimated Iodine Release (RR) Rate

  • ( *

) x RR(NG)

=

RR(Iodine) Ci/sec

(

) x=

Based on G. E. Data for monitor response under normal flow rates listed on page 8 Iodine / Noble Gas Ratio Loss of Coolant Accident Control Rod Drop Refueling Accident Steam Line Break Single Phase Steam Line Break Two Phase Containment Design Basis Accident RATIOS **

2.98E-03 9.93E-03 1.24E-04 1.79E+01 1.79E+01 2.13E-02 EAP-4.1 RELEASE RATE DETERMINATION ATTACHMENT 2 Rev.

No.

15 Page 15 of 26 I

j I

WORK SHEET TO DETERMINE RELEASE RATE FROM CONTAINMENT RAD MONITORS DATE:

TIME:

NAME:

Column 1 Column 2 Column 3 Column 41 Column 5 Column 6 Column 7 Column 8 Containment Containment Time of Time of Time of Calculated Expected Flow Estimated Rad Monitor Rad Monitor Reading Shutdown Reading Concentration Rate to Release Rate in containment Environment (Ci/sec)

I.D.

Dose Rate After (Ci/cc)

(cc/sec)

(R/hr)

Shutdown (hr) AT x

x

  • To convert cfm to cdsec, multiply cfin by 472 from CRC handbook of Chemistry and Physics. 64th Edition. n. F-308.

NOTE:

The Primary Containment and Reactor Building leak rate default value is 1.5%

per day (1298 cc/sec). The as-left Primary Containment leak rate calculated after RO-15 was approximately 1,569 scf/day (1 1 CFM or 514.4 cc/sec).

The dose rate at the site boundary is 500 mr/yr whole body from noble gas, 1,500 mr/yr for any organ from iodines and particulates with half lives greater than 8 days, per Offsite Dose C4lculation Manual (ODCM)

The current total as-left Primary Containment leakage can be found in the last run of ST-39B attachment 7. The last run ST-39B is in a binder in the bottom drawer of the middle file cabinet in the Operations file area adjacent to the Control Room. Attachment 7 is used to update the leakage totals subsequent to a complete run of ST-39B (i.e., forced outage LLRTs). The most recently dated forms of attachment 7 will contain the current as-left Minimum Pathway leakage and Maximum Pathway leakage. These numbers will provide the least and most amount of leakage pro;ected for all Primary Containment leakage pathways.

These numbers are reported in Standard Liters per Minute (SLM). To convert to cc/sec, as required in EAP-4. 1, divide SLM by 28.31 to get CFM, them multiply CFM by 472 to get cc/sec.

EAP-4.1 Rev. No.

RELEASE RATE DETERMINATION i5 ATTACHMENT 3 Page 16 of 26 Calculated Concentration* Location on Graph (Ci/cc)

Area above Case #1 5.20E-2 Area between Case #1 and Case #2 3 45E-2 Area between Case #2 and Case'#3 1.09E-2 Area between Case #3 and Case #4 3.30E-4 Area between Case #4 and Case #5 1.91E-5 Area between Case #5 and Case #6 1.91E-6 Area below Case #6 Normal

  • Concentrations derived using EAP-44 estimates of core inventory and a containment volume of 7.48E+9cc (i.e. drywell and torus gas space volume).

Page 1 of 1

~~

I--

.j,

O.

RELEASE RATE DETERMINATION EAP-4.1 Page 1 of 1 FITZPATRICK HRCRM READINGS loo 107

=

C3 a:

C) c-I w

105 104 10, 101 FITZPRTRICK -

HRCRM RERDINGS Page 17 of 26 100" Rev. No.

is

RELEASE RATE DETERMINATION 1.5% LEAKA(

Attachnent 5 GE SOURCE TERM ESTIMATE Page 1 of 1

-1Cl z

I-,

Cl::

0 z

C-'

-

H Page 18 of 26 Lfl 0

(-y

-o N.<

VJ EAP-4. 1 I

C>

.-YlN "AD'iMi III(-) twoa 1 0a1 1110 Rev. No.

is

RELEASE RATE DETERMINATION EAP-4.1 Page I of 1

.0% LEAKAGE SOURCE F:

z LLI (N

c,*j V

Cjl, nW 1111:.iuk Page 19 of 26 Rev. No.

is

(D 80)25%

PRIMARY CONfAINMLNi B6OUNR' LE AKAGL z

ACCIDENT SOURCE

[TERM ESTIMAT[S 700 600 CaS~

Hw 0

2 00 I'dI LLI (D

200 10 o

0

__n_

13 12 18 24 30 ~~

0'0 F4.

RELEASE RATE DETERMINATION 50% LEAKAGE SOURCE TERM ESTIMATE Page 1 of 1 rc-l

"-'53 C

uc~

C Page 21 of 26 Rev. No.

15 EAP-4. 1 00 "PillS, Ill() tu 1.1 1

RELEASE RATE DETERMINATION 100% LEAKAGE SOURCE TERM ESTIMATE Page 1 of 1 00

  • ev.

No.

15

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Page 22 of 26 EAP-4.1

RELEASE RATE DETERMINATION EAP-4.1 0 Page 1 of 1 CATASTROPHIC LEAKAGE SOURCE TERM ESTIMATE C11 Q

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Rev. No..

15

RELEASE RATE DETERMINATION 1 Page 1 of 2 CALCULATION METHOD FOR DETERMINING PERCENT OF TECHNICAL SPECIFICATION FOR NRC EVENT NOTIFICATION WORKSHEET

1.

The formula for calculating the percent of Technical Specification of Airborne releases was derived from the JAF Offsite Dose Calculation Manual, Revision 7.

The following assumptions apply:

The release Technical Specification limit of 500 mrem/year ([CTS] Technical Specifications, Appendix B, Section 3 2.a.1 [ITS] 5.5.4) was used as the basis for the noble gas instantaneous release limit.

The Technical Specification of 1,500 mrem/year to any organ ([CTS] Technical Specifications, Appendix B, Section 3.2.a.2 [ITS]5.5.4) was used as the basis for the radloiodine, tritium and eight day particulate instantaneous release limit The most conservative X/q (4.83E-7 sec/m 3) for ground based receptors at the site boundary was used for all cases and is the FSAR defined accident X/q.

All assumptions and conservatism of the ODCM were applied.

2 As a result of these assumptions and conservatism, these formulae should be used only to estimate the initial percent of Technical Specifications as required by the NRC Event Notification Worksheet (EAP-1.1, ). As more detailed source term and meteorological data become available, a more accurate determination of percent Technical Specification should be performed.

3.

Technical Specification release rates for stack and vent noble gas releases are obtained from the setpoint release rates for these points described in the ODCM.

4.

Calculation method for determining the initial percent of Technical Specifications for NRC Event Worksheet (use calculation worksheet on next page).

For Noble Gas Vent Release:

% T S. = RRNG (Ci/s) x 1432 For Noble Gas Stack Release:

% T S. = RRNG (Ci/s) x 333 Where RRNG = noble gas release rate in curies per second 1432 = 100% divided by vent setpoint release rate of 0 0698 Ci/sec 333 = 100% divided by stack setpoint release rate of 0.3 Ci/sec These equations assume an instantaneous release rate, ODCM dose conversion factors, and historical meteorological data.

For Gross Liquid Release excluding Tritium:

% T.S. = FL (gallm) x CL (gCi/ml) x 2120 Where FL = flow rate in gallons per minute CL = concentration of liquid effluent in gCi/ml 2120 = unit and dose conversion factor For iodine, tritium and particulates with half-lives greater than 8 days:

"% T.S iodine and particulate = RRiodine (Ci/sec) x 40.48

"% T S.tritium = RRtritium (Ci/sec) x 0.32 Total % T.S. = Z % T.S for all release points Page 24 of 26 EAP-4. 1 Rev.

No.

15

ATTACHMENT 11 CALCULATION METHOD FOR DETERMINING PERCENT OF TECHNICAL SPECIFICATION FOR NRC EVENT NOTIFICATION WORKSHEET Page 2 of 2 Noble Gas Vent Reiease

% T.S. = RRNG x 1432

% T.S.

=

[RRNC

]

% T.S.

=

Ci/s x 1432 Noble Gas Stack Release

% T.S.

=

RRNG (Ci/s) x 333

% T.S.

=

[RRNG _

Cl/s x 333

% T.S. =

Gross Liquid Release excluding Tritium

% T.S.

= FL x CL (.ICl/ml) x 2120

% T.S.'

[FL

] gal/m x

[CL

% T.S.

=

NOTE:

100% NG Vent Release= 0.0698 ci/sec 100% NG Stack Release = 0.3 cl/sec NOTE:

If

% TS Ž 100 - Fill out Part II Form This is indication of a release in progress pCi/ml x [2120]

Iodine and Particulate with half lives greater than 8 days'

% T.S.

&p = Z RR(Ci/s)i&p (all vents) x 40.48

% T.S.

&p =

[(RR&p

) Ci/s + (RRip

) Cl/s +

stack T.B. vent RR Ci/s + (RR,,p _

), Cl/s +

Rx Bldg vent Refuel Floor (RRQp

) Ci/s]'x 40.48 Radwaste Bldg Tritiu

% T.S.

+/-&p =

(RR 5 p

)

Cl/s x

40.48 total vents

% T.S.

iap =

im

% T.S.

Tritium = Z RR(Cl/S)Tritium (all vents) x 0.32

% T.S. Tritium =

[(RRTritium

) Ci/s +

(RRTritium

) Ci/s +

stack T.B. vent (RRTritium

) Ci/s

+

(RRTritium

)

Ci/s

+

Rx Bldg vent Refuel Floor (RRTritium

) Ci/s] x 0.32 Radwaste Bldg

% T.S.

Tritium =

(RRTritium

) Ci/s x 0.32 total vents

% T.S.

Tritium

=

Where:

RR= release rate (Ci/sec)

FL = Flow Rate (gal/rm)

CL = Concentration o f liquid effluent ( pCi/ml),

EAP-4.1 RELEASE RATE DETERMINATION ATTACHMENT 11 Rev.

No.

15 Page 25 of 26

RELEASE RATE DETERMINATION EAP-4.1 ATTACHMENT 12 Page 1 of 1 ANALYZED ACCIDENT TYPES New Accident Names/Analyzed Accidents Loss of Coolant Control Rod Drop Refueling Steam Line Break Steam Line Break lOC* e......, 5g..,

per Attachment A of EAP-4 Accident Accident Two Phase F,.

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loca jaf crd jaf rfa jaf slb2 jaf slb2 jaf esf jaf Loss of Coolant Steam Line Break Containment Design OLD EDAMS Accident Name Used Control Rod Drop Refueling Accident Two Phase Basis Accident Analyzed Release Point Elevated Ground Elevated Ground Ground Elevated Nuchidel LOCA I

CRD

[

RFA SLB1I SLB2 CDA Kr83M 1.353E+00 1 577E-03 6 117E-03 1 517E-05 1 517E-05 1 154E-02" Kr 85M 2 906E+00 3 386E-03 8 839E-02 2 725E-05 2 725E-05 1 508E-04 Kr85 1 301E-01 1.156E-04 1 604E-01 8 917E-08 8 917E-08 3 658E-09 Kr 87 5 572E+00 6 494E-03 1.432E-05 8 917E-05 8 917E-05 0 000E+00 Kr 88 7 894E+00 9 200E-03 2.777E-02 8 917E-05 8 917E-05 0 000E+00 Kr 89 9 817E+00 1 144E-02 0 OOOE+00 5 800E-04 5 800E-04 0 OOOE+00 Kr subtotal 2 767E+01 3 221E-02 2 827E-01 8 008E-04 8 008E-04 1.508E-04 Xel3lm 6 825E-02 7.953E-05 8 783E-02 6 692E-08 6.692E-08 7.994E-05" Xe133m 9.942E-01 1.159E-03 1 048E+00 1 292E-06 1 292E-06 1 934E-03 0 z Xe133 2 386E+01 2 781E-02 2 833E+01 3 658E-05 3 658E-05 2 769E-02 Xe135 3 081E+00 3 589E-03 6 522E+00 9 833E-05 9 833E-05 1 952E-01 Xe135m 4 494E+00 5 239E-03 3 578E-01 1 158E-04 1 158E-04 5 686E-01 Xe137 2 094E+01 2 440E-02 0 OOOE+00 6 692E-04 6 692E-04 0 OOOE+00 Xe138 1 988E+01 2 316E-02 0 000E+00 3 975E-04 3 975E-04 0 000E+00 Xe subtotal 7 332E+01 8 544E-02 3 635E+01 1 319E-03 1 3192-03 7 934E-01 Gas (NG) subtotal 1.010E+02 1.176E-01 3.663E+01 2.120E-03 2.120E-03 7.936E-01 1131 3 406E-02 1 323E-04 1 299E-03 9 808E-04 9 808E-04 1 918E-03 1132 4 975E-02 1 933E-04 1 680E-03 7 628E-03 7 628E-03 2 803E-03 S1133 7 119E-02 2 766E-04 1 346E-03 6 536E-03 6 536E-03 4 011E-03 ao 1134 7 839E-02 3 044E-04 0 000E+00 1 380E-02 1 380E-02 4 417E-03 1 1135 6 725E-02 2 612E-04 2 233E-04 9 075E-03 9 075E-03 3 789E-03 Iodine subtotal 3.006E-01 1.168E-03 4.548E-03 3.802E-02 3.802E-02 1.694E-02 CS137 3 583E-03 1 671E-05 1 769E-04 1 198E-05 1 198E-05 2 019E-04 TE132 8 178E-03 0 000E+00 0 000E+00 6 900E-04 6 900E-04 4 606E-04

-a SR 89 2.132E-03 0 000E+00 0 000E+00 1 489E-04 1 489E-04 1 201E-04 SR 90 2.228E-04 0 000E+00 0 000E+00 1.126E-05 1.126E-05 1 255E-05 F

Ba140 4.094E-03 0 000E+00 0 000E+00 4.358E-04 4.358E-04 2 306E-04 La140 4.336E-05 0 000E+00 0 000E+00 0 000E+00 0 000E+00 2.443E-06 I Particulate subtotal 1.83E-02 1.67E-05 1.77E-04 1.30E-03 1.30E-03 I

03E-03 RELEASE RATE TOTALS (Cilsec) 1.01E+021 1.19E-01 3.66E+01 4.14E-02 4.14E-021 8.12E-01 Accident Duration Used for EDAMS 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />sl 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 2 hours 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hoursi 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> TOTAL Release Assumed (CQ) 2.92E+061 1.71 E+03 2 64E+05 2 982+02 2.98E+021 5.84E+03 RATIOS Iodine / Noble Gas Ratio Noble gas / Iodine Ratio Noble Gas / Particulate Ratio Iodine / Particulate Ratio NG / Particulate + Iodine Ratio Loss of Coolant Accident Control Rod Drop 2 98E-03 Refueling Accident Steam Line Break Two Phase Steam Line Break T

I 5

1 1.

9 93E-03 1 24E-04 1 79E+01 1.79E+01 LOCA - Engineered Safety Feature Component Leakage 2.13E-02 3 36E+02 1 01E+02 8 05E+03 5 58E-02 5.58E-02 4 69E+01 5 53E+03 7 04E+03 2 07E+05 1 63E+00 1.63E+00 7 72E+02 1 65E+01 6 99E+01 2 57E+01 2 93E+01 2 93E+01 1 65E+01 3 17E+02 9 93E+01 7 75E+03 5 39E-02 5 39E-02 4 42E+01 Rev. No.

15 u) 0 Page 26 of 26

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