ML030340043
| ML030340043 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| 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) | |
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: U.S.N.R.C. Document Center/Washington, DC FROM: 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.
V(31 IiMFI= llnr1~t*_I itifl tAtd JANUARY 24. 2003 V0 V IVIF1H I iisrlt 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
_______ I ________________ I I 1 1
ýOtf 5
EMERGENCY PLAN IMPLEMENTING PROCEDURES/VOLUME 2 UPDATE LIST ICONTROLLED 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 IAP-2 CLASSIFICATION OF EMERGENCY 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 r .Y.
Date of Procedure Procedure Revision Use of Last Number Title , Number Procedure Review 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 VEHICLE AND PERSONEL - V 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: N/A I-,
APPROVED BY: DATE: i-RESPONSIBLE PROCEDURE OWNER EFFECTIVE DATE: 94wim W ;Z 63 FIRST ISSUE El FULL REVISION 01 LIMITED REVISION El
-k 41 -)14- -k -k + -k * * * * * * * * * * * * * * * * * * * * *
- INFORMATIONAL USE *
- TSR *
- ADMINISTRATIVE
- CONTROLLED #:
PERIODIC REVIEW DATE: JUNE 2007
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 EAP-4. 1 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.
Rev. No. 15 Page 4 of 26
RELEASE RATE DETERMINATION EAP-4.1 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, Attachment 6.
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
RELEASE RATE DETERMINATION EAP-4. 1 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 Rev. No. 15 Page 6 of 26
RELEASE RATE DETERMINATION EAP-4.1 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 Attachment 2 .
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.
Rev. No. 15 Page 7 of 26
RELEASE RATE DETERMINATION "EAP-4. 1 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:
K(corrected) = New Flow Rate1 x [ Factor(listed]
[Normal Flow Rate I
- 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.
Rev. No. 15 Page 8 of 26
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.
Rev. No. 15S Page 9 of 26
RELEASE RATE DETERMINATION EAP-4.1 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 Attachment 3.
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.
Rev. No. 15 Page 10 of 26
RELEASE RATE DETERMINATION EAP-4.1 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:
Calculated Concentration*
Attachment 4 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).
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
RELEASE RATE DETERMINATION EAP-4.1 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 Attachment 12 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
RELEASE RATE DETERMINATION EAP-4.1 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
FLOW CHART TO DETERMINE RELEASE RATE FROM LOW RANGE EFFLUENT MONITORS Page 1 of 1 DATA Rx B _ (cpm) RF (cpm) RW _ (cpm) DATE TIME Stack (cps) TB (cpm) NAME Rx B EPIC )
x ( * = RR (pCI/s)
(cpm) Pt I D 3337
- . (cpm) x ) = _ _ _ _ Actual Iodine Release Rate (RR)
(Actual lI/NG Ratio) x RR(NG) = RR(lodine) Ci/sec Refuel EPIC x = Ci/sec Pt I D (cpm) x ( * ) = RR (pCi/s)
Floor x (
(cpm) 3338 Estimated Iodine Release Rate (RR)
Radwaste EPIC _
) R )sex RR(NG) = RR(Iodine) Ci/sec xx (
(cpm) Pt I D - (CPM) * = RR (pCi/s) x Cilsec 3340 Noble Gas Re~easeRa~e-RR(NG)
Turbine EPIC Building Pt I D (CPm) x * ) = RR (pCi/s)
) = _ _ _ _ RR (pCi/sec) + 1 0E6 = RR(NG) Ci/sec (cpm) 3339 x
_________ 1.0E6 = Cilsec Stack EPIC (cps) Pt I D (cps) x ( * ) = RR (pCi/s) 3336 X x___
Iodine / Noble Gas Ratio RATIOS **
Refer to Section 4.1 1 C~and D for additional guidance Loss of Coolant Accident 2.98E-03 Monitor K Factor Normal Flow Rates Based on (cfm)
Control Rod Drop 9.93E-03 Reactor Bldg (Pt. 3337) 3.2E-1 ijCi/sec/cpm 61,000 Refuel Floor (Pt 3338) 3.7E-1 pCi/sec/cpm 70,000 Refueling Accident 1.24E-04 Radwaste Bldg (Pt. 3340) 1.7E-1 pCi/sec/cpm 32,500 Steam Line Break Single Turbine Bldg. (Pt. 3339) 5.6E-1 pCi/sec/cpm 107,000 Phase 1.79E+01 Stack (Pt. 3336) 6.0E-1 pCi/sec/cps 6,600 Steam Line Break Two IF flow rates differ from the Normal Flow Rates listed above, THEN a correction to the K factor is necessary as follows: Phase 1.79E+01 K (corrected) =
"NNew Flow Rate N al Flow Rate X [ K Factor (hsted Containment Design Basis
' Accident 2.13E-02 NOTE: -The accuracy of ventilation flow rate indications at the low end of an instrument range should be confirmed with appropriate instrument calibration procedures.
EAP-4 .1 RELEASE RATE DETERMINATION ATTACHMENT 1 Rev. No. 15 Page 14 of 26
(
FLOW CHART TO DETERMINE RELEASE RATE FROM HIGH RANGE EFFLUENT MONITORS (HREM) Page 1 of 1 DATA: Stack (mR/hr)
DATE:
TB (mR/hr) RW . (mR/hr) TIME, NAME:
Stack (HREM), EPIC (mR/hr) (1 40)*-. = RR (Ci/s) 1 SBGT Train Pt. I.D. Noble Gas Release Rate RR (NG)
(mR/hr) I 1191 (1.40) = -o (Ci/sec)
- I ; ,'
Stack (HREM) EPIC (mR/hr) (2.54)I 1 SBGT Pt. I D.
I Fan 1191 (2.54) = Actual Iodine Release Rate (RR) .
(mR/hr)
- j &
(Actual IING Ratio) x RR(NG) RR(lodine) Cilsec I _ x TB ERIC "(mR/hr)
Estimated Iodine Release (RR) Rate (mR/hr) 1194 (22 6) = _ _ _ _ _
( ) x=
Radwaste EPIC (6.85) = RR (Gu/s)
(HREM) Pt. I.D.
(mR/hr) 1195 H1 (mR/hr)
(6 85) =
"* Iodine / Noble Gas Ratio RATIOS **
Based on G. E. Data for monitor response Loss of Coolant Accident 2.98E-03 under normal flow rates listed on page 8 Control Rod Drop 9.93E-03 Refueling Accident 1.24E-04 Steam Line Break Single Phase 1.79E+01 Steam Line Break Two Phase 1.79E+01 Containment Design Basis Accident 2.13E-02 EAP-4.1 RELEASE RATE DETERMINATION ATTACHMENT 2 Rev. No. 15 Page 15 of 26
WORK SHEET TO DETERMINE RELEASE RATE FROM CONTAINMENT RAD MONITORS Page 1 of 1 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 I.D. in containment Environment (Ci/sec)
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.
~~ -, . . . . . . .jI--, O. . .
Calculated NOTE:
Concentration* The Primary Containment and Reactor Building leak rate default value is 1.5%
Attachment 4 Location on Graph (Ci/cc) per day (1298 cc/sec). The as-left Primary Containment leak rate calculated after Area above Case #1 5.20E-2 RO-15 was approximately 1,569 scf/day (1 1 CFM or 514.4 cc/sec).
Area between Case #1 and Case #2 3 45E-2 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 Area between Case #2 and Case'#3 1.09E-2 days, per Offsite Dose C4lculation Manual (ODCM)
Area between Case #3 and Case #4 3.30E-4 The current total as-left Primary Containment leakage can be found in the last Area between Case #4 and Case #5 1.91E-5 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 Area between Case #5 and Case #6 1.91E-6 Control Room. Attachment 7 is used to update the leakage totals subsequent to a Area below Case #6 Normal 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.
- Concentrations derived using EAP-44 estimates of core These numbers are reported in Standard Liters per Minute (SLM). To convert to inventory and a containment volume of 7.48E+9cc (i.e. drywell cc/sec, as required in EAP-4. 1, divide SLM by 28.31 to get CFM, them multiply and torus gas space volume). CFM by 472 to get cc/sec.
EAP-4 .1 RELEASE RATE DETERMINATION ATTACHMENT 3 Rev. No. i5 Page 16 of 26
RELEASE RATE DETERMINATION EAP-4.1 Attachment 4 Page 1 of 1 FITZPATRICK HRCRM READINGS loo 107 105
=
C3 a:
104 C) c-I w
10, 101 100"
- FITZPRTRICK - HRCRM RERDINGS Rev. No. is Page 17 of 26
RELEASE RATE DETERMINATION EAP-4. 1 Attachnent 5 Page 1 of 1 1.5% LEAKA(GE SOURCE TERM ESTIMATE
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.-YlN "AD'iMiIII(-) twoa 1 0a1 1110 Rev. No. is Page 18 of 26
RELEASE RATE DETERMINATION EAP-4.1 Attachment 6 Page I of 1
.0% LEAKAGE SOURCE F:
z LLI (N
- c,*j V
Cjl, nW 1111:.iuk Rev. No. is Page 19 of 26
(D 80)25% PRIMARY CONfAINMLNi B6OUNR' LE AKAGL z ACCIDENT SOURCE [TERM ESTIMAT[S 700 600 CaS~ Hw 0
200 I'dI LLI (D 200 10 o 0 _ _ _ ,_ __n_
13 12 18 24 30 ~~
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RELEASE RATE DETERMINATION EAP-4. 1 Attachment 8 Page 1 of 1 50% LEAKAGE SOURCE TERM ESTIMATE rc-l
"-'53 C
uc~
C 00 "PillS,Ill() tu 1.11 Rev. No. 15 Page 21 of 26
RELEASE RATE DETERMINATION EAP- 4.1 Attachment 9 Page 1 of 1 100% LEAKAGE SOURCE TERM ESTIMATE
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1,)JVI I:I*In[,I+u R*ev. No. 15 Page 22 of 26
RELEASE RATE DETERMINATION EAP-4.1 Attachment 10 Page 1 of 1 CATASTROPHIC LEAKAGE SOURCE TERM ESTIMATE c-il LU LU1
- z LU Q
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c--A iflO' Rev. No.. 15 Page 23 of 26
RELEASE RATE DETERMINATION EAP-4. 1 Attachment 11 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, Attachment 6). 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 Rev. No. 15 Page 24 of 26
ATTACHMENT 11 Page 2 of 2 CALCULATION METHOD FOR DETERMINING PERCENT OF TECHNICAL SPECIFICATION FOR NRC EVENT NOTIFICATION WORKSHEET Noble Gas Vent Reiease NOTE:
% T.S. = RRNG x 1432 100% NG Vent Release= 0.0698 ci/sec
% T.S. = [RRNC ] Ci/s x 1432 100% NG Stack Release = 0.3 cl/sec
% T.S. =
Noble Gas Stack Release NOTE:
If % TS Ž 100 - Fill out Part II Form
% T.S. = RRNG (Ci/s) x 333
% T.S. = [RRNG _ Cl/s x 333 This is indication of a release in progress
% T.S. =
Gross Liquid Release excluding Tritium
% T.S. = FL x CL (.ICl/ml) x 2120
% T.S.' [FL ] gal/m x [CL _____ pCi/ml x [2120]
% T.S. =
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
% T.S. +/-&p = (RR 5 p ) Cl/s x 40.48 total vents
% T.S. iap =
Tritiuim
% 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,. c ,l.*,
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 11135 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 Particulatesubtotal 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />si 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 Loss of Coolant Refueling LOCA - Engineered Steam Line Break Steam Line Break Safety Feature Accident Control Rod Drop Accident Two Phase Component Leakage u) RATIOS 0 T I 5 1 1.
Iodine / Noble Gas Ratio 2 98E-03 9 93E-03 1 24E-04 1 79E+01 1.79E+01 2.13E-02 Noble gas / Iodine Ratio 3 36E+02 1 01E+02 8 05E+03 5 58E-02 5.58E-02 4 69E+01 Noble Gas / Particulate Ratio 5 53E+03 7 04E+03 2 07E+05 1 63E+00 1.63E+00 7 72E+02 Iodine / Particulate Ratio 1 65E+01 6 99E+01 2 57E+01 2 93E+01 2 93E+01 1 65E+01 NG / Particulate + Iodine Ratio 3 17E+02 9 93E+01 7 75E+03 5 39E-02 5 39E-02 4 42E+01 Rev. No. 15 Page 26 of 26