Text

License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 3 of 5
	ML17095A115
Person / Time
Site:	Monticello
Issue date:	03/31/2017
From:	; Northern States Power Company, Minnesota, Xcel Energy
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML17095A107	List: L-MT-17-012, License Amendment Request to Revise Emergency Action Level Scheme: Emergency Action Level Matrix, Hot Conditions (Attachment 5); ML17095A112; ML17095A113; ML17095A114; ML17095A115; ML17095A118; ML17095A120; ML17095A121;
References
	L-MT-17-012 CA-04-194
	Download: ML17095A115 (36)
	v • d • e

CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Including Minor Revision, with Attachment C as annotated (36 total pages) Calculation 04-194 Minor Revion la justification The "CHRRM Response To Drywell Airborne Radioactivity" plot on page 22 of24 of calc 2004-07060 R2 (MNGP calc 04-194 Rev.l) used a "Time after Release" ordinate axis label when it should have been "Time after Shutdown".

The two points in time during the post-accident progression are not coincident:

Isotopic decay rates are based on the moment of reactor shutdown for an inception point. The vendor was contacted confirming the data was used in this regard and further detfills can be found in C.Af:l Number: 013 70699. The same plot also appears on page 46 of this calc and has been updated accordingly.

There is no impact to the calc conclusion.

CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airbornef>tltivft,,'-\

Rlo-. o. . '? lS z_,,LtO .. -". Client NSP Project Monticello NGP Proj. No 12400-045 .c: 1.0E+06 1.0E+05 1.0E+04 3l *1.0E+03 c 0 a. UI 2; 1.0E+02 0:: 0:: 5 1.0E+01 1.0E+OO 1.0E-01 1.0E-02 File GQ308-2.DOC Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060 (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 22 of 24 Prepared by Date Reviewed by Date Equip. No. Approved by Date CHRRM Response To Drywell Airborne Radioactivity

,,----Gap Activity; 100% Gap Activity, 20% , ,, , Gap Activity; 10% / / / -Gap Activity; 05% --,.V // '/,, -Gap Activity; 300 µCi/gm DEl-131 RW; 2.0 µCi/gm DEl-131, 300,000 µCi/sec ' ,.. , , RW; 0.2 µCi/gm DEl-131, 100,000 µCi/sec / // RW; 4.11E-5 µCi/gm DEl-131, 2967 µCi/sec / ,/' I/// v ---/ f --/ --K 1.0E-01 --"'-f f v .... -/ -v / / v"' ---,,,, --/ / / // / *A f / / --// ....... :-... ,..__ ....... .........

1.0E+OO 1.0E+01 Time After-Release (hrs) Shutdown -....... ---,..__ ,...__ -.........

-.........

Form GQ-3.08.1 Rev.2 --....... ......... -r----....._

............. ....... ...... .........

r--. ----............._

I' ..... j'\ -.........

!'-.. .................

.... ..............

...............

1.0E+02 1.0E+03 1a CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne

-ll\ '1 1 ptVj.e---lib 0 f 'C .c oc 1.0E+06 1.0E+05 1.0E+04 °;' 1.0E+03 If) s::: 0 c.. If) 1.0E+02 a:: :i:: 0 1.0E+01 1.0E+OO 1.0E-01 1.0E-02 CHRRM Response To Drywell Airborne Radioactivity Cale.: 2004-07060 Rev.: 2 Attachment C Page C1 of C7 --------/ / / ..........

/ 1.0E-01 Gap Activity; 100% Gap Activity, 20% Gap Activity; 10% / / / Gap Activity; 05% / / / -r--// // '// -Gap Activity; 300 µCi/gm DEl-131 --RW; 2.0 µCi/gm DEl-131, 300,000 µCi/sec , __ RW; 0.2 µCi/gm DEl-131, 100,000 µCi/sec , , RW; 4.11 E-5 µCi/gm DEl-131, 2967 µCi/sec ,r // --...._ / I/ / / / -,.(__,; -... / /// / ---..:: y r--------...... v / ;-..__ .... -....... ----.v v )// ------r---_ "" ;--..........

.... ,_ , --I/ -......._ '-/ / I/ -----.... -....... " // r/ r-........ I""-"-.. !'I..\ -........ --, " , / -....._ ' // ........ '-// r-... r-......, i"----,....._ ........ ' r..... l'-o.i-. ""-, -,....._ ....... " "" .... -.........._...

1.0E+OO 1.0E+01 1.0E+02 1.0E+03 Time After-Release (hrs) Shutdown CA-04.:194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne ACtivity" 10/21/13

Condition Evaluation CAP Number: 01370699 Condition Evalu.ation Number: 01370699-01 Description of problem: Procedure A.2-208 (Core Damage Assessment) includes Figure 7.1, "Containment Radiation Monitor Response Curves", which is used to assess the extent of core damage based on _ radiation levels in containment.

Labeling on the chart is misleading and appears to have led to incorrect procedure guidance for using the chart. Evaluation Details: Given the situation in which the RCS (Reactor Coolant System) barrier has been lost, containment radiation levels (due to airborne radioactivity) can be used to determine the extent of core damage. To generate the Gurves, radiation levels were calculated for various source terms, ranging from reactor water with normal dose equivalent iodine (DEi) concentrations to 100% of gap activity.

The calculation, which was performed by Sargent & Lundy, states that, "[t]he scope of this calculation is to determine the response of the CHRRM [Containment High Range Radiation Monitor] ... for a period of 30 days after shutdown." The chart which shows the curves is a source of confusion, however. The time scale, which ranges from*o.01 to 720 hrs (30 days), is laQeled, "Time After Release (hrs)." Previous similar charts used "time after shutdown" as the time-based entry point. Given that the curves reflect source term decay, and that the decay process starts at shutdown, it's obvious that "time after shutdown" is the proper value to use for entering the chart. A release from the coolant system can occur well after shutdown, or even before shutdown, so that unless shutdown and the start of a release coincide, the decay factors would be inaccurate.

A discussion with the S&L employee who approved the calculation confirmed that the chart should be entered with the time after shutdown.

Actions:

To address the condition, procedure A.2-208 needs to be revised. Step 6.2.2 should be revised to use "time after shutdown".

Any reference to "containment breach" should be deleted. In addition, the title on the time scale of Figure 7.1 should be changed to, 'Time After Shutdown".

[CA 01370699-03]

Preparer's Name: G. Mathiasen Date: 3/12/13 Page 1 of 1 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" QF--0549 01=--0547 QF-0528 TOG Calculation Description 04-194Rev1 TABLE OF CONTENTS Page 1 of 1 Calculation Signature Sheet External Design Document Suitability Review Checklist Design Review Comment Form Table of Contents

Sargent & Lundy Calculation 2004-07060 Rev 2 Total Pages 5 3 2 1 229 240 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" ISSUE

SUMMARY

Form SOP-0402-07, Revision B DESIGN CONTROL

SUMMARY

CLIENT: NSP UNIT NO.: 1 PAGE NO.: 1 PROJECT NAME: Montlcello Nuclear Generating Plant PROJECT NO.: 11972-019 I S&L NUCLEAR QA PROGRAM I CALC.NO .. : 2004-07060 APPLICABLE

£8l YES 0 NO TITLE: Containment High Range Radiation MoniloP (CHARM} Response to Deywell Airbome Activity EQUIPMENT ND.: RM7860A/B IDENTIRGATlON OF PAGES ADDED/REVISED/SUPERSEDEDNOIDED

& REVIEWMETIIOD See Rev. 0 summary sheet fol'Signatures.

INPUTS/ ASSUMPTIONS

£8l VERIFIED 0 REVIEW METHOD: Detailed Review REV.: 0 STATUS: £81 APPROVED 0 SUPERSEDED BY CALCULATION NO. OVOID DATE FOR REV.: 10/20/2004 PREPARER:

John Rich (Signature on Fiie) DATE: 10115/2004 REVIEWER:

B. J. Andrews (Signature on File) DATE: 10/20/2004 APPROVER:

W. J. Johnson (Signature on Rle) DATE: 10120/2004 IDENTIFICATION OF PAGES ADDEDIREVISED/SUPERSEDEDNQIDEO

& REVIEW METHOD The following pages have been revised: 1, 2, 3, 4, 5, 11, 12,13, 14, 16, 17, 18, 19, 20, 21, 22, and Attachments A through F INPUTS/ ASSUMPTIONS See Rev. 1 summary sheet.for signatures.

£81 VERIFIED 0 UNVERIFIED REVIEW METHOD: Detailed REV.: 1 STATUS: £81 APPROVED 0 SUPERSEDED BY CALCULATION NO. OVOID DATE FOR REV.: 9/2612007 PREPARER:

J.M. Rich (Signature on File) DATE: 9126/2007 REVIEWER:

B. J. Andl'ews (Signature on File) DATE: 9/2612007 APPROVER:

W.J. Johnson (Signature on File) DATE: 9/2612007 lDENTIFlCATION OF PAGES ADOED/REVISED/SUPERSEDEDNOIDEO

& REVIEW METHOD This is a complete revision ol lhe calcula!lon.

Pages 1 through 24 and Attachments A (1 page), B (9 pages), C (7 pages), 0.(47 pages), E (47 pages), F (47 pages). INPUTS/ ASSUMPTIONS and G (47 pages). £8l VERIFIED 0 UNVERIFIED

-REVIEW METHOD: Detailed REV.: 2 STATUS: 181 APPROVED 0 SUPERSEDED BY CALCULATION NO. OVOID DATEFORREV.:

t;.-112--J})

PREPARER:

Anthony G. Klazura fA, k'Rc.A.,fM DATE: t!:t!Jo//

REVIEWER:

J.M. Rich l,.--1uU.

U.!v " {/ DATE: , "i 1/ APPROVER:

w. J. Johnson i1 ;:,, / /1,,{£4..

_ *' DATE: t:; fn /; i " 1 I NOTE: PRINT AND SIGN IN THE SIGNATURE AREAS SOP040207.DOC Page 1of24 Rev. Date: 01-29-2010 CA-04 " -194, "Containment High RanQe Radiation Monitor (CHRRM) Response to Drywell Airborne Activit" Calo*. Fo" Containment High Range Radiation Monitor Calo No. 2004-07060 u .. m*y"* (CHRRM) Response To Drywell Airborne Activity Rev.. 2 \Date X \ Safety Related \ \ Non-Safety Related Page 2 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date TABLE OF CONTENTS 1 PURPOSE AND SCOPE .................................................................................................................

3 2 METHODOLOGY AND ACCEPTANCE CRITERIA ........................................................................

3 2.1 Identification of Computer Codes ...................................................................................................

3 2.2 Method of Analysis .........................................................................................................................

4 2.3 Acceptance Criteria ........................................................................................................................

4 3 DESIGN INPUT ................................................................................................................................

4 4 ASSUMPTIONS

...............................................................................................................................

6 4.1 Drywell Geometry ...........................................................................................................................

6 4.2 Noble Gas In Reactor Water ..........................................................................................................

6 4.3 Normal Noble Gas Release Rate For Reactor Water ....................................................................

6 4.4 Dose Equivalent 1131 For Reactor Water .......................................................................................

6 4.5 Plateout.

..........................................................................................................................................

6 5 CALCULATIONS

.............................................................................................................................

7 5.1 Geometric Input ..............................................................................................................................

7 5.2 Radionuclide Source Input ...........................................................................................................

10 5.2.1 Drywell Fraction, "IDEPL T" ......................................................................................................

10 5.2.2 Reactor Water Noble Gas .......................................................................................................

10 5.2.3 Reactor Water Iodine ...............................................................................................................

12 5.2.4 Gap Activity .............................................................................................................................

13 5.2.5 Gap Activity DEl131 ................................................................................................................

14 5.3 Dose Rates in R/hr .......................................................................................................................

15 5.4 EAL Dose Rates ...........................................................................................................................

20 6

SUMMARY

AND CONCLUSIONS

.................................................................................................

23 7 REFERENCES

...................................................................................................

...........................

23 ATTACHMENTS Attachment A, Summary of Computer Input and Output Files .......................................................

A 1-A 1 Attachment B, Design Information Transmittal (DIT) No. 933 (Reference 7.2) .............................

81-89 Attachment C, Tabular Data and Plot for CHRRM Dose Rate vs Time .........................................

C1-C7 Attachment D, Computer Output, Case 1 .....................................................................................

D1-D47 Attachment E, Computer Output, Case 2 .....................................................................................

E1-E47 Attachment F, Computer Output, Case 3 ......................................................................................

F1-F47 Attachment G, Computer Output, Case 4 ...................................................................................

G1-G47 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv'

§. Caloo. Fo" Containment High Range Radiation Monitor Calo No. 2004-07060

_,.e u..n*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 !Date X I Safety Related I I Non-Safety Related Page 3 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date 1 PURPOSE AND SCOPE The purpose of this calculation is to generate Containment High Range Radiation Monitor (CHRRM) response curves (R/hr vs. time) for both reactor coolant leaks and leaks associated with a fuel cladding breach. Drywell airborne radioactivity sources will be combined to generate these curves. The four drywell airborne radioactivity sources are: (a) reactor water noble gas (b) reactor water iodine (c) fuel gap noble gas (d) fuel gap iodine The scope of this calculation is to determine the response of the CHRRM to the four releases listed above, for a period of 30 days after shutdown.

There are two CHRRMs. A single calculation is applicable to both monitors because of the similarity in their configurations.

The CHRRM is credited for responding to the loss of a fission product barrier. These sources correspond to two cases of the loss of a fission product barrier. If the loss is only a breach of the reactor coolant system, the airborne activity will be due only to the activity in the reactor coolant. If there is a fuel cladding failure, the airborne activity will be due to the activity in the fuel rod gap. Revision 1 The purposes of Revision 1 were to (1) update the core source term and (2) update the iodine dose conversion factors. The core source term was changed from the one generated in MNGP calculation 03-194 (used in Rev. 0), to the Alternative Source Term (AST) inventory generated in Sargent & Lundy (S&L) calculation 2004-07600

[Ref. 7.12]. The iodine dose conversion factors were changed from TID-14844 values (used in Rev. 0) to FGR-11 values [Ref. 7.14] to be consistent with the "Dose equivalent 1-131" definition in Technical Specification 1.1 [Ref. 7.13]. . Revision 2 Revision 2 is a complete revision of this calculation.

The purpose of Revision 2 is to generate CHRRM response curves for radiation sources associated with an Extended Power Uprate (EPU) to a reactor power level of 2004 MWt. EPU core radionuclide inventories are provided in GE Task Report T0802 [Ref. 7.15]. 2 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 Identification of Computer Codes The time-dependent dose rates are calculated with the computer code RUNT-PC [Ref. 7.1]. RUNT-PC has been qualified under S&L's QA program and therefore verification and validation of this code is not required as part of this calculation.

RUNT-PC is a combination of two programs, RACER and ISOSHLD. RACER calculates time-dependent radionuclide activities.

ISOSHLD performs gamma and beta shielding calculations for a variety of shield geometries.

Gamma attenuation calculations are performed using Gaussian quadrature integration of point and line kernel dose rate equations.

Energy dependent linear attenuation coefficients and buildup factors, for each integration, are derived from input parameters and internal databases.

Integrated doses can be calculated for time-dependent sources. RUNT-PC (and its main-frame predecessor, RUNT) have been used to perform the gamma analyses for File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv For. Containment High Range Radiation Monitoc c.io No. 2004-07060 ree Lun*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 ioate X I Safety Related I I Non-Safety Related Page 4 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date designing Byron/Braidwood and LaSalle. Analyses and results using RUNT have been submitted to the NRC for Byron/Braidwood, LaSalle, Dresden and Clinton, and are specifically cited in their USARs. 2.2 Method of Analysis The source term at t=O (the instant the release takes place) is determined for each release (reactor coolant release and gap release).

The t=O source terms are then decayed to obtain the time dependence and used to calculate the dose rate at the CHRRMs locations.

The drywell airborne source volume is modeled as a cylinder with a central core (annular source). The computer program RUNT-PC performs both the decay and dose rate calculations.

2.3 Acceptance

Criteria There are no acceptance criteria for this calculation.

This calculation provides the time dependence of the CHRRM response to a release of airborne radioactivity in the containment.

The results of this calculation will be used elsewhere to support Emergency Action Level (EAL) related procedures.

3 DESIGN INPUT Design Input is presented in Table 3.1-1 below. Reactor core EPU noble gas and radioiodine fission product inventories (curies/MWt) are presented in Table 3.1-2 and are from Appendix A of GE Task Report T0802 [Ref. 7.15]. Radionuclide inventories presented in Table 3.1-2 are reactor shutdown (i.e., no decay) values and represent reactor core average End of Cycle (EOC) values for a burnup of 35 GWD/MTU. Radionuclide inventories presented in Table 3.1-2 are for the krypton, xenon, and iodine isotopes that are identified in Table 2 of DIT 933 [Ref. 7.2]. Table 3.1-1: Design Input Description Value Reference Core Power Level 2004 MWt Table 2 of Ref. 7.2 Main Steam Flow Rate (at 2004 MWt) 8.335E+06 lb/hr Table 1 of Ref. 7.2 Reactor Water Mass 368,948 lbs Table 1 of Ref. 7.2 Containment Leak Rate 1.2%/day Table 1 of Ref. 7.2 El. of Concrete Floor at Drvwell Bottom 920'-6" Ref. 7.3 El. of Midpoint of Drvwell Spherical Section (Equator) 942'-5" Ref. 7.3 Drvwell Inside Radius (nominal) 31'-0" Ref. 7.4 Pedestal Radius 12'-7" Ref. 7.6 Drywell Concrete Thickness (nominal) 5'-0" Ref. 7.3 Drvwell Free Volume 134,200 ft" Table 1 of Ref. 7.2 Torus Free Volume (maximum) 108,250 ft" Table 1 of Ref. 7.2 Detector Distance From Drvwell Wall 6" to 8" Ref. 7.2 CHRRM Detector Elevation 947'-9" Ref. 7.5 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 "

CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv C""* For. Containment High Range Radiation Monitor Calo No. 2004-07060 areie Lur,.ly"c (CHRRM) Response To Drywell Airborne Activity Rev. 2 JDate X J Safety Related J J Non-Safety Related Page 5 of 24 " Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 3.1-1; Design Input Description Value Reference rad-air to Roentqen conversion factor 1/0.877 Ref. 7.7 Noble Gas Release Rate (Typical at t=30 min) 2.967E+03

µCi/s Table 1 of Ref. 7.2 Noble Gas Release Rate (Nominal at t=30 min) 100,000 µCi/s Assumption 4.3 1131 Inhalation Dose Conversion Factor (FGR-11) 8.89E-9 Sv/Bq inhaled Ref. 7.14 1132 Inhalation Dose Conversion Factor (FGR-11) 1.03E-10 Sv/Bq inhaled Ref. 7.14 1133 Inhalation Dose Conversion Factor (FGR-11) 1.58E-9 Sv/Bq inhaled Ref. 7.14 1134 Inhalation Dose Conversion Factor (FGR-11) 3.55E-11 Sv/Bq inhaled Ref. 7.14 1135 Inhalation Dose Conversion Factor (FGR-11) 3.32E-10 Sv/Bq inhaled Ref. 7.14 Noble Gas Gap Activity*

10% of Kr-85, Ref. 7.9 5% of all others Ref. 7.9 See Table 5.2.4-1 Iodine Gap Activity*

8%ofl-131 Ref. 7.9 5% of all others Ref. 7.9 See Table 5.2.5-1 Noble Gas Normal Operation Activity See Table 5.2.2-1 Ref. 7.8 Iodine Normal Operation Activity See Table 5.2.3-1 Ref. 7.2

Reg Guide 1.183 [Ref 7.9] specifies the fraction of noble gas and iodine core inventories that resides in the fuel rod gaps. Since gap activities are required in this evaluation and not core inventories, the gap activities are obtained from Req Guide 1.183 instead of documents that address reactor core inventories.

Table 3.1-2; EOG Core Fission Product Inventories EOG Core Inventories at Shutdown (no Decay); Core Burnup of 35 GWd/MTU Inventory Inventory lnventorv Nuclide (Ci/MWt) 1'1 Nuclide (Ci/MWt) 1'1 Nuclide (Ci/MWt) 1'1 Kr-83m 3.46E+03 Xe-131m 2.98E+02 1-131 2.68E+04 Kr-85m 7.38E+03 Xe-133m 1.71E+03 1-132 3.90E+04 Kr-85 3.33E+02 Xe-133 5.48E+04 1-133 5.51E+04 Kr-87 1.42E+04 Xe-135m 1.07E+04 1-134 6.09E+04 Kr-88 2.01E+04 Xe-135 1.82E+04 1-135 5.17E+04 Kr-89 2.46E+04 Xe-137 4.83E+04 Xe-138 4.60E+04 Notes: (1) Inventories are the 0 sec values from column 2 of Appendix A to EPU Task Report T0802 [Ref. 7.15]. File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High RanQe Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv s §. Cal". Fo" Containment High Range Radiation Monitor Calo No. 2004-07060 ar@lle Lun*v"* (CHRRM) Response To Drywall Airborne Activity Rev. 2 I Date X I Safety Related . I I Non-Safety Related Page 6 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date 4 ASSUMPTIONS Validated Assumptions

4.1 Drywall

Geometry For the purposes of this calculation the drywall source volume is represented as a cylinder with a solid core. The source distribution between the drywall and torus region is preserved, the correct drywall volume is used to determine the source strength, and the source volume viewed by the detector is essentially the same. This is acceptable for this calculation because the effect of the difference in geometry between the Mark I containment geometry in the vicinity of the CHRRMs and the geometry, as modeled, is small with regard to the source volume that affects the dose rate at the detector.

4.2 Noble

Gas In Reactor Water For the purposes of this calculation it is assumed that the concentration of noble gas in reactor water is the same as the concentration in reactor steam on a unit mass basis (i.e., µCi/gm). This is acceptable because the high flow rates and turbulence in the reactor vessel cause essentially complete mixing of steam and water in the vessel. 4.3 Normal Noble Gas Release Rate For Reactor Water For the purposes of this calculation it is assumed that the nominal noble gas release rate is 100,000 µCi/sec after a 30 minute delay from the reactor nozzle. This is acceptable because the resulting dose rates are directly proportional to the release rate so dose rates for any other release rate may be calculated using the nominal release rate. 4.4 Dose Equivalent 1131 For Reactor Water For the purposes of this calculation it is assumed that the DEl131 is 1 µCi/gm. This is acceptable because the resulting dose rates are directly proportional to the DEl131 so dose rates for any other release rate may be calculated using the nominal DEi 131. 4.5 Plateout For the purposes of this calculation iodine plateout is ignored. This is acceptable because gamma radiation from nearby plated out iodine would approximately compensate for the removal of nearby airborne iodine. (The effects of sources near the detector dominate the dose rate at the detector.

Sources far from the detector, whether airborne or plated out on surfaces, have a much smaller effect.) Unvalidated Assumptions None File GQ308-2.DOC Form GQ-3.08.1 Rev.2 "

L__ __ CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activitv' s *i Col"', For. Containment High Range RadiaUon Monitoc Cole No. 2004-07060 arme Lun*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 7 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date 5 CALCULATIONS

5.1 Geometric

Input For the purposes of this calculation the drywell is represented as a cylinder with a central core (Assumption 4.1 ). See Figure 5.1-1 below. Figure 5.1-1; Dose Rate Calculation Geometrv r SLTH

... 1 y SOURCE----<

T1 T2 T3 T4 TS File GQ308-2.DOC Form GQ-3.08.1 Rev.2 L_ CA-04 -194, "Containment High Ranqe Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv s Caloo. Fo.o Containment H;gh Range Rad;at;on Monitor Calo No. 2004-07060 ar!!fe L..un*y"* (CHRRM) Response To Drywall Airborne Activity Rev. 2 lDate X I Safety Related I I Non-Safety Related Page 8 of Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date T1 =pedestal radius, 12'-7" = 12.58 ft T2 =distance between the pedestal and the drywall at the detector elevation, 947'-9" (calculated below) T3 =drywall concrete thickness

= 5'-0" T4 -not used T5 -not used X =distance from centerline to dose point (calculated below) Y = height of the dose point above the bottom of the drywall SL TH = source height based on drywall volume (calculated below) Calculate T2 T2 is calculated using the drywall radius, R, and the height of the detector above the equator, h. rR2 h R equator T2 = R2-T1 Where: T1 =pedestal radius= 12.58 ft R2 = radius of containment at the detector elevation (947'-9")

R2 = (R2 -h2) 112 R =radius of containment spherical portion (e.g., at equator) R = 31'-0" h = height ofdetector above containment equator h = (detector elevation)

-(equator elevation) h = (947'-9")

-(942'-5")

h = 5'-4" R2 = (R2 -h2) 112 R2 = ((31'-0")2 -(5'-4)2) 112 R2 = (93.2556) 112 R2 = 30.5378 ft (30'-6.45")

T2 = R2-T1 T2 = 30.5378 -12.58 T2 = 17.96 ft Calculate T3 T3 is the drywall concrete thickness=

5'-0" 24 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 "

CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activity' s *§ C*I". For. Containment High Range RadiaUon Monitor Cale No. 2004-07060 oreie L...un*v"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 9 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Calculate X X, the distance from the center of the cylinder to the dose point, is the distance from the CHRRMs to the center of the drywell. X= R2-6" x = 30.54' -0.5' x = 30.04' The distance from the center of the cylinder to the dose point is calculated for a CHRRM detector location that is 6" from the drywell wall. The CHRRM detectors are located approximately 6" to 8" from the wall (Table 3.1-1). The dose rate at 6" from the drywell wall could be slightly lower, but not significantly lower, than the dose rate at a distance of 8" from the wall due to the smaller volume of source between the detector and the wall. Use of the slightly smaller dose rate obtained for the detector location 6" from the wall is conservative since the calculation is determining dose rates for radiation monitor setpoints.

This evaluation does not consider the dose rate contribution to the CHRRM detectors due to backscatter radiation off the drywell wall. The backscatter contribution to the dose rate at the detector location is expected to be no more than a few percent. Ignoring backscatter radiation minimizes the dose rate at the CHRRM detector locations which is conservative for this analysis.

Calculate SL TH SL TH, the source height, is calculated so that the source volume in the calculation geometry is the same as the drywell volume. 1t H (R2 2 -T1 2) = VcALC = VoRYWELL Where: VcALC =source volume in the calculation H = source height R2 =radius of containment at the detector elevation (947'-9")

= 30.5378 ft T1 = pedestal radius= 12.58 ft VoRYWELL = drywell volume ,,; 134,200 ft 3 1t H (R2 2 -T1 2) = VcALC = VoRYWELL n H (30.5378 2 -12.58 2) = 134,200 n H (77 4.301) = 134,200 H = 134,200 I (TI (774.301)) H = 55.16 ft Calculate Y Y, the distance from the bottom of the cylinder to the dose point is the height of the detector minus the height of the drywell floor. y = 947'-9" -920'-6" y = 27'-3" = 27.25' File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activitv' s Cal<0. Fo< Containment High Range Radiation Monitor Calo No. 2004-07060 erme L.un*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 JDate X I Safety Related I I Non-Safety Related Page 10 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date 5.2 Radionuclide Source Input 5.2.1 Drywell Fraction, "IDEPL T" The source terms are calculated based on the reactor water inventory or reactor fuel gap inventory.

These are released to the entire containment, but it is only the activity in the drywell that affects the CHRRMs. Therefore, only the drywell is modeled. The drywell volume is 134,200 ft 3 and the maximum torus free volume is 108,250 ft 3 so the drywell fraction is: F = 134,200 I (134,200 + 108,250) F = 0.554 IDEPL Tis the input parameter in RUNT-PC that is used to input the drywell fraction so IDEPLT = F = 0.554. 5.2.2 Reactor Water Noble Gas The noble gas release rate after a 30-minute delay is first converted to a t=O release rate at the reactor nozzle (i.e., before the 30-minute delay takes place). The noble gas release rate at the reactor nozzle is then converted to the reactor steam concentration at the reactor nozzle. It is then assumed that the reactor water concentration on a unit mass basis is the same as the reactor steam concentration. (Assumption 4.2) Calculate reactor Nozzle (t=O) Release Rate The t=30 minute release rate is converted to the t=O release rate by reversing the decay. An example is shown below. The calculations are summarized in Table 5.2.2-1. S(Kr-88)0

= S(Kr-88ho x e"<Kr-88) x 1000 Where: S(Kr-88)0 = Kr-88 release rate at t=O min (µCi/sec)

S(Kr-88)3 0 = Fraction x 100000 µCi/sec (Fraction from Ref. 7.8) S(Kr-88)3 0 = 5.24E-2 x 100000 µCi/sec S(Kr-88ho

= 5.24E+3 µCi/sec S(Kr-88ho

= Kr-88 release rate at t=30 min (µCi/sec)

A.(Kr-88)

= Kr-88 decay constant (sec-1) 1800 = seconds in 30 minutes S(Kr-88)0

= S(Kr-88)30xeMKr-88)x1000 S(Kr-88)0

= 5.24E3 x es.10E-os x 1000 S(Kr-88)0 = 5.92E3 µCi/sec File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne

§

'"" Containment High Range Radiation Monttm C*lo No. 2004-07060 nreie L...un*v"" (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date s L__ __ _ Client Project Proj. No X I Safety Related I I Non-Safety Related Page 11 of 24 NSP Prepared by Date Monticello NGP Reviewed by Date 12400-045 Equip. No. Approved by Date Table 5.2.2-1; Reactor Nozzle Noble Gas Release Rate at t=O C100.000 µCl/sec at t=30 min) Nuclide Half-Life A-Fraction Release Rate Release Rate Ref. 7.11 (sec-1) (t= 30min) (t=30 min) (t=O min) Ref. 7.8 (µCi/sec) (µCi/sec)

Kr-83m 1.86 hr 1.04E-04 9.36E-03 9.36E+02 1.13E+03 Kr-85m 4.48 hr 4.30E-05 1.64E-02 1.64E+03 1.77E+03 Kr-85 10.73yr 2.05E-09 6.40E-05 6.40E+OO 6.40E+OO Kr-87 1.27 hr 1.52E-04 5.11 E-02 5.11E+03 6.71E+03 Kr-88 2.84 hr 6.78E-05 5.24E-02 5.24E+03 5.92E+03 Kr-89 3.15 m 3.67E-03 2.18E-01 2.18E+04 1.60E+07 Xe-131m 11.9 d 6.74E-07 5.23E-05 5.23E+OO 5.24E+OO Xe-133m 2.19 d 3.66E-06 7.82E-04 7.82E+01 7.87E+01 Xe-133 5.243 d 1.53E-06 2.19E-02 2.19E+03 2.20E+03 Xe-135m 15.3 m 7.55E-04 6.41E-02 6.41E+03 2.50E+04 Xe-135 9.10 hr 2.12E-05 5.92E-02 5.92E+03 6.15E+03 Xe-137 3.82 m 3.02E-03 2.88E-01 2.88E+04 6.66E+06 Xe-138 14.1 m 8.19E-04 2.18E-01 2.18E+04 9.53E+04 Total 1.0E+OO 1.0E+05 2.29E+07 Calculate Reactor Water Noble Gas Inventory For 100,000 µCi/sec after 30 Minute Delay The reactor water inventory is calculated by assuming the reactor water activity (µCi/gm) is the same as the steam activity at the reactor nozzle (µCi/gm) (Assumption 4.2). The steam activity at the reactor nozzle (µCi/gm at t=O) is calculated assuming a release rate of 100,000 µCi/sec after 30 minute delay (t=30 min), back-calculating the release rate at t=O, and using the total steam flow at rated power. An example is shown below and the calculations are summarized in Table 5.2.2-2. INV(Kr-88)Rw

= ACT(Kr-88)Rw x MRw ACT(Kr-88)Rw

= ACT(Kr-88)RsTEAM

= S(Kr-88)0 I FsTEAM Where: INV(Kr-88)Rw

= inventory in reactor water (Ci) ACT(Kr-88)Rw

= activity in reactor water (µCi/gm) MRw = mass of reactor water (gm) MRw = 368948 lbs x 453.59 gm/lb MRw = 1.67E+08 gm ACT(Kr-88)RsTEAM

=activity in reactor steam (µCi/gm) S(Kr-88)0 = Kr-88 release rate at t=O min (µCi/sec)

FsTEAM =Steam flow rate (g/sec) FsTEAM = 8.335E+06 lbs/hr x 453.59 gm/lb/ 3600 sec/hr FsTEAM = 1.050E+06 gm/sec ACT(Kr-88)Rw

= ACT(Kr-88)RSTEAM

= S(Kr-88)0 I FsTEAM ACT(Kr-88)Rw

= 5.92E3 / 1.050E+06 ACT(Kr-88)Rw

= 5.64E-03 µCi/gm File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activit11' s §. Cal". Fo.o Containment High Range Radiation Monitor Calo No. 2004-07060 a.,.e 1-un*y"" (CHRRM) Response To Drywell Airborne Activity Rev. 2 !Date X I Safety Related I I Non-Safety Related Page 12 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.2.2-2; Noble Gas Reactor Water Inventory at t=O C100.000 µCi/sec at t=30 min) Nuclide Nuclide Release Rate Steam Steam Reactor Water Reactor Reactor ID (t=O min) Flow Activity Activity Water Water (µCi/sec) (g/sec) (µCi/gm) (µCi/gm) Mass Inventory (gm) (Ci) Kr-83m 45 1.13E+03 1.050E+06 1.07E-03 1.07E-03 1.67E+08 1.80E-01 Kr-85m 54 1.77E+03 1.050E+06 1.69E-03 1.69E-03 1.67E+08 2.82E-01 Kr-85 55 6.40E+OO 1.050E+06 6.09E-06 6.09E-06 1.67E+08 1.02E-03 Kr-87 65 6.71 E+03 1.050E+06 6.39E-03 6.39E-03 1.67E+08 1.07E+OO Kr-88 70 5.92E+03 1.050E+06 5.64E-03 5.64E-03 1.67E+08 9.43E-01 Kr-89 74 1.60E+07 1.050E+06 1.53E+01 1.53E+01 1.67E+08 2.56E+03 Xe-131m 301 5.24E+OO 1.050E+06 4.99E-06 4.99E-06 1.67E+08 8.34E-04 Xe-133m 311 7.87E+01 1.050E+06 7.50E-05 7.50E-05 1.67E+08 1.25E-02 Xe-133 312 2.20E+03 1.050E+06 2.09E-03 2.09E-03 1.67E+08 3.50E-01 Xe-135m 324 2.50E+04 1.050E+06 2.38E-02 2.38E-02 1.67E+08 3.98E+OO Xe-135 325 6.15E+03 1.050E+06 5.86E-03 5.86E-03 1.67E+08 9.80E-01 Xe-137 334 6.66E+06 1.050E+06 6.34E+OO 6.34E+OO 1.67E+08 1.06E+03 Xe-138 339 9.53E+04 1.050E+06 9.07E-02 9.07E-02 1.67E+08 1.52E+01 Total 2.29E+07 1.050E+06 2.18E+01 2.18E+01 1.67E+08 3.64E+03 5.2.3 Reactor Water Iodine The measured reactor water radio-iodine concentrations are the starting point for calculating the total reactor water inventory of each radio-iodine nuclide (1131, 1132, 1133, 1134, 1135). The reactor water dose equivalent 1131 in µCi/gm (DEi 131) is calculated using the measured radio-iodine nuclide concentrations and FGR-11 inhalation effective dose conversion factors. The reactor water DEi 131 is then used to calculate the ratio to convert the reactor water measured DEi 131 to a DEi 131 of 1 µCi/gm. The inventory is calculated for a DEi 131 of 1 µCi/gm for convenience.

It is multiplied by the DEl131 of interest to obtain the reactor water inventory (e.g., multiplied by 0.2 to obtain the inventory for a DEl131 of 0.2 µCi/gm). An example is shown below. The calculations are summarized in Table 5.2.3-1. INV(l132)Rw

= ACT(l132)Rw x MRw ACT(l132)Rw

= ACT(l132)MEAS I DEl131MEAS DEl131MEAS

= l:(ACTi x DEl131i) INV(l132)Rw

= (ACT(l132)MEAS I DEl131MEAs) x MRw . INV(l132)Rw

= 1.0E-06 x (ACT(l132)MEAS

/ l:(ACT; x DEl131;))

x MRw Where: INV(l132)Rw

= 1132 inventory in reactor water (Ci) ACT(l 132)Rw = activity in reactor water (µCi/gm) File GQ308-2.DOC MRw = mass of reactor water (gm)

DEl131 MEAS = DEl131 of measured reactor water iodine concentrations ACT;= measured activity of iodine nuclide i, (1131. 1132, 1133, 1134, 1135) DEl131i = 1131 dose equivalent of each iodine nuclide i = DCFi I DCF1131 Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activitv' s *§. Coles. For. Conta;nment H;gh Range Rad;ation Mon;for catc No. 2004-07060

o.,.e L.un*y"" (CHRRM) Response To Drywall Airborne Activity Rev. 2 I Date X J Safety Related I I Non-Safety Related Page 13 of Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date DCFi = FGR-11 Inhalation Effective dose conversion factor for nuclide i DCF1 1 3 1 = FGR-11 Inhalation Effective dose conversion factor for 1131 1.0E-06 = conversion from µCi to Ci Iodine Nuclide 1-131 1-132 1-133 1-134 1-135 Total DEl132MEAS

= ACT(l132)MEAS x DCFi I DCF1131 DEl132MEAS

= 2.02E-04 x 1.03E-10 I 8.89E-09 DEl132MEAs

= 2.34E-06 µCi/gm L(ACTi x DEl131i) = 4.11 E-05 (See Table 5.2.3-1 for summation)

ACT(l132)Rw

= (ACT(l132)MEAs I L(ACTi x DEl131i) ACT(l132)Rw

= 2.02E-04 I 4.11 E-05 ACT(l132)Rw

= 4.92E+OO µCi/gm MRw = 368948 lbs x 453.59 gm/lb MRw = 1.67E+08 gm INV(l132)Rw

= ACT(l132)Rw x MRw x 1.0E-06 INV(l132)Rw

= 4.92E+OO x 1.67E+08x1..0E-06 INV(l132)Rw

= 8.23E+02 Ci Table 5.2.3-1: Reactor Water Inventory For DEl131=1.0 uCi/qm Nuclide FGR-11 FGR-11 Measured Measured Reactor ID Inhalation DEl131 Ratio Reactor Reactor Water Effective Dose Water Water Activity at Factors Iodine DEl131 1µCi/gm (SV/Bq) (µCi/gm) (µCi/gm)

DEl131 Ref. 7.2 300 8.89E-09 1.00E+OO 8.04E-06 8.04E-06 1.96E-01 305 1.03E-10 1.16E-02 2.02E-04 2.34E-06 4.92E+OO 310 1.58E-09 1.78E-01 1.09E-04 1.94E-05 2.65E+OO 316 3.55E-11 3.99E-03 6.68E-04 2.67E-06 1.63E+01 323 3.32E-10 3.73E-02 2.32E-04 8.66E-06 5.65E+OO 1.22E-03 4.11E-05 2.97E+01 5.2.4 Gap Activity Reactor Water Mass (gm) 1.67E+08 1.67E+08 1.67E+08 1.67E+08 1.67E+08 Reactor Water Inventory (Ci) 3.27E+01 8.23E+02 4.44E+02 2.72E+03 9.45E+02 4.97E+03 24 The Kr-85 gap activity is 10% of the total Kr-85 in the core, the 1-131 gap activity is 8% of the total 1-131 in the core, and for all other nuclides (noble gas and. iodine) the gap activity is 5% of the total core activity (Design Input Table 3.1-1). The reactor core activities in Design Input Table 3.1-2 are core activities in units of curies per MWt. The core activity values in Table 3.1-2 must be multiplied by the reactor EPU power level of 2004 MWt to obtain total radionuclide inventories in the reactor core and must be multiplied by the appropriate fraction (10%, 8% or 5%) to convert from the core activity to the gap activity.

The calculation is carried out as follows. Kr-85: 1131: All others: File GQ308-2.DOC I = lcoRE (Ci/MWt) x 2004 MWt x 0.1 I = lcoRE (Ci/MWt) x 2004 MWt x 0.08 I = lcoRE (Ci/MWt)x 2004 MWt x 0.05 Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activit11' s *§-Caloo. For. Containment High Range Radiation Manito' C"c No. 2004-07060 L.un*y"c (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 14 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date The EPU gap activities (Curies) for 2004 MWt are calculated in Table 5.2.4-1 below. Table 5.2.4-1: Gap Activity Core Gap Core Gap Noble Core lnventory(2) Gap Activity (4) Iodine Core lnventory(2) Gap Activity(4) Gas Activity (1) (Curies) Fraction (Ci) 2004 Nuclide Activity (1) (Curies) Fraction (Ci) 2004 Nuclide (Ci/MWt) 2004 MWt (3) MWt (Ci/MWt) 2004 MWt (3) MWt Kr-83m 3.46E+03 6.93E+06 0.05 3.47E+05 1-131 2.68E+04 5.37E+07 0.08 4.30E+06 Kr-85m 7.38E+03 1.48E+07 0.05 7.39E+05 1-132 3.90E+04 7.82E+07 0.05 3.91 E+06 Kr-85 3.33E+02 6.67E+05 0.1 6.67E+04 1-133 5.51 E+04 1.10E+08 0.05 5.52E+06 Kr-87 1.42E+04 2.85E+07 0.05 1.42E+06 1-134 6.09E+04 1.22E+08 0.05 6.10E+06 Kr-88 2.01E+04 4.03E+07 0.05 2.01 E+06 1-135 5.17E+04 1.04E+08 0.05 5.18E+06 Kr-89 2.46E+04 4.93E+07 0.05 2.46E+06 TOTAL 4.68E+08 2.50E+07 Xe-131m 2.98E+02 5.97E+05 0.05 2.99E+04 Xe-133m 1.71 E+03 3.43E+06 0.05 1.71E+05 Xe-133 5.48E+04 1.10E+08 0.05 5.49E+06 Xe-135m 1.07E+04 2.14E+07 0.05 1.07E+06 Xe-135 1.82E+04 3.65E+07 0.05 1.82E+06 Xe-137 4.83E+04 9.68E+07 0.05 4.84E+06 Xe-138 4.60E+04 9.22E+07 0.05 4.61 E+06 TOTAL 5.01 E+08 2.51 E+07 Notes: (1) Reactor core radionuclide activities (Ci/MWt) are from Design Input Table 3.1-2. (2) The reactor core inventory for EPU is obtained by multiplying the reactor core activities from columns 2 and 7 by the EPU reactor power level of 2004 MWt. For Kr-85, the reactor core inventory

= 3.33E+02 Ci/MWt x 2004 MWt = 6.67E+05 Ci. (3) Gap fractions are from Design lnputTable 3.1-1. (4) The gap activity is obtained by multiplying the reactor core activity by the gap fraction.

For Kr-85, gap activity=

6.67E+05 Ci x 0.1 = 6.67E+04 Ci. 5.2.5 Gap Activity DEl131 The nuclide mix in the gap differs from the nuclide mix in normal reactor water. Therefore the DEl131 is recalculated for use in calculating the dose response to airborne iodine for gap releases.

The method and equations are essentially the same as in Section 5.2.3 of this calculation except that the DEl131 activity in the gap is divided by the reactor water mass to yield an effective DEl131 specific activity in reactor water for each iodine nuclide. The effective DEl131 specific activity in reactor water for the gap release, 3.32E+04 µCi/gm, is calculated in Table 5.2.5-1 below. File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity'

§ Calo.. For. Containment High Range Radiation Monito' Calo No. 2004-07060

ar!!le u...n*y"c (CHRRM) Response To Drywell Airborne Activity Rev. 2 JDate X J Safety Related J J Non-Safety Related Page 15 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.2.5-1; Reactor Water DEl131 For Gap Release Nuclide FGR-11 FGR-11 2004 MWt Reactor Water Gap Activity Inhalation Dose DEl131 Gap Activity Mass RW DEl131 Factors (SV/Bq) Ratio (Ci) <1> (gm) (l.!Ci/qm)

<2> 1-131 8.89E-09 1.00E+OO 4.30E+06 1.67E+08 2.57E+04 1-132 1.03E-10 1.16E-02 3.91E+06 1.67E+08 2.72E+02 1-133 1.58E-09 1.78E-01 5.52E+06 1.67E+08 5.88E+03 1-134 3.55E-11 3.99E-03 6.10E+06 1.67E+08 1.46E+02 1-135 3.32E-10 3.73E-02 5.18E+06 1.67E+08 1.16E+03 Total 2.50E+07 3.32E+04 Notes: (1) Activity values are obtained from Column 10 of Table 5.2.4-1. (2) The Gap Activity RW DEl131 value is obtained by multiplying the gap activity value in column 4 by the DEl131 Ratio in column 3 and by the conversion factor of 1 E+6 µCi/Ci and then dividing by the reactor water mass in column 5. 5.3 Dose Rates in R/hr The computer program RUNT-PC calculates the dose rates at the CHRRM location in units of rads-air/hr.

These dose rates are converted to units of R/hr by multiplying by a conversion factor F. F = 1 I (0.877 R/rad-air)

[Ref. 7.7] The computer output dose rates in rads-air/hr and R/hr are contained in Tables 5.3-1, 5.3-2, 5.3-3, and 5.3-4 below. File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell d ........ _c<< Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060 (CHRRM) Response To Drywell Airborne Activity Rev. 2 jDate Airborne Activity" X I Safety Related I I Non-Safety Related Page 16 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.3-1; Reactor Water Noble Gas Gamma Dose Rates Time Reactor Water Noble Gas Time Reactor Water Noble Gas Time Reactor Water Noble Gas Time Reactor Water Noble Gas 100,000 µCi/sec 100,000 µCi/sec 100,000 µCi/sec 100,000 µCi/sec (30 min delay) (30 min delay) (30 min delay) (30 min delay) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) O.OOE+OO O.OOE+OO O.OOE+OO 9.17E-01 4.95E-01 5.64E-01 1.00E+01 1.60E-03 1.83E-03 1.20E+02 8.51E-05 9.70E-05 2.78E-04 1.93E+01 2.20E+01 1.00E+OO 4.01 E-01 4.57E-01 1.20E+01 1.18E-03 1.35E-03 1.44E+02 7.43E-05 8.47E-05 1.67E-03 1.90E+01 2.17E+01 1.08E+OO 3.25E-01 3.71 E-01 1.40E+01 9.05E-04 1.03E-03 1.68E+02 6.49E-05 7.40E-05 3.06E-03 1.87E+01 2.13E+01 1.17E+OO 2.64E-01 3.01 E-01 1.60E+01 7.18E-04 8.19E-04 1.92E+02 5.69E-05 6.49E-05 4.44E-03 1.85E+01 2.11 E+01 1.25E+OO 2.15E-01 2.46E-01 1.80E+01 5.88E-04 6.70E-04 2.16E+02 4.99E-05 5.69E-05 5.83E-03 1.82E+01 2.08E+01 1.33E+OO 1.76E-01 2.01 E-01 2.00E+01 5.64E-04 2.40E+02 4.38E-05 5.00E-05 7.22E-03 1.80E+01 2.05E+01 1.42E+OO 1.44E-01 1.65E-01 2.20E+01 4.25E-04 4.85E-04 2.64E+02 3.86E-05 4.40E-05 8.61E-03 1.77E+01 2.02E+01 1.50E+OO 1.19E-01 1.36E-01 2.40E+01 3.73E-04 4.25E-04 2.88E+02 3.40E-05 3.88E-05 1.69E-02 1.63E+01 1.86E+01 1.58E+OO 9.83E-02 1.12E-01 2.80E+01 3.00E-04 3.42E-04 3.12E+02 3.01E-05 3.43E-05 2.53E-02 1.51 E+01 1.72E+01 1.67E+OO 8.16E-02 9.30E-02 3.20E+01 2.51E-04 2.86E-04 3.36E+02 2.66E-05 3.03E-05 3.36E-02 1.39E+01 1.59E+01 1.75E+OO 6.81E-02 7.76E-02 3.60E+01 2.17E-04 2.48E-04 3.60E+02 2.36E-05 2.69E-05 4.19E-02 1.29E+01 1.47E+01 1.83E+OO 5.71E-02 6.51E-02 4.00E+01 1.92E-04 2.19E-04 3.84E+02 2.10E-05 2.40E-05 5.03E-02 1.20E+01 1.37E+01 1.92E+OO 4.82E-02 5.50E-02 4.40E+01 1.74E-04 1.98E-04 4.08E+02 1.87E-05 2.14E-05 5.86E-02 1.11 E+01 1.27E+01 2.00E+OO 4.10E-02 4.67E-02 4.80E+01 1.60E-04 1.82E-04 4.32E+02 1.68E-05 1.91 E-05 6.69E-02 1.04E+01 1.18E+01 2.50E+OO 1.80E-02 2.05E-02 5.20E+01 1.48E-04 1.69E-04 4.56E+02 1.50E-05 1.71 E-05 7.53E-02 9.68E+OO 1.10E+01 3.00E+OO 1.04E-02 1.19E-02 5.60E+01 1.39E-04 1.59E-04 4.80E+02 1.35E-05 1.54E-05 8.36E-02 9.05E+OO 1.03E+01 3.50E+OO 7.36E-03 8.39E-03 6.00E+01 1.32E-04 1.51 E-04 5.04E+02 1.22E-05 1.39E-05 1.67E-01 5.09E+OO 5.80E+OO 4.00E+OO 5.84E-03 6.66E-03 6.40E+01 1.26E-04 1.44E-04 5.28E+02 1.11 E-05 1.26E-05 2.50E-01 3.35E+OO 3.82E+OO 4.50E+OO 4.92E-03 5.61E-03 6.80E+01 1.21 E-04 1.38E-04 5.52E+02 1.01 E-05 1.15E-05 3.34E-01 2.44E+OO 2.78E+OO 5.00E+OO 4.27E-03 4.87E-03 7.20E+01 1.17E-04 1.33E-04 5.76E+02 9.17E-06 1.05E-05 4.17E-01 1.87E+OO 2.13E+OO 5.50E+OO 3.77E-03 4.30E-03 7.60E+01 1.13E-04 1.29E-04 6.00E+02 8.40E-06 9.57E-06 5.00E-01 1.47E+OO 1.68E+OO 6.00E+OO 3.36E-03 3.84E-03 8.00E+01 1.09E-04 1.25E-04 6.24E+02 7.71E-06 8.79E-06 5.84E-01 1.18E+OO 1.34E+OO 6.50E+OO 3.02E-03 3.45E-03 8.40E+01 1.06E-04 1.21 E-04 6.48E+02 7.11 E-06 8.11E-06 6.67E-01 9.43E-01 1.08E+OO 7.00E+OO 2.73E-03 3.12E-03 8.80E+01 1.03E-04 1.18E-04 6.72E+02 6.58E-06 7.50E-06 7.50E-01 7.59E-01 8.66E-01 7.50E+OO 2.48E-03 2.83E-03 9.20E+01 1.01 E-04 1.15E-04 6.96E+02 6.11E-06 6.97E-06 8.34E-01 6.12E-01 6.98E-01 8.00E+OO 2.26E-03 2.58E-03 9.60E+01 9.82E-05 1.12E-04 7.20E+02 5.69E-06 6.49E-06 File GQ308-2.DOC Form GQ-3.08.1 Rev.2

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CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Cales. For: Containment High Range Radiation Monitor Cale No . 2004-07060

.. 2 !Date (CHRRM) Response To Drywell Airborne Activity Rev. X I Safety Related I I Non-Safety Related Page 17 of 24 Airborne Activity" Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.3-2; Reactor Water Iodine Gamma Dose Rates Time Reactor Water Iodine Time Reactor Water Iodine Time Reactor Water Iodine Time Reactor Water Iodine DEl131 = 1 uCi/qm DEl131 = 1 uCi/qm DEl131=1 uCi/qm DEl131 = 1 uCi/qm (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) O.OOE+OO O.OOE+OO O.OOE+OO 9.17E-01 2.79E+01 3.18E+01 1.00E+01 3.85E+OO 4.39E+OO 1.20E+02 7.48E-02 8.53E-02 2.78E-04 4.58E+01 5.22E+01 1.00E+OO 2.67E+01 3.05E+01 1.20E+01 3.19E+OO 3.64E+OO 1.44E+02 5.74E-02 6.55E-02 1.67E-03 4.57E+01 5.21E+01 1.08E+OO 2.57E+01 2.93E+01 1.40E+01 2.69E+OO 3.07E+OO 1.68E+02 4.72E-02 5.38E-02 3.06E-03 4.57E+01 5.21E+01 1.17E+OO 2.47E+01 2.81E+01 1.60E+01 2.30E+OO 2.62E+OO 1.92E+02 4.03E-02 4.59E-02 4.44E-03 4.57E+01 5.21E+01 1.25E+OO 2.37E+01 2.70E+01 1.80E+01 1.99E+OO 2.26E+OO 2.16E+02 3.52E-02 4.01E-02 5.83E-03 4.56E+01 5.20E+01 1.33E+OO 2.28E+01 2.60E+01 2.00E+01 1.73E+OO 1.97E+OO 2.40E+02 3.11 E-02 3.54E-02 7.22E-03 4.56E+01 5.19E+01 1.42E+OO 2.19E+01 2.50E+01 2.20E+01 1.51E+OO 1.73E+OO 2.64E+02 2.76E-02 3.15E-02 8.61 E-03 4.55E+01 5.19E+01 1.50E+OO 2.11E+01 2.41 E+01 2.40E+01 1.33E+OO 1.52E+OO 2.88E+02 2.46E-02 2.81E-02 1.69E-02 4.53E+01 5.17E+01 1.58E+OO 2.04E+01 2.32E+01 2.80E+01 1.05E+OO 1.20E+OO 3.12E+02 2.20E-02 2.51E-02 2.53E-02 4.51 E+01 5.14E+01 1.67E+OO 1.96E+01 2.24E+01 3.20E+01 8.40E-01 9.57E-01 3.36E+02 1.97E-02 2.24E-02 3.36E-02 4.49E+01 5.12E+01 1.75E+OO 1.90E+01 2.16E+01 3.60E+01 6.83E-01 7.79E-01 3.60E+02 1.76E-02 2.01E-02 4.19E-02 4.47E+01 5.09E+01 1.83E+OO 1.83E+01 2.09E+01 4.00E+01 5.64E-01 6.43E-01 3.84E+02 1.58E-02 1.80E-02 5.03E-02 4.45E+01 5.07E+01 1.92E+OO 1.77E+01 2.02E+01 4.40E+01 4.72E-01 5.38E-01 4.08E+02 1.41 E-02 1.61 E-02 5.86E-02 4.43E+01 5.05E+01 2.00E+OO 1.71 E+01 1.95E+01 4.80E+01 4.00E-01 4.56E-01 4.32E+02 1.27E-02 1.44E-02 6.69E-02 4.40E+01 5.02E+01 2.50E+OO 1.42E+01 1.62E+01 5.20E+01 3.43E-01 3.91 E-01 4.56E+02 1.14E-02 1.30E-02 7.53E-02 4.38E+01 5.00E+01 3.00E+OO 1.20E+01 1.37E+01 5.60E+01 2.98E-01 3.39E-01 4.80E+02 1.02E-02 1.16E-02 8.36E-02 4.36E+01 4.97E+01 3.50E+OO 1.04E+01 1.19E+01 6.00E+01 2.61 E-01 2.97E-01 5.04E+02 9.16E-03 1.04E-02 1.67E-01 4.16E+01 4.74E+01 4.00E+OO 9.18E+OO 1.05E+01 6.40E+01 2.30E-01 2.62E-01 5.28E+02 8.22E-03 9.38E-03 2.50E-01 3.97E+01 4.53E+01 4.50E+OO 8.21E+OO 9.36E+OO 6.80E+01 2.05E-01 2.34E-01 5.52E+02 7.39E-03 8.42E-03 3.34E-01 3.79E+01 4.32E+01 5.00E+OO 7.43E+OO 8.47E+OO 7.20E+01 1.84E-01 2.09E-01 5.76E+02 6.64E-03 7.57E-03 4.17E-01 3.62E+01 4.13E+01 5.50E+OO 6.79E+OO 7.75E+OO 7.60E+01 1.66E-01 1.89E-01 6.00E+02 5.97E-03 6.81E-03 5.00E-01 3.46E+01 3.95E+01 6.00E+OO 6.26E+OO 7.14E+OO 8.00E+01 1.51 E-01 1.72E-01 6.24E+02 5.37E-03 6.12E-03 5.84E-01 3.31E+01 3.78E+01 6.50E+OO 5.81E+OO 6.63E+OO 8.40E+01 1.38E-01 1.57E-01 6.48E+02 4.83E-03 5.51E-03 6.67E-01 3.17E+01 3.61E+01 7.00E+OO 5.42E+OO 6.18E+OO 8.80E+01 1.27E-01 1.44E-01 6.72E+02 4.34E-03 4.95E-03 7.50E-01 3.03E+01 3.46E+01 7.50E+OO 5.0BE+OO 5.79E+OO 9.20E+01 1.17E-01 1.33E-01 6.96E+02 3.91E-03 4.46E-03 8.34E-01 2.91E+01 3.31E+01 8.00E+OO 4.78E+OO 5.45E+OO 9.60E+01 1.0BE-01 1.23E-01 7.20E+02 3.52E-03 4.01E-03 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activity" Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060

.-:.: L..L..-.ely

c (CHRRM) Response To Drywell Airborne Activity Rev

2 !Date X I Safety Related I I Non-Safety Related Page 18 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.3-3; Gap Activity Noble Gas Gamma Dose Rates (Noble Gas Gap Activity of 2.51 E+07 Ci. 2004 MWt) Time Gap Activity Noble Gas Time Gap Activity Noble Gas Time Gap Activity Noble Gas Time Gap Activity Noble Gas (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr} (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) O.OOE+OO O.OOE+OO O.OOE+OO 9.17E-01 3.30E+04 3.77E+04 1.00E+01 5.23E+03 5.96E+03 1.20E+02 1.23E+03 1.41 E+03 2.78E-04 6.86E+04 7.82E+04 1.00E+OO 3.17E+04 3.61E+04 1.20E+01 4.34E+03 4.95E+03 1.44E+02 1.07E+03 1.22E+03 1.67E-03 6.82E+04 7.78E+04 1.08E+OO 3.05E+04 3.47E+04 1.40E+01 3.76E+03 4.29E+03 1.68E+02 9.25E+02 1.05E+03 3.06E-03 6.79E+04 7.75E+04 1.17E+OO 2.93E+04 3.34E+04 1.60E+01 3.36E+03 3.83E+03 1.92E+02 8.01E+02 9.13E+02 4.44E-03 6.76E+04 7.71E+04 1.25E+OO 2.82E+04 3.22E+04 1.80E+01 3.08E+03 3.51 E+03 2.16E+02 6.94E+02 7.91E+02 5.83E-03 6.73E+04 7.68E+04 1.33E+OO 2.72E+04 3.10E+04 2.00E+01 2.88E+03 3.28E+03 2.40E+02 6.01E+02 6.85E+02 7.22E-03 6.70E+04 7.64E+04 1.42E+OO 2.62E+04 2.99E+04 2.20E+01 2.72E+03 3.10E+03 2.64E+02 5.21E+02 5.94E+02 8.61E-03 6.67E+04 7.61E+04 1.50E+OO 2.53E+04 2.89E+04 2.40E+01 2.60E+03 2.96E+03 2.88E+02 4.51E+02 5.14E+02 1.69E-02 6.50E+04 7.42E+04 1.58E+OO 2.45E+04 2.79E+04 2.80E+01 2.42E+03 2.76E+03 3.12E+02 3.91E+02 4.46E+02 2.53E-02 6.35E+04 7.24E+04 1.67E+OO 2.37E+04 2.70E+04 3.20E+01 2.29E+03 2.61E+03 3.36E+02 3.39E+02 3.87E+02 3.36E-02 6.21E+04 7.08E+04 1.75E+OO 2.30E+04 2.62E+04 3.60E+01 2.18E+03 2.49E+03 3.60E+02 2.94E+02 3.35E+02 4.19E-02 6.08E+04 6.94E+04 1.83E+OO 2.23E+04 2.54E+04 4.00E+01 2.10E+03 2.39E+03 3.84E+02 2.55E+02 2.91E+02 5.03E-02 5.97E+04 6.80E+04 1.92E+OO 2.16E+04 2.46E+04 4.40E+01 2.02E+03 2.31E+03 4.08E+02 2.21E+02 2.52E+02 5.86E-02 5.86E+04 6.68E+04 2.00E+OO 2.10E+04 2.39E+04 4.80E+01 1.96E+03 2.23E+03 4.32E+02 1.92E+02 2.19E+02 6.69E-02 5.76E+04 6.57E+04 2.50E+OO 1.79E+04 2.05E+04 5.20E+01 1.90E+03 2.16E+03 4.56E+02 1.67E+02 1.90E+02 7.53E-02 5.67E+04 6.47E+04 3.00E+OO 1.57E+04 1.79E+04 5.60E+01 1.84E+03 2.10E+03 4.80E+02 1.45E+02 1.65E+02 8.36E-02 5.59E+04 6.37E+04 3.50E+OO 1.40E+04 1.59E+04 6.00E+01 1.79E+03 2.04E+03 5.04E+02 1.26E+02 1.43E+02 1.67E-01 5.02E+04 5.73E+04 4.00E+OO 1.25E+04 1.43E+04 6.40E+01 1.74E+03 1.99E+03 5.28E+02 1.09E+02 1.24E+02 2.50E-01 4.70E+04 5.36E+04 4.50E+OO 1.14E+04 1.30E+04 6.80E+01 1.70E+03 1.94E+03 5.52E+02 9.47E+01 1.08E+02 3.34E-01 4.47E+04 5.10E+04 5.00E+OO 1.04E+04 1.18E+04 7.20E+01 1.66E+03 1.89E+03 5.76E+02 8.23E+01 9.39E+01 4.17E-01 4.27E+04 4.87E+04 5.50E+OO 9.53E+03 1.09E+04 7.60E+01 1.61E+03 1.84E+03 6.00E+02 7.16E+01 8.16E+01 5.00E-01 4.09E+04 4.66E+04 6.00E+OO 8.78E+03 1.00E+04 8.00E+01 1.57E+03 1.79E+03 6.24E+02 6.23E+01 7.10E+01 5.84E-01 3.91E+04 4.46E+04 6.50E+OO 8.13E+03 9.27E+03 8.40E+01 1.54E+03 1.75E+03 6.48E+02 5.42E+01 6.18E+01 6.67E-01 3.75E+04 4.27E+04 7.00E+OO 7.55E+03 8.61E+03 8.80E+01 1.50E+03 1.71E+03 6.72E+02 4.72E+01 5.38E+01 7.50E-01 3.59E+04 4.09E+04 7.50E+OO 7.04E+03 8.03E+03 9.20E+01 1.46E+03 1.67E+03 6.96E+02 4.12E+01 4.69E+01 8.34E-01 3.44E+04 3.92E+04 8.00E+OO 6.59E+03 7.52E+03 9.60E+01 1.43E+03 1.63E+03 7.20E+02 3.59E+01 4.09E+01 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04-194, "Containment Hiqh Ranqe Radiation Monitor (CHRRM) Response to Drvwell Airborne Activity" Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060 .a;:.: L.u!nmly

c (CHRRM) Response To Drywell Airborne Activity Rev . 2 !Date X I Safety Related I I Non-Safety Related Page 19 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Table 5.3-4; Gap Activity Iodine Gamma Dose Rates (DEl131= 3.32E+04 µCi/gm. 2004 MWt) Time Gap Activity Iodine Time Gap Activity Iodine Time Gap Activity Iodine Time Gap Activity Iodine (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) (hrs) (rad-air/hr) (R/hr) O.OOE+OO O.OOE+OO O.OOE+OO 9.17E-01 1.16E+05 1.32E+05 1.00E+01 3.37E+04 3.84E+04 1.20E+02 5.05E+03 5.76E+03 2.78E-04 1.62E+05 1.85E+05 1.00E+OO 1.13E+05 1.29E+05 1.20E+01 2.98E+04 3.39E+04 1.44E+02 4.45E+03 5.07E+03 1.67E-03 1.62E+05 1.85E+05 1.08E+OO 1.10E+05 1.25E+05 1.40E+01 2.67E+04 3.04E+04 1.68E+02 3.98E+03 4.53E+03 3.06E-03 1.62E+05 1.84E+05 1.17E+OO 1.07E+05 1.22E+05 1.60E+01 2.42E+04 2.76E+04 1.92E+02 3.57E+03 4.08E+03 4.44E-03 1.62E+05 1.84E+05 1.25E+OO 1.04E+05 1.19E+05 1.80E+01 2.22E+04 2.53E+04 2.16E+02 3.22E+03 3.68E+03 5.83E-03 1.62E+05 1.84E+05 1.33E+OO 1.02E+05 1.16E+05 2.00E+01 2.04E+04 2.33E+04 2.40E+02 2.91E+03 3.32E+03 7.22E-03 1.62E+05 1.84E+05 1.42E+OO 9.94E+04 *1.13E+05 2.20E+01 1.89E+04 2.16E+04 2.64E+02 2.63E+03 3.00E+03 8.61E-03 1.62E+05 1.84E+05 1.50E+OO 9.71 E+04 1.11E+05 2.40E+01 1.76E+04 2.01E+04 2.88E+02 2.38E+03 2.72E+03 1.69E-02 1.61 E+05 1.83E+05 1.58E+OO 9.49E+04 1.08E+05 2.80E+01 1.55E+04 1.77E+04 3.12E+02 2.16E+03 2.46E+03 2.53E-02 1.60E+05 1.83E+05 1.67E+OO 9.28E+04 1.06E+05 3.20E+01 1.38E+04 1.58E+04 3.36E+02 1.95E+03 2.22E+03 3.36E-02 1.60E+05 1.82E+05 1.75E+OO 9.07E+04 1.03E+05 3.60E+01 1.25E+04 1.43E+04 3.60E+02 1.77E+03 2.01E+03 4.19E-02 1.59E+05 1.82E+05 1.83E+OO 8.88E+04 1.01E+05 4.00E+01 1.15E+04 1.31 E+04 3.84E+02 1.60E+03 1.82E+03 5.03E-02 1.59E+05 1.81E+05 1.92E+OO 8.70E+04 9.92E+04 4.40E+01 1.06E+04 1.21E+04 4.08E+02 1.45E+03 1.65E+03 5.86E-02 1.58E+05 1.81E+05 2.00E+OO 8.52E+04 9.72E+04 4.80E+01 9.86E+03 1.12E+04 4.32E+02 1.31E+03 1.49E+03 6.69E-02 1.58E+05 1.80E+05 2.50E+OO 7.62E+04 8.69E+04 5.20E+01 9.25E+03 1.05E+04 4.56E+02 1.19E+03 1.35E+03 7.53E-02 1.57E+05 1.79E+05 3.00E+OO 6.91E+04 7.88E+04 5.60E+01 8.72E+03 9.94E+03 4.80E+02 1.08E+03 1.23E+03 8.36E-02 1.57E+05 1.79E+05 3.50E+OO 6.34E+04 7.23E+04 6.00E+01 8.27E+03 9.43E+03 5.04E+02 9.73E+02 1.11E+03 1.67E-01 1.52E+05 1.73E+05 4.00E+OO 5.88E+04 6.70E+04 6.40E+01 7.87E+03 8.97E+03 5.28E+02 8.81 E+02 1.00E+03 2.50E-01 1.47E+05 1.68E+05 4.50E+OO 5.49E+04 6.26E+04 6.80E+01 7.52E+03 8.58E+03 5.52E+02 7.99E+02 9.10E+02 3.34E-01 1.42E+05 1.62E+05 5.00E+OO 5.16E+04 5.89E+04 7.20E+01 7.21 E+03 8.22E+03 5.76E+02 7.23E+02 8.25E+02 4.17E-01 1.38E+05 1.57E+05 5.50E+OO 4.88E+04 5.56E+04 7.60E+01 6.93E+03 7.90E+03 6.00E+02 6.55E+02 7.47E+02 5.00E-01 1.34E+05 1.53E+05 6.00E+OO 4.63E+04 5.28E+04 8.00E+01 6.68E+03 7.62E+03 6.24E+02 5.94E+02 6.77E+02 5.84E-01 1.30E+05 1.48E+05 6.50E+OO 4.42E+04 5.04E+04 8.40E+01 6.45E+03 7.36E+03 6.48E+02 5.38E+02 6.13E+02 6.67E-01 1.26E+05 1.44E+05 7.00E+OO 4.22E+04 4.81E+04 8.80E+01 6.25E+03 7.12E+03 6.72E+02 4.87E+02 5.55E+02 7.50E-01 1.23E+05 1.40E+05 7.50E+OO 4.05E+04 4.61E+04 9.20E+01 6.06E+03 6.91E+03 6.96E+02 4.41E+02 5.03E+02 8.34E-01 1.19E+05 1.36E+05 8.00E+OO 3.89E+04 4.43E+04 9.60E+01 5.88E+03 6.70E+03 7.20E+02 4.00E+02 4.56E+02 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Ranqe Radiation Monitor (CHRRM) Response to Drywell Airborne Activitl

§. Calo.. Fo" Containment High Range Radlatlon Monitor Calo No. 2004-07060 areie L.un.iy"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 20 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date -Pl'Oj. No 12400-045 Equip. No. Approved by Date 5.4 EAL Dose Rates The CHRRM dose rates have been calculated for four dose sources as a function of time in Tables 5.3-1, 5.3-2, 5.3-3, and 5.3-4: a. Table 5.3-1, Reactor Water Noble Gas (100,000 µCi/sec Off-Gas Release Rate) b. Table 5.3-2, Reactor Water Iodine (DEl-131 = 1 µCi/gm) c. Table 5.3-3, Gap Activity Noble Gas (2.51 E+07 Ci) d. Table 5.3-4, Gap Activity Iodine (2.50E+07 Ci, DEl-131 = 3.32E+04 µCi/gm) These dose rates (a-d above) are combined with multipliers to produce dose rates that correspond to the BWR Emergency Action Levels 3 and 4 in Table 5-F-2 of NEI 99-01 [Ref. 7.1 O]. The multipliers for each EAL are developed below and summarized in Table 5.4-1. The CHRRM dose rates as a function of time are plotted in Figure 5.4-1 below. The tabular data is contained in Attachment C. Table 5.4-1; Multipliers For EAL Cases [Ref. 7.10] Barrier Condition N.G. N.G.

Iodine Iodine Source Multiplier Source Multiplier RCS RW, Normal Operation Table 5.3-1 2.97E-2 Table 5.3-2 4.11 E-5 DEl-131 = 4.11 E-5 µCi/gm Off-gas = 2967 µCi/sec (30 min delay) RCS RW, Design Basis Table 5.3-1 1.00E+O Table 5.3-2 2.00E-1 DEl-131 = 0.2 µCi/gm Off-qas = 100,000 J..LCi/sec (30 min delay) RCS RW, Upper Limit Table 5.3-1 3.00E+O Table 5.3-2 2.00E+O DEl-131 = 2.0 µCi/gm Off-qas = 300,000 uCi/sec (30 min delay) Fuel Clad Gap, DEl-131= 300 J..LCi/qm (2004 MWt) Table 5.3-3 9.04E-3 Table 5.3-4 9.04E-3 Fuel Clad Gap, 5% damaqed (2004 MWt) Table 5.3-3 5.00E-2 Table 5.3-4 5.00E-2 Fuel Clad Gap, 10% damaQed (2004 MWt) Table 5.3-3 1.00E-1 Table 5.3-4 1.00E-1 Fuel Clad Gap, 20% damaQed (2004 MWt) Table 5.3-3 2.00E-1 Table 5.3-4 2.00E-1 Fuel Clad Gap, 100% damaQed (2004 MWt) Table 5.3-3 1.00E+O Table 5.3-4 1.00E+O RCS Barrier Breach, Reactor Water Release; Normal Operation Sources The normal operation reactor water release is based on normal operating conditions.

It has a DEl-131 of 4.11 E-05 µCi/gm for the normal reactor water iodine mix, and an off-gas release rate of 2967 µCi/sec (after 30 minute delay). The multipliers for this case are (4.11 E-5/1) for the radio-iodines and (2967/100,000) for the noble gas. RCS Barrier Breach. Reactor Water Release; Design Basis Sources The design basis reactor water release is based on a DEl-131 of 0.2 µCi/gm for the normal reactor water iodine mix, and an off-gas release rate of 100,000 µCi/sec (after 30 minute delay). The multipliers for this case are (0.2/1) for the radio-iodines and (100,000/100,000) for the noble gas. RCS Barrier Breach. Reactor Water Release; Upper Limit Sources The upper limit reactor water release is based on a DEl-131 of 2.0 µCi/gm for the normal reactor water mix, and an off-gas release rate of 300,000 µCi/sec (after 30 minute delay). The multipliers for this case are (2.0/1) for the radio-iodines and (300,000/100,000) for the noble gas. File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drvwell Airborne Activitv'

§ Calos. Fo" Containment High Range Radiation Monlto* Calo No. 2004-07060 art!le Lun*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 jDate X j Safety Related j j Non-Safety Related Page 21 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Fuel Clad Breach, Gap Activity; DEl-131 = 300µCi/gm This case is based on a DEl-131 of 300 µCi/gm for the gap activity iodine mix, which yields a multiplier of 300/3.32E4.

The noble gas quantity is based on the same DEl-131 ratio since the noble gas gap release fraction is the same as the iodine release fraction.

The multiplier for this case is 300/3.32E4

= 9.04E-3. Fuel Clad Breach, Gap Activity; 5% Clad Damage This case is based on 5% of the gap activity.

The multiplier for this case is 0.05. Fuel Clad Breach, Gap Activity:

10% Clad damage This case is based on 10% of the gap activity.

The multiplier for this case is 0.10. Fuel Clad Breach. Gap Activity:

20% Clad damage This case is based on 20% of the gap activity.

The multiplier for this case is 0.20. Fuel Clad Breach. Gap Activity:

100% Clad Damage This case is based on 100% of the gap activity.

The multiplier for this case is 1.0. File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04-194, "Containment HiQh RanQe Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" ,.;.: L..ui.-.*y

c Client NSP Project Monticello NGP Proj. No 12400-045 I g 1.0E+06 1.0E+05 1.0E+04 8l 1.0E+03 c 0 a. ill 0:: 2: 1.0E+02 0:: 0:: :i: (.) 1.0E+01 1.0E+OO 1.0E-01 1.0E-02 File GQ308-2.DOC Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060 (CHRRM) Response To Drywell Airborne Activity Rev. 2 !Date X I Safety Related I I Non-Safety Related Page 22 of 24 Prepared by Date Reviewed by Date Equip. No. Approved by Date CHRRM Response To Drywall Airborne Radioactivity Gap Activity; 100% Gap Activity, 20% , , Gap Activity; 10% / / ,, / / / -Gap Activity; 05% ----,,' // /,, -Gap Activity; 300 µCi/gm DEl-131 RW; 2.0 µCi/gm DEl-131, 300,000 µCi/sec , , , RW; 0.2 µCi/gm DEl-131, 100,000 µCi/sec / / --v / / /, RW; 4.11E-511Ci/gm DEl-131, 2967 µCi/sec ---!.. 6.<::/ ,,,,, /// v ---J , --/ .., v r--. r--...........

/ v V/ ,,"' ------r-.... r--. ' -/ 1---. r-_ , , , ----l/ ' / / / ----........ // "/ ,...._ r--. ..... I"'--... ' '" I'\ '"--, -/ " / / ,...__ ""'" --// r-...... t--!'--.. --..... , ........ / ,...__ ...........

v r-...... t--':-... -/ , ........ ....__ / .........

.. --':-... ...............

1.0E-01 1.0E+OO 1.0E+01 1.0E+02 1.0E+03 Time After Release (hrs) Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv' Caloo. Fo" Containment High Range Radiation Mon;tor Colo No. 2004-07060 S.10llr!!!'le L...un*y"* (CHRRM) Response To Drywell Airborne Activity Rev. 2 I Date X I Safety Related I I Non-Safety Related Page 23 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date 6

SUMMARY

AND CONCLUSIONS The CHRRM response to in-containment releases corresponding to a breach of the reactor coolant boundary and clad damage have been calculated and plotted. The tabular data and full size plots are contained in Attachment C. Note that the reactor water dose rates were not added to the clad damage dose rates because they are a small fraction of the clad damage dose rates, and not including them in the detector response is conservative.

7 REFERENCES 7.1 RUNT-PC,"A Computer Program For Modeling Radionuclide Buildup And Decay For General Purpose Isotope Shielding Analysis Using Gaussian Quadrature Integration Of Point And Line Kernel Dose Rate Equations For Predefined And Ad Hoc Source And Shield Geometries," S&L Program RUNT 03.7.705-1.1/0 7.2 Xcel Energy Design Information Transmittal (DIT) No. 933 (EC 13638),

Subject:

Design inputs for revision to S&L calculation 2004-07060 Rev 1 (MNGP calculation 04-194 Rev 1) to update calculation for EPU source term, Included as Attachment B to this calculation)

7.3 Drawing

NF-36212 (C-70), "Radiation Shielding Requirements, Reactor Bldg. Section B-B," Rev. 2 7.4 Drawing NF-36169 (C-374), "Reactor Bldg. Drywall Vessel Fdn. Sht. 1, Rev. 2 7.5 Drawing NF-36685 (E-333), "Reactor Bldg. Drywell Conduits and Trays Above El 933," Rev. G 7.6 Drawing NF-36291 (C-393), "Reactor Building Drywell Int. Framing Plan, Sht. 1, Rev. A 7.7 Principals of Radiation Protection, Morgan and Turner, Reprint 1973, Krieger Publishing Company (p132) 7.8 MNGP USAR, Table 14.7-19, Rev. 27 7.9 US NRC Reg. Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,

July 2000 7.10 "Methodology for Development of Emergency Action Levels,

NEI 99-01 (NUMARC/NESP-007), Nuclear Energy Institute, September 2002. 7.11 Nuclides and Isotopes (Chart Of The Nuclides), 14 1 h Edition, 1989, General Electric Company 7.12 Sargent & Lundy (S&L) calculation 2004-07600, "Alternative Source Term -Core Isotopic Inventory," Rev. 0, 11/08/04 7.13 Monticello NGP Technical Specifications, Through Amendment 164 7.14 Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion,

EPA-520/1-88-020, September 1988 7.15 Task Report T0802, "Core Source Term," for Nuclear Management Company, LLC (NMC), Monticello Nuclear Generating Plant Extended Power Uprate, GE-NE-0000-0064-6767-TR-RO, July 2007, GE Energy, Nuclear File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04 -194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activitv' Cales. For: Containment High Range Radiation Monitor Cale No. 2004-07060 (CHRRM) Response To Drywell Airborne Activity Rev. 2 !Date X I Safety Related I I Non-Safety Related Page 24 of 24 Client NSP Prepared by Date Project Monticello NGP Reviewed by Date Proj. No 12400-045 Equip. No. Approved by Date Attachments Attachment A, Summary of Computer Input and Output Files ......................................................

A 1-A 1 Attachment 8, Design Information Transmittal (DIT) No. 933 (Reference 7.2) .............................

81-89 Attachment C, Tabular Data And Plots For CHRRM Dose Rate vs Time ......................................

C1-C7 Attachment D, Computer Output, Case 1 ....................

................................................................

D1-D47 Attachment E, Computer Output, Case 2 .....................................................................................

E1-E47 Attachment F, Computer Output, Case 3 ......................................................................................

F1-F47 Attachment G, Computer Output, Case 4 ........................

.........................................................

G1-G47 File GQ308-2.DOC Form GQ-3.08.1 Rev.2 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" 'C' .s::. 1.0E+06 1.0E+05 1.0E+04 ';' 1.0E+03 rn c: 0 c.. rn &! 2: 1.0E+02 a::: a::: :c (..) 1.0E+01 1.0E+OO 1.0E-01 1.0E-02 -CHRRM Response To Drywell Airborne Radioactivity Containment Barrier Cale.: 2004-07060 Rev.: 2 Attachment C Page C1 of C7 r Potential Loss Gao Activitv:

100% v , Gap Activity, 20% I Fuel Clad I , / Gap Activity; 10% // Barrier Loss / / / Gao Activitv:

05% / / / r--,,v // /,, Gap Activity; 300 >tCi/gm DEl-131 I -RW; 2.0 µCi/gm DEl-131, 300,000 µCi/sec / , t'(VV; U.£ µv11gm Ut:J-ljJ, 1UU,uuu / _,, / / RW; 4.11 E-5 µCi/gm DEl-131, 2967 µC1 ec RCS Barrier ----v v I// 7 ,.....--r-----" / "'V// / Loss -k _v r--. ---, -...... / -.........

/ 17"1? / ---r-........ v // v 1,/' -......._

-....... -I---. "!'.. r-----r--. r-,_ .., , , , ---/ --.........

' / / I/ -----...... ........ !'.. // '/ ......_ ...... r---..... " !'.. I\ r--. "'-" -/ -.........

'" / / -----r--// -r-'r--" -----........ / .............

........ I/ r-'r--""-;-.. -/ "---/ ' ' ---.......

K 1.0E-01 1.0E+OO 1.0E+01 1.0E+02 1.0E+03 Time After Release (hrs)

I CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 3 Dose Rates Case 3 Dose Rates Time Gap Noble Gas (hrs) (rad-air/hr) (R/hr) 2.78E-04 6.B6E+04 7.82E+04 1.67E-03 6.82E+04 7.7BE+04 3.06E-03 6.79E+04 7.75E+04 4.44E-03 6.76E+04 7.71E+04 5.B3E-03 6.73E+04 7.68E+04 7.22E-03 6.70E+04 7.64E+04 8.61E-03 6.67E+04 7.61E+04 1.69E-02 6.50E+04 7.42E+04 2.53E-02 6.35E+04 7.24E+04 3.36E-02 6.21E+04 7.08E+04 4.19E-02 6.08E+04 6.94E+04 5.03E-02 5.97E+04 6.80E+04 5.86E-02 5.86E+04 6.68E+04 6.69E-02 5.76E+04 6.57E+04 7.53E-02 5.67E+04 6.47E+04 8.36E-02 5.59E+04 6.37E+04 1.67E-01 5.02E+04 5.73E+04 2.50E-01 4.70E+04 5.36E+04 3.34E-01 4.47E+04 5.10E+04 4.17E-01 4.27E+04 4.87E+04 5.00E-01 4.09E+04 4.66E+04 5.84E-01 3.91E+04 4.46E+04 6.67E-01 3.75E+04 4.27E+04 7.50E-01 3.59E+04 4.09E+04 8.34E-01 3.44E+04 3.92E+04 0 17<'-n1 3.30E+04 3.77E+04 1.00E+OO 3.17E+04 3.61E+04 ov 3.0SE+04 3.47E+04 1.17E+OO 2.93E+04 3.34E+04 1.25E+OO 2.B2E+04 3.22E+04 1.33E+OO 2.72E+04 3.10E+04 1.42E+OO 2.62E+04 2.99E+04 1.SOE+OO 2.53E+04 2.89E+04 1.SBE+OO 2.45E+04 2.79E+04 1.67E+OO 2.37E+04 2.70E+04 1.75E+OO 2.30E+04 2.62E+04 1.B3E+DO 2.23E+04 2.54E+04 1.92E+DO 2.16E+D4 2.46E+04 2.DDE+OO 2.10E+04 2.39E+04 2.5DE+DO 1.79E+D4 2.05E+04 3.0DE+OO 1.57E+04 1.79E+04 3.5DE+OO 1.40E+04 1.59E+04 4.0DE+DO 1.25E+04 1.43E+04 4.SOE+DO 1.14E+04 1.30E+04 5.DDE+OO 1.D4E+04 1.18E+04 5.5DE+OO 9.53E+03 1.D9E+04 6.DOE+OO 8.7BE+03 1.0DE+04 6.SOE+OO 8.13E+03 9.27E+03 Containment High Range Radiation Monitor CHRRM Response To Drywell Airborne Radioactivity Containment Barrier Potential Loss Gap Release Attachment C Page C2 of C7 !Fuel Clad Barrier Case 4 Dose Rates Full Gap Activity I 20% Gap Activity I 1 0% Gap Activity 5% Gap Activity I DEl131=300

µCi/gm I . DEl131 *v DEl131 DEl131 Case 4 Dose Rates NG 3.32E4 NG 6.64E3 NG 3.32E3 NG 1.66E+3 NG DEl131 Time Gap Iodine 2.51E7Ci µCi/g Total 5.02E6 Ci µCi/g Total I 2.51E6 Ci µCi/g Total 1.26E6 Ci µCi/g Total 2.27E5 Ci 300 µCii!Jll Total (hrs) (rad-air/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) I (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) II (R/hr) 1.62E+05 1.B5E+05 7.82E+04 1.85E+05 2.63E+05 1.56E+04 3.69E+04 5.26E+04 7.B2E+03 1.85E+04 2.63E+04 3.91E+03 9.24E+03 1.31E+04 7.06E+02 1.67E+OJ .::: .....

1.67E-03 1.62E+05 1.B5E+05 7.78E+04 1.85E+05 2.62E+05 1.56E+04 3.69E+04 5.25E+04 7.78E+03 1.B5E+04 2.62E+04 3.89E+03 9.23E+03 1.31E+04 7.03E+02 1.67E+03 2.37E+03 3.06E-03 1.62E+05 1.B4E+05 7.75E+04 1.84E+05 2.62E+05 1.55E+04 3.69E+04 5.24E+04 7.75E+03 1.84E+04 2.62E+04 3.87E+03 9.22E+03 1.31E+04 7.00E+02 1.67E+03 2.37E+03 4.44E-03 1.62E+05 1.B4E+05 7.71E+04 1.84E+05 2.61E+05 1.54E+04 3.69E+04 5.23E+04 7.71E+03 1.84E+04 2.61E+04 3.85E+03 9.22E+03 1.31E+04 6.97E+02 1.67E+03 2.36E+03 5.83E-03 1.62E+05 1.84E+05 7.6BE+04 1.84E+05 2.61E+05 1.54E+04 3.69E+04 5.22E+04 7.6BE+03 1.84E+04 2.61E+04 3.84E+03 9.21E+03 1.31E+04 6.94E+02 1.67E+03 2.36E+03 7.22E-03 1.62E+05 1.84E+05 7.64E+04 1.84E+05 2.61E+05 1.53E+04 3.69E+04 5.21E+04 7.64E+03 1.84E+04 2.61E+04 3.82E+03 9.21E+03 1.30E+04 6.90E+02 1.67E+03 2.36E+03 8.61E-03 1.62E+05 1.84E+05 7.61E+04 1.84E+05 2.60E+05 1.52E+04 3.68E+04 5.20E+04 7.61E+03 1.84E+04 2.60E+04 3.80E+03 9.21E+03 1.30E+04 6.87E+02 1.66E+03 2.35E+03 1.69E-02 1.61E+05 1.83E+05 7.42E+04 1.83E+05 2.58E+05 1.48E+04 3.67E+04 5.15E+04 7.42E+03 1.83E+04 2.58E+04 3.71E+03 9.17E+03 1.29E+04 6.70E+02 1.66E+03 2.33E+03 2.53E-02 1.60E+05 1.83E+05 7.24E+04 1.83E+05 2.55E+05 1.45E+04 3.66E+04 5.11E+04 7.24E+03 1.83E+04 2.55E+04 3.62E+03 9.14E+03 1.28E+04 6.54E+02 1.65E+03 2.31E+03 3.36E-02 1.60E+05 1.82E+05 7.08E+04 1.82E+05 2.53E+05 1.42E+04 3.65E+04 5.06E+04 7.08E+03 1.82E+04 2.53E+04 3.54E+03 9.12E+03 1.27E+04 6.40E+02 1.65E+03 2.29E+03 4.19E-02 1.59E+05 1.82E+05 6.94E+04 1.82E+05 2.51E+05 1.39E+04 3.63E+04 5.02E+04 6.94E+03 1.82E+04 2.51E+04 3.47E+03 9.08E+03 1.25E+04 6.27E+02 1.64E+03 2.27E+03 5.03E-02 1.59E+05 1.81E+05 6.80E+04 1.81E+05 2.49E+OS 1.36E+04 3.62E+04 4.98E+04 6.80E+03 1.81E+04 2.49E+04 3.40E+03 9.0SE+03 1.25E+04 6.15E+02 1.64E+03 2.25E+03 5.86E-02 1.58E+05 1.81E+05 6.68E+04 1.81E+05 2.47E+05 1.34E+04 3.61E+04 4.95E+04 6.68E+03 1.81E+04 2.47E+04 3.34E+03 9.03E+03 1.24E+04 6.04E+02 1.63E+03 2.23E+03 6.69E-02 1.58E+05 1.80E+05 6.57E+04 1.80E+05 2.46E+05 1.31E+04 3.60E+04 4.91E+04 6.57E+03 1.80E+04 2.46E+04 3.28E+03 9.00E+03 1.23E+04 5.94E+02 1.63E+03 2.22E+03 7.53E-02 1.57E+05 1.79E+05 6.47E+04 1.79E+05 2.44E+05 1.29E+04 3.58E+04 4.88E+04 6.47E+03 1.79E+04 2.44E+04 3.23E+03 8.96E+03 1.22E+04 5.84E+02 1.62E+03 2.20E+03 8.36E-02 1.57E+05 1.79E+05 6.37E+04 1.79E+05 2.42E+05 1.27E+04 3.57E+04 4.85E+04 6.37E+03 1.79E+04 2.42E+04 3.19E+03 8.93E+03 1.21E+04 5.76E+02 1.61E+03 2.19E+03 1.67E-01 1.52E+05 1.73E+05 5.73E+04 1.73E+05 2.30E+05 1.15E+04 3.46E+04 4.61E+04 5.73E+03 1.73E+04 2.30E+04 2.86E+03 8.65E+03 1.15E+04 5.18E+02 1.56E+03 2.08E+03 2.SOE-01 1.47E+05 1.68E+05 5.36E+04 1.68E+05 2.21E+05 1.07E+04 3.35E+04 4.42E+04 5.36E+03 1.68E+04 2.21E+04 2.68E+03 8.38E+03 1.11E+04 4.85E+02 1.51E+03 2.00E+03 3.34E-01 1.42E+05 1.62E+05 5.10E+04 1.62E+05 2.13E+05 1.02E+04 3.25E+04 4.26E+04 5.10E+03 1.62E+04 2.13E+04 2.55E+03 8.11E+03 1.07E+04 4.61E+02 1.47E+03 1.93E+03 4.17E-01 1.38E+05 1.57E+05 4.87E+04 1.57E+05 2.06E+05 9.74E+03 3.15E+04 4.12E+04 4.87E+03 1.57E+04 2.06E+04 2.44E+03 7.87E+03 1.03E+04 4.40E+02 1.42E+03 1.86E+03 5.00E-01 1.34E+05 1.53E+05 4.66E+04 1.53E+05 1.99E+05 9.32E+03 3.05E+04 3.98E+04 4.66E+03 1.53E+04 1.99E+04 2.33E+03 7.63E+03 9.96E+03 4.21E+02 1.38E+03 1.80E+03 5.84E-01 1.30E+OS 1.48E+05 4.46E+04 1.48E+05 1.93E+05 8.93E+03 2.96E+04 3.85E+04 4.46E+03 1.48E+04 1.93E+04 2.23E+03 7.41E+03 9.64E+03 4.03E+02 1.34E+03 1.74E+03 6.67E-01 1.26E+05 1.44E+05 4.27E+04 1.44E+05 1.87E+05 8.55E+03 2.88E+04 3.73E+04 4.27E+03 1.44E+04 1.87E+04 2.14E+03 7.19E+03 9.33E+03 3.86E+02 1.30E+03 1.69E+03 7.SOE-01 1.23E+05 1.40E+05 4.09E+04 1.40E+05 1.81E+05 8.19E+03 2.79E+04 3.61E+04 4.09E+03 1.40E+04 1.81E+04 2.0SE+03 6.98E+03 9.03E+03 3.70E+02 1.26E+03 1.63E+03 8.34E-01 1.19E+05 1.36E+05 3.92E+04 1.36E+05 1.75E+05 7.85E+03 2.72E+04 3.50E+04 3.92E+03 1.36E+04 1.75E+04 1.96E+03 6.79E+03 8.75E+03 3.55E+02 1.23E+03 1.58E+03 n n< 1.16E+05 1.32E+05 3.77E+04 1.32E+05 1.70E+05 7.53E+03 2.64E+04 3.39E+04 3.77E+03 1.32E+04 1.70E+04 1.88E+03 6.60E+03 8.48E+03 3.40E+02 1.19E+O 1.00E+OO 1.13E+05 1.29E+05 3.61 E+04 1.29E+OS 1.65E+05 7.23E+03 2.57E+O 3.30E+04 3.61E+03 1.29E+04 1.65E+04 1.81E+03 6.43E+03 8.24E+03 3.27E+02 1.49E+03 1.uc +uu 1.10E+05 1.25E+05 3.47E+04 1.25E+05 1.60E+05 6.95E+03 2.50E+O v. 3.47E+03 1.25E+04 1.60E+04 1.74E+03 6.26E+03 8.00E+03 3.14E+02 1.13E+Oo -1."1"'1-'.VJ 1.17E+OO 1.07E+05 1.22E+05 3.34E+04 1.22E+05 1.55E+05 6.68E+03 2.44E+04 3.11E+04 3.34E+03 1.22E+04 1.55E+04 1.67E+03 6.10E+03 7.77E+03 3.02E+02 1.10E+03 1.40E+03 1.25E+OO 1.04E+05 1.19E+05 3.22E+04 1.19E+05 1.51E+05 6.43E+03 2.38E+04 3.02E+04 3.22E+03 1.19E+04 1.51E+04 1.61E+03 5.95E+03 7.56E+03 2.91E+02 1.08E+03 1.37E+03 1.33E+OO 1.02E+05 1.16E+05 3.10E+04 1.16E+05 1.47E+05 6.20E+03 2.32E+04 2.94E+04 3.10E+03 1.16E+04 1.47E+04 1.55E+03 5.BOE+03 7.35E+03 2.BOE+02 1.0SE+03 1.33E+03 1.42E+OO 9.94E+04 1.13E+05 2.99E+04 1.13E+05 1.43E+05 5.9BE+03 2.27E+04 2.B6E+04 2.99E+03 1.13E+04 1.43E+04 1.49E+03 5.67E+03 7.16E+03 2.70E+02 1.02E+03 1.29E+03 1.SOE+OO 9.71E+04 1.11E+05 2.89E+04 1.11E+05 1.40E+05 5.78E+03 2.21E+04 2.79E+04 2.89E+03 1.11E+04 1.40E+04 1.44E+03 5.53E+03 6.98E+03 2.61E+02 1.00E+03 1.26E+03 1.58E+OO 9.49E+04 1.0BE+OS 2.79E+04 1.08E+05 1.36E+05 5.58E+03 2.16E+04 2.72E+04 2.79E+03 1.08E+04 1.36E+04 1.40E+03 5.41E+03 6.81E+03 2.52E+02 9.77E+02 1.23E+03 1.67E+OO 9.2BE+04 1.06E+05 2.70E+04 1.06E+05 1.33E+05 5.40E+03 2.12E+04 2.66E+04 2.70E+03 1.06E+04 1.33E+04 1.35E+03 5.29E+03 6.64E+03 2.44E+02 9.56E+02 1.20E+03 1.75E+OO 9.07E+04 1.03E+05 2.62E+04 1.03E+05 1.3DE+D5 5.24E+D3 2.07E+D4 2.59E+D4 2.62E+D3 1.D3E+04 1.3DE+D4 1.31E+D3 5.17E+D3 6.48E+03 2.37E+02 9.35E+02 1.17E+03 1.B3E+OD 8.BBE+04 1.01E+05 2.54E+D4 1.01E+05 1.27E+05 5.08E+03 2.03E+04 2.53E+D4 2.54E+D3 1.01E+04 1.27E+04 1.27E+03 5.06E+03 6.33E+D3 2.29E+02 9.15E+D2 1.14E+03 1.92E+DD B.70E+D4 9.92E+D4 2.46E+04 9.92E+D4 1.24E+D5 4.93E+03 1.98E+04 2.48E+D4 2.46E+03 9.92E+03 1.24E+D4 1.23E+03 4.96E+D3 6.19E+03 2.23E+02 8.96E+02 1.12E+03 2.DDE+OO 8.52E+04 9.72E+04 2.39E+D4 9.72E+04 1.21E+D5 4.79E+D3 1.94E+04 2.42E+D4 2.39E+D3 9.72E+03 1.21E+04 1.20E+03 4.86E+03 6.06E+D3 2.16E+02 8.78E+02 1.09E+03 2.50E+OO 7.62E+04 8.69E+04 2.05E+04 B.69E+04 1.07E+05 4.09E+03 1.74E+04 2.15E+D4 2.DSE+D3 8.69E+03 1.07E+04 1.02E+03 4.34E+03 5.37E+03 1.85E+02 7.85E+02 9.70E+02 3.0DE+OO 6.91E+04 7.88E+04 1.79E+D4 7.88E+04 9.66E+D4 3.58E+D3 1.58E+04 1.93E+D4 1.79E+D3 7.B8E+03 9.66E+03 8.95E+02 3.94E+03 4.83E+D3 1.62E+02 7.12E+02 8.73E+02 3.50E+OO 6.34E+04 7.23E+04 1.59E+04 7.23E+04 8.B2E+04 3.18E+03 1.45E+04 1.76E+D4 1.59E+D3 7.23E+D3 8.B2E+03 7.95E+02 3.61E+D3 4.41 E+D3 1.44E+02 6.53E+02 7.97E+02 4.00E+OO 5.B8E+04 6.7DE+04 1.43E+04 6.70E+04 B.13E+04 2.86E+03 1.34E+04 1.63E+04 1.43E+D3 6.70E+D3 8.13E+03 7.15E+02 3.35E+D3 4.06E+D3 1.29E+02 6.05E+02 7.35E+02 4.5DE+OD 5.49E+04 6.26E+D4 1.30E+04 6.26E+D4 7.56E+04 2.59E+D3 1.25E+04 1.51E+D4 1.3DE+D3 6.26E+D3 7.56E+03 6.48E+02 3.13E+D3 3.78E+03 1.17E+D2 5.66E+02 6.83E+02 5.00E+OD 5.16E+04 5.89E+D4 1.18E+04 5.B9E+04 7.D7E+04 2.37E+03 1.18E+04 1.41E+04 1.1BE+03 5.B9E+D3 7.07E+03 5.92E+02 2.94E+03 3.53E+03 1.07E+D2 5.32E+02 6.39E+D2 5.5DE+DD 4.BBE+04 5.56E+04 1.09E+D4 5.56E+04 6.65E+D4 2.17E+D3 1.11E+04 1.33E+D4 1.09E+D3 5.56E+D3 6.65E+D3 5.43E+02 2.7BE+03 3.33E+03 9.81E+D1 5.03E+02 6.01E+D2 6.DDE+DO 4.63E+04 5.28E+04 1.00E+D4 5.28E+04 6.28E+D4 2.DDE+D3 1.06E+04 1.26E+D4 1.DDE+D3 5.2BE+D3 6.28E+D3 5.01E+02 2.64E+03 3.14E+D3 9.05E+D1 4.77E+02 5.6BE+D2 6.5DE+DO 4.42E+04 5.04E+04 9.27E+03 5.04E+04 5.96E+D4 1.B5E+D3 1.01E+04 1.19E+04 9.27E+02 5.04E+03 5.96E+D3 4.63E+02 2.52E+D3 2.98E+03 8.37E+D1 4.55E+02 5.39E+D2 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 3 Dose Rates Case 3 Dose Rates Time Gap Noble Gas (hrs) (rad-air/hr) (R/hr) 7.00E+OO 7.55E+03 8.61E+03 7.SOE+OO 7.04E+03 8.03E+03 8.00E+OO 6.59E+03 7.52E+03 1.00E+01 5.23E+03 5.96E+03 1.20E+01 4.34E+03 4.95E+03 1.40E+01 3.76E+03 4.29E+03 1.60E+01 3.36E+03 3.83E+03 1.80E+D1 3.0BE+03 3.51E+03 2.00E+01 2.88E+03 3.28E+03 2.20E+01 2.72E+03 3.10E+03 2.40E+01 2.60E+03 2.96E+03 2.80E+01 2.42E+03 2.76E+03 3.20E+01 2.29E+03 2.61E+03 3.60E+01 2.18E+03 2.49E+03 4.00E+01 2.10E+03 2.39E+D3 4.40E+01 2.02E+03 2.31E+03 4.80E+01 1.96E+03 2.23E+03 5.20E+01 1.SOE+03 2.16E+03 5.60E+01 1.84E+03 2.10E+03 6.00E+01 1.79E+03 2.04E+03 6.40E+01 1.74E+03 1.99E+03 6.BOE+01 1.70E+03 1.94E+03 7.20E+01 1.66E+03 1.89E+03 7.60E+01 1.61E+03 1.84E+03 8.00E+01 1.57E+03 1.79E+03 8.40E+01 1.54E+03 1.75E+03 8.80E+01 1.50E+03 1.71E+03 9.20E+01 1.46E+03 1.67E+03 9.60E+01 1.43E+03 1.63E+03 1.20E+02 1.23E+03 1.41E+03 1.44E+02 1.07E+03 1.22E+03 1.68E+02 9.25E+02 1.05E+03 1.92E+02 8.01E+02 9.13E+02 2.16E+02 6.94E+02 7.91E+02 2.40E+02 6.01E+02 6.85E+02 2.64E+02 5.21E+02 5.94E+02 2.88E+02 4.51E+02 5.14E+02 3.12E+02 3.91E+02 4.46E+02 3.36E+02 3.39E+02 3.87E+02 3.60E+02 2.94E+02 3.35E+02 3.84E+02 2.55E+02 2.91E+02 4.08E+02 2.21E+02 2.52E+02 4.32E+02 1.92E+02 2.19E+02 4.56E+02 1.67E+02 1.90E+02 4.80E+02 1.45E+02 1.65E+02 5.04E+02 1.26E+02 1.43E+02 5.28E+02 1.09E+02 1.24E+02 5.52E+02 9.47E+01 1.08E+02 Case 4 Dose Rates Case 4 Dose Rates Time Gap Iodine (hrs) (rad-air/hr) (Rlhr) 7.00E+OO 4.22E+04 4.81E+04 7.SOE+OO 4.05E+04 4.61E+04 8.00E+OO 3.89E+04 4.43E+04 1.00E+01 3.37E+04 3.84E+04 1.2DE+01 2.98E+04 3.39E+04 1.40E+01 2.67E+04 3.04E+04 1.60E+01 2.42E+04 2.76E+04 1.80E+01 2.22E+04 2.53E+04 2.00E+01 2.04E+04 2.33E+04 2.20E+01 1.89E+04 2.16E+04 2.40E+01 1.76E+04 2.01E+04 2.80E+01 1.55E+04 1.77E+04 3.20E+01 1.3BE+04 1.58E+04 3.60E+D1 1.25E+04 1.43E+04 4.00E+01 1.15E+04 1.31E+04 4.40E+01 1.06E+D4 1.21E+04 4.80E+01 9.86E+03 1.12E+04 5.20E+01 9.25E+03 1.05E+04 5.60E+01 8.72E+03 9.94E+03 6.00E+01 8.27E+03 9.43E+03 6.40E+01 7.87E+03 B.97E+03 6.BOE+01 7.52E+03 B.5BE+03 7.20E+01 7.21E+03 B.22E+03 7.60E+01 6.93E+03 7.90E+03 8.00E+01 6.68E+03 7.62E+03 8.40E+01 6.45E+03 7.36E+03 8.80E+01 6.25E+03 7.12E+03 9.20E+01 6.06E+03 6.91E+03 9.60E+01 5.88E+03 6.70E+03 1.20E+02 5.05E+03 5.76E+03 1.44E+02 4.45E+03 5.07E+03 1.68E+02 3.98E+03 4.53E+03 1.92E+02 3.57E+03 4.08E+03 2.16E+02 3.22E+03 3.68E+03 2.40E+02 2.91E+03 3.32E+03 2.64E+02 2.63E+03 3.00E+03 2.88E+02 2.38E+03 2.72E+03 3.12E+02 2.16E+03 2.46E+03 3.36E+02 1.95E+03 2.22E+03 3.60E+02 1.77E+03 2.01E+03 3.84E+02 1.60E+03 1.82E+03 4.08E+02 1.45E+03 1.65E+03 4.32E+02 1.31E+03 1.49E+03 4.56E+02 1.19E+03 1.35E+03 4.80E+02 1.08E+03 1.23E+03 5.04E+02 9.73E+02 1.11E+03 5.28E+02 8.81E+02 1.00E+03 5.52E+02 7.99E+02 9.10E+02 Containment High Range Radiation Monitor CHRRM Response To Drywell Airborne Radioactivity Gap Release Full Gap Activity 20% Gap Activity 10% Gap Activity DEl131 DEl131 DEl131 NG 3.32E4 NG 6.64E3 NG 3.32E3 2.51E7Ci µCi/g Total 5.02E6 Ci µCi/g Total 2.51E6 Ci µCi/g Total (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) 8.61E+03 4.81E+04 5.67E+04 1.72E+03 9.62E+03 1.13E+04 8.61E+02 4.81E+03 5.67E+03 8.03E+03 4.61E+04 5.42E+04 1.61E+03 9.22E+03 1.08E+04 8.03E+02 4.61E+03 5.42E+03 7.52E+03 4.43E+04 5.18E+04 1.50E+03 8.86E+03 1.04E+04 7.52E+02 4.43E+03 5.18E+03 5.96E+03 3.84E+04 4.43E+04 1.19E+03 7.67E+03 8.87E+03 5.96E+02 3.84E+03 4.43E+03 4.95E+03 3.39E+04 3.89E+04 9.91E+02 6.79E+03 7.78E+03 4.95E+02 3.39E+03 3.89E+03 4.29E+03 3.04E+04 3.47E+04 8.57E+02 6.09E+03 6.95E+03 4.29E+02 3.04E+03 3.47E+03 3.83E+03 2.76E+04 3.14E+04 7.66E+02 5.52E+03 6.29E+03 3.83E+02 2.76E+03 3.14E+03 3.51E+03 2.53E+04 2.88E+04 7.02E+02 5.05E+03 5.75E+03 3.51E+02 2.53E+03 2.88E+03 3.28E+03 2.33E+04 2.65E+04 6.56E+02 4.65E+03 5.31E+03 3.28E+02 2.33E+03 2.65E+03 3.10E+03 2.16E+04 2.47E+04 6.20E+02 4.31E+03 4.93E+03 3.10E+02 2.16E+03 2.47E+03 2.96E+D3 2.01E+04 2.30E+04 5.93E+02 4.02E+03 4.61E+03 2.96E+02 2.01E+03 2.30E+03 2.76E+03 1.77E+04 2.04E+04 5.51E+02 3.53E+03 4.08E+03 2.76E+02 1.77E+03 2.04E+03 2.61E+03 1.58E+04 1.84E+04 5.22E+02 3.15E+03 3.68E+03 2.61E+02 1.58E+03 1.84E+03 2.49E+03 1.43E+04 1.68E+04 4.98E+02 2.86E+03 3.35E+03 2.49E+02 1.43E+03 1.68E+03 2.39E+03 1.31E+04 1.55E+04 4.78E+02 2.61E+03 3.09E+03 2.39E+02 1.31E+03 1.55E+03 2.31E+03 1.21E+04 1.44E+04 4.61E+02 2.42E+03 2.88E+03 2.31E+D2 1.21E+03 1.44E+03 2.23E+03 1.12E+04 1.35E+04 4.46E+02 2.25E+03 2.69E+03 2.23E+02 1.12E+03 1.35E+03 2.16E+03 1.05E+04 1.27E+04 *4.33E+02 2.11E+03 2.54E+03 2.16E+02 1.05E+03 1.27E+03 2.10E+03 9.94E+03 1.20E+04 4.20E+02 1.99E+03 2.41E+03 2.10E+02 9.94E+02 1.20E+03 2.04E+03 9.43E+03 1.15E+04 4.09E+02 1.89E+03 2.29E+03 2.04E+02 9.43E+02 1.15E+03 1.99E+03 8.97E+03 1.10E+04 3.9BE+02 1.79E+03 2.19E+03 1.99E+02 B.97E+02 1.10E+03 1.94E+03 8.58E+03 1.05E+04 3.B7E+02 1.72E+03 2.10E+03 1.94E+02 8.58E+02 1.05E+03 1.89E+03 8.22E+03 1.01E+04 3.77E+02 1.64E+03 2.02E+03 1.89E+02 8.22E+02 1.01E+03 1.84E+03 7.90E+03 9.74E+03 3.68E+02 1.58E+03 1.95E+03 1.84E+02 7.9DE+02 9.74E+02 1.79E+03 7.62E+03 9.41 E+03 3.59E+02 1.52E+D3 1.88E+03 1.79E+02 7.62E+02 9.41E+02 1.75E+03 7.36E+03 9.11E+03 3.50E+02 1.47E+03 1.82E+03 1.75E+02 7.36E+02 9.11E+02 1.71E+03 7.12E+03 8.83E+03 3.41E+02 1.42E+03 1.77E+03 1.71E+02 7.12E+02 8.83E+02 1.67E+03 6.91E+03 8.57E+03 3.33E+02 1.38E+03 1.71E+D3 1.67E+02 6.91E+02 8.57E+02 1.63E+03 6.70E+03 8.33E+03 3.25E+02 1.34E+03 1.67E+03 1.63E+02 6.70E+02 8.33E+02 1.41 E+03 5.76E+03 7.17E+03 2.81E+02 1.15E+03 1.43E+03 1.41E+02 5.76E+02 7.17E+02 1.22E+03 5.07E+03 6.29E+03 2.44E+02 1.01E+03 1.26E+03 1.22E+02 5.07E+02 6.29E+02 1.05E+03 4.53E+03 5.59E+03 2.11E+02 9.06E+02 1.12E+03 1.05E+02 4.53E+02 5.59E+02 9.13E+02 4.08E+03 4.99E+03 1.83E+02 8.15E+02 9.98E+02 9.13E+01 4.08E+02 4.99E+02 7.91E+02 3.68E+03 4.47E+03 1.58E+02 7.35E+02 8.93E+D2 7.91E+01 3.68E+02 4.47E+02 6.85E+02 3.32E+03 4.01E+03 1.37E+D2 6.64E+02 8.01E+02 6.85E+01 3.32E+02 4.01E+02 5.94E+D2 3.00E+03 3.60E+03 1.19E+02 6.00E+02 7.19E+02 5.94E+01 3.00E+02 3.60E+02 5.14E+02 2.72E+03 3.23E+03 1.03E+02 5.43E+02 6.46E+02 5.14E+01 2.72E+02 3.23E+02 4.46E+02 2.46E+03 2.90E+03 8.92E+01 4.91E+02 5.81E+02 4.46E+01 2.46E+02 2.90E+02 3.87E+02 2.22E+03 2.61E+03 7.73E+01 4.45E+02 5.22E+02 3.87E+01 2.22E+02 2.61E+02 3.35E+02 2.01E+03 2.35E+03 6.70E+01 4.03E+02 4.70E+02 3.35E+01 2.01E+02 2.35E+02 2.91E+02 1.82E+03 2.11E+03 5.81E+01 3.65E+02 4.23E+02 2.91E+01 1.82E+02 2.11E+02 2.52E+02 1.65E+03 1.90E+03 5.04E+01 3.30E+02 3.80E+02 2.52E+01 1.65E+02 1.90E+02 2.19E+02 1.49E+03 1.71E+03 4.38E+01 2.99E+02 3.43E+02 2.19E+01 1.49E+02 1.71E+02 1.90E+02 1.35E+03 1.54E+03 3.80E+01 2.71E+02 3.09E+02 1.90E+01 1.35E+02 1.54E+02 1.65E+02 1.23E+03 1.39E+03 3.30E+01 2.45E+02 2.78E+02 1.65E+01 1.23E+02 1.39E+02 1.43E+02 1.11E+03 1.25E+03 2.86E+01 2.22E+02 2.51E+02 1.43E+01 1.11E+02 1.25E+02 1.24E+02 1.00E+03 1.13E+03 2.49E+01 2.01E+02 2.26E+02 1.24E+01 1.00E+02 1.13E+02 1.08E+02 9.10E+02 1.02E+03 2.16E+01 1.82E+02 2.04E+02 1.08E+01 9.10E+01 1.02E+02 5% Gap Activity DEl131 NG 1.66E+3 1.26E6 Ci i1Ci/g Total (R/hr) (Rlhr) (R/hr) 4.31E+02 2.41E+03 2.84E+03 4.02E+02 2.31E+03 2.71E+03 3.76E+02 2.21E+03 2.59E+03 2.98E+02 1.92E+03 2.22E+03 2.48E+02 1.70E+03 1.94E+03 2.14E+02 1.52E+03 1.74E+03 1.92E+02 1.38E+03 1.57E+03 1.76E+02 1.26E+03 1.44E+03 1.64E+02 1.16E+03 1.33E+03 1.55E+02 1.0BE+03 1.23E+03 1.48E+02 1.00E+03 1.15E+03 1.38E+02 8.83E+02 1.02E+03 1.30E+02 7.88E+02 9.19E+02 1.24E+02 7.14E+02 8.38E+02 1.20E+02 6.53E+02 7.73E+02 1.15E+02 6.04E+02 7.19E+02 1.12E+02 5.62E+02 6.74E+02 1.08E+02 5.27E+02 6.35E+02 1.05E+02 4.97E+02 6.02E+02 1.02E+02 4.71E+02 5.74E+02 9.94E+01 4.49E+02 5.4BE+02 9.68E+01 4.29E+02 5.26E+02 9.44E+01 4.11E+02 5.05E+02 9.20E+01 3.95E+02 4.87E+02 8.97E+01 3.81E+02 4.71E+02 8.75E+01 3.68E+02 4.55E+02 8.53E+01 3.56E+02 4.42E+02 8.34E+01 3.45E+02 4.29E+02 8.14E+01 3.35E+02 4.17E+02 7.03E+01 2.88E+D2 3.58E+02 6.09E+01 2.54E+02 3.15E+02 5.27E+01 2.27E+02 2.79E+02 4.56E+01 2.04E+02 2.49E+02 3.95E+01 1.84E+02 2.23E+02 3.43E+01 1.66E+02 2.0DE+02 2.97E+01 1.50E+02 1.80E+02 2.57E+01 1.36E+02 1.62E+02 2.23E+01 1.23E+02 1.45E+02 1.93E+01 1.11E+02 1.31E+02 1.68E+01 1.01E+02 1.17E+02 1.45E+01 9.12E+01 1.06E+02 1.26E+01 8.25E+01 9.51E+01 1.09E+01 7.47E+01 8.57E+01 9.49E+OO 6.77E+01 7.72E+01 8.24E+OO 6.13E+01 6.95E+01 7.16E+OO 5.55E+01 6.26E+01 6.21E+OO 5.02E+01 5.65E+01 5.40E+OO 4.55E+01 5.09E+01 Attachment C Page C3 ofC7 DEl131=300

µCi/gm NG DEl131 2.27E5 Ci 300 µCi/g Total (R/hr) (R/hr) (R/hr) 7.78E+01 4.35E+02 5.13E+02 7.26E+01 4.17E+02 4.89E+02 6.79E+01 4.00E+02 4.68E+02 5.38E+01 3.47E+02 4.01E+02 4.48E+01 3.07E+02 3.51E+02 3.87E+01 2.75E+02 3.14E+02 3.46E+01 2.49E+02 2.84E+02 3.17E+01 2.28E+02 2.60E+02 2.96E+01 2.10E+02 2.40E+02 2.80E+01 1.95E+02 2.23E+02 2.68E+01 1.81E+02 2.08E+02 2.49E+01 1.59E+02 1.84E+02 2.36E+01 1.42E+02 1.66E+D2 2.25E+01 1.29E+02 1.51E+02 2.16E+01 1.1BE+02 1.40E+02 2.08E+01 1.09E+02 1.30E+02 2.02E+01 1.02E+02 1.22E+02 1.95E+01 9.53E+01 1.15E+02 1.90E+01 8.98E+01 1.09E+02 1.85E+01 8.52E+01 1.04E+02 1.BOE+01 B.11E+01 9.90E+01 1.75E+01 7.75E+01 9.50E+01 1.71E+01 7.43E+01 9.13E+01 1.66E+01 7.14E+01 8.80E+01 1.62E+01 6.88E+01 8.51E+01 1.58E+01 6.65E+01 8.23E+01 1.54E+01 6.44E+01 7.98E+01 1.51E+01 6.24E+01 7.75E+01 1.47E+01 6.06E+01 7.53E+01 1.27E+01 5.20E+01 6.47E+01 1.10E+01 4.59E+01 5.69E+01 9.53E+OO 4.10E+01 5.05E+01 8.25E+OO 3.68E+01 4.51E+01 7.15E+OO 3.32E+01 4.04E+01 6.19E+OO 3.00E+01 3.62E+01 5.36E+OO 2.71E+01 3.25E+01 4.65E+OO 2.45E+01 2.92E+01 4.03E+OO 2.22E+01 2.62E+01 3.49E+OO 2.01E+01 2.36E+01 3.03E+OO 1.82E+01 2.12E+01 2.63E+OO 1.65E+01 1.91E+01 2.28E+OO 1.49E+01 1.72E+01 1.98E+OO 1.35E+01 1.55E+01 1.72E+OO 1.22E+01 1.39E+01 1.49E+OO 1.11E+01 1.26E+01 1.29E+OO 1.00E+01 1.13E+01 1.12E+OO 9.08E+OO 1.02E+01 9.76E-01 8.23E+OO 9.20E+OO CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 3 Dose Rates Case 3 Dose Rates Time Gap Noble Gas (hrs) (rad-air/hr) (R/hr) 5.76E+02 8.23E+01 9.39E+01 6.00E+02 7.16E+01 8.16E+01 6.24E+02 6.23E+01 7.10E+01 6.48E+02 5.42E+01 6.18E+01 6.72E+02 4.72E+01 5.38E+01 6.96E+02 4.12E+01 4.69E+01 7.20E+02 3.59E+01 4.09E+01 Case 4 Dose Rates Case 4 Dose Rates Time Gap Iodine (hrs) (rad-air/hr) (R/hr) 5.76E+02 7.23E+02 8.25E+02 6.00E+02 6.55E+02 7.47E+02 6.24E+02 5.94E+02 6.77E+02 6.48E+02 5.38E+02 6.13E+02 6.72E+02 4.87E+02 5.55E+02 6.96E+02 4.41E+02 5.03E+02 7.20E+02 4.00E+02 4.56E+02 Containment High Range Radiation Monitor CHRRM Response To Drywell Airborne Radioactivity Gap Release Full Gap Activity 20% Gap Activity 10% Gap Activity DEl131 DEl131 DEl131 NG 3.32E4 NG 6.64E3 NG 3.32E3 2.51E7 Ci µCl/g Total 5.02E6 Ci µCi/g Total 2.51E6 Ci µCl/g Total (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) 9.39E+01 8.25E+02 9.18E+02 1.B8E+01 1.65E+02 1.B4E+02 9.39E+OO 8.25E+01 9.18E+01 8.16E+01 7.47E+02 8.29E+02 1.63E+01 1.49E+02 1.66E+02 B.16E+OO 7.47E+01 B.29E+01 7.10E+01 6.77E+02 7.48E+02 1.42E+01 1.35E+02 1.50E+02 7.10E+OO 6.77E+01 7.4BE+01 6.18E+01 6.13E+02 6.75E+02 1.24E+01 1.23E+02 1.35E+02 6.18E+OO 6.13E+01 6.75E+01 5.38E+01 5.55E+02 6.09E+02 1.0BE+01 1.11E+02 1.22E+02 5.38E+OO 5.55E+01 6.09E+01 4.69E+01 5.03E+02 5.50E+02 9.39E+OO 1.01E+02 1.10E+02 4.69E+OO 5.03E+01 5.50E+01 4.09E+01 4.56E+02 4.97E+02 B.19E+OO 9.11E+01 9.93E+01 4.09E+OO 4.56E+01 4.97E+01 5% Gap Activity DEl131 NG 1.66E+3 1.26E6 Ci µCi/g Total (R/hr) (R/hr) (R/hr). 4.69E+OO 4.12E+01 4.59E+01 4.0BE+OO 3.73E+01 4.14E+01 3.55E+OO 3.38E+01 3.74E+01 3.09E+OO 3.06E+01 3.37E+01 2.69E+OO 2.7BE+01 3.05E+01 2.35E+OO 2.52E+01 2.75E+01 2.05E+OO 2.28E+01 2.48E+01 Attachment C Page C4 ofC7 DEl131=300

µCi/gm NG DEl131 2.27E5 Ci 300 µCi/g Total (R/hr) (R/hr) (R/hr) 8.4BE-01 7.45E+OO 8.30E+OO 7.3BE-01 6.75E+OO 7.49E+OO 6.42E-01 6.12E+OO 6.76E+OO 5.59E-01 5.54E+OO 6.10E+OO 4.B7E-01 5.02E+OO 5.50E+OO 4.24E-01 4.55E+OO 4.97E+OO 3.70E-01 4.12E+OO 4.49E+OO CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 1 Dose Rates Gas Time I 100,000 µCi/sec (hrs) I (rad-air/hr) (R/hr) 2.78E-04 1.93E+01 2.20E+01 1.67E-03 1.90E+01 2.17E+01 3.06E-03 1.87E+01 2.13E+01 4.44E-03 1.85E+01 2.11E+01 5.83E-03 1.82E+01 2.08E+01 7.22E-03 1.BOE+01 2.05E+01 8.61E-03 1.77E+01 2.02E+01 1.69E-02 1.63E+01 1.86E+01 2.53E-02 1.51E+01 1.72E+01 3.36E-02 1.39E+01 1.59E+01 4.19E-02 1.29E+01 1.47E+01 5.03E-02 1.20E+01 1.37E+01 5.86E-02 1.11E+01 1.27E+01 6.69E-02 1.04E+01 1.18E+01 7.53E-02 9.68E+OO 1.10E+01 8.36E-02 9.05E+OO 1.03E+01 1.67E-01 5.09E+OO 5.80E+OO 2.SOE-01 3.35E+OO 3.82E+OO 3.34E-01 2.44E+OO 2.78E+OO 4.17E-01 1.87E+OO 2.13E+OO 5.00E-01 1.47E+OO 1.68E+OO 5.84E-01 1.18E+OO 1.34E+OO 6.67E-01 9.43E-01 1.0BE+OO 7.50E-01 7.59E-01 8.66E-01 8.34E-01 6.12E-01 6.9BE-01 9.17E-01 4.95E-01 5.64E-01 11.00E+OOI 4.01E-01 4.57E-01 l.uv1-uv 3.25E-01 3.71E-01 1.17E+OO 2.64E-01 3.01E-01 1.25E+OO 2.15E-01 2.46E-01 1.33E+OO 1.76E-01 2.01E-01 1.42E+OO 1.44E-01 1.65E-01 1.50E+OO 1.19E-01 1.36E-01 1.58E+OO 9.83E-02 1.12E-01 1.67E+OO 8.16E-02 9.30E-02 1.75E+OO 6.81E-02 7.76E-02 1.83E+OO 5.71E-02 6.51E-02 1.92E+OO 4.82E-02 5.50E-02 2.00E+OO 4.10E-02 4.67E-02 2.50E+OO 1.BOE-02 2.05E-02 Containment High Range Radiation Monitor CHRRM Response To Drywell Airborne Radioactivity Reactor Water Release Attachment C Page C5 of C7 IRCS Barrier Loss _ \t Case 2 Dose Rates Normal Reactor Water High Reactor Water I Tech Scee Reactor Water I Reactor Water Iodine NG DEl131 NG DEl131 NG DEl131 I Time I DEl131=1 µCi/gm 2967 µCi/s 4.1 E-5 µCi/g Total 100000 µCi/s 0.2 µCi/g Total 300000 µCi/s 2.0 µCi/g I Total I I (hrs) I (rad-air/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) I (R/hr) I 2.78E-04 4.58E+01 5.22E+01 6.52E-01 2.14E-03 6.54E-01 2.20E+01 1.04E+01 3.24E+01 6.59E+01 1.04E+02 1.70E+02 1.67E-03 4.57E+01 5.21E+01 6.42E-01 2.14E-03 6.45E-01 2.17E+01 1.04E+01 3.21E+01 6.50E+01 1.04E+02 1.69E+02 3.06E-03 4.57E+01 5.21E+01 6.33E-01 2.14E-03 6.35E-01 2.13E+01 1.04E+01 3.18E+01 6.40E+01 1.04E+02 1.68E+02 4.44E-03 4.57E+01 5.21E+01 6.25E-01 2.14E-03 6.27E-01 2.11E+01 1.04E+01 3.15E+01 6.32E+01 1.04E+02 1.67E+02 5.83E-03 4.56E+01 5.20E+01 6.16E-01 2.14E-03 6.18E-01 2.08E+01 1.04E+01 3.12E+01 6.23E+01 1.04E+02 1.66E+02 7.22E-03 4.56E+01 5.19E+01 6.08E-01 2.14E-03 6.10E-01 2.05E+01 1.04E+01 3.09E+01 6.15E+01 1.04E+02 1.65E+02 8.61E-03 4.55E+01 5.19E+01 5.99E-01 2.13E-03 6.02E-01 2.02E+01 1.04E+01 3.06E+01 6.06E+01 1.04E+02 1.64E+02 1.69E-02 4.53E+01 5.17E+01 5.53E-01 2.12E-03 5.55E-01 1.86E+01 1.03E+01 2.90E+01 5.59E+01 1.03E+02 1.59E+02 2.53E-02 4.51E+01 5.14E+01 5.10E-01 2.11E-03 5.12E-01 1.72E+01 1.03E+01 2.75E+01 5.16E+01 1.03E+02 1.54E+02 3.36E-02 4.49E+01 5.12E+01 4.72E-01 2.10E-03 4.74E-01 1.59E+01 1.02E+01 2.61E+01 4.77E+01 1.02E+02 1.50E+02 4.19E-02 4.47E+01 5.09E+01 4.37E-01 2.09E-03 4.39E-01 1.47E+01 1.02E+01 2.49E+01 4.42E+01 1.02E+02 1.46E+02 5.03E-02 4.45E+01 5.07E+01 4.0SE-01 2.0BE-03 4.07E-01 1.37E+01 1.01E+01 2.38E+01 4.10E+01 1.01E+02 1.42E+02 5.86E-02 4.43E+01 5.05E+01 3.77E-01 2.07E-03 3.79E-01 1.27E+01 1.01E+01 2.28E+01 3.81E+01 1.01E+02 1.39E+02 6.69E-02 4.40E+01 5.02E+01 3.51E-01 2.06E-03 3.53E-01 1.18E+01 1.00E+01 2.19E+01 3.55E+01 1.00E+02 1.36E+02 7.53E-02 4.38E+01 5.00E+01 3.28E-01 2.05E-03 3.30E-01 1.10E+01 1.00E+01 2.10E+01 ! 3.31E+01 1.00E+02 1.33E+02 8.36E-02 4.36E+01 4.97E+01 3.06E-01 2.04E-03 3.08E-01 1.03E+01 9.95E+OO 2.03E+01 3.10E+01 9.95E+01 1.30E+02 1.67E-01 4.16E+01 4.74E+01 1.72E-01 1.95E-03 1.74E-01 5.80E+OO 9.49E+OO 1.53E+01 1.74E+01 9.49E+01 1.12E+02 2.50E-01 3.97E+01 4.53E+01 1.13E-01 1.86E-03 1.15E-01 3.82E+OO 9.06E+OO 1.29E+01 1.15E+01 9.06E+01 1.02E+02 3.34E-01 3.79E+01 4.32E+01 8.24E-02 1.78E-03 8.42E-02 2.78E+OO 8.65E+OO 1.14E+01 B.33E+OO 8.65E+01 9.48E+01 4.17E-01 3.62E+01 4.13E+01 6.33E-02 1.70E-03 6.SOE-02 2.13E+OO 8.26E+OO 1.04E+01 6.40E+OO B.26E+01 8.90E+01 5.00E-01 3.46E+01 3.95E+01 4.99E-02 1.62E-03 5.15E-02 1.68E+OO 7.89E+OO 9.57E+OO 5.04E+OO 7.89E+01 8.40E+01 5.84E-01 3.31E+01 3.78E+01 3.9BE-02 1.55E-03 4.13E-02 1.34E+OO 7.55E+OO 8.89E+OO 4.02E+OO 7.55E+01 7.95E+01 6.67E-01 3.17E+01 3.61E+01 3.19E-02 1.48E-03 3.34E-02 1.0BE+OO 7.22E+OO 8.30E+OO 3.23E+OO 7.22E+01 7.55E+01 7.50E-01 3.03E+01 3.46E+01 2.57E-02 1.42E-03 2.71E-02 8.66E-01 6.92E+OO 7.78E+OO 2.60E+OO 6.92E+01 7.18E+01 8.34E-01 2.91E+01 3.31E+01 2.07E-02 1.36E-03 2.21E-02 6.98E-01 6.63E+OO 7.33E+OO 2.09E+OO 6.63E+01 6.84E+01 Q 17F-n1 2.79E+01 3.18E+01 1.67E-02 1.31E-03 1.BOE-02 5.64E-01 6.35E+OO 6.92E+OO 1.69E+OO 6.35E+01 11.00E+OOI 2.67E+01 3.05E+01 1.36E-02 1.25E-03 1.48E-02 4.57E-01 6.10E+OO 6.55E+OO 1.37E+OO 6.10E+01 6.23E+011 1.08E+OO 2.57E+01 2.93E+01 1.10E-02 1.20E-03 1.22E-02 3.71E-01 5.85E+OO 6.22E+OO 1.11E+OO 5.85E+01 V 1.17E+OO 2.47E+01 2.81E+01 8.94E-03 1.16E-03 1.01E-02 3.01E-01 5.62E+OO 5.92E+OO 9.04E-01 5.62E+01 5.71E+01 1.25E+OO 2.37E+01 2.70E+01 7.29E-03 1.11E-03 8.40E-03 2.46E-01 5.40E+OO 5.65E+OO 7.37E-01 5.40E+01 5.48E+01 1.33E+OO 2.28E+01 2.60E+01 5.96E-03 1.07E-03 7.03E-03 2.01E-01 5.20E+OO 5.40E+OO 6.02E-01 5.20E+01 5.26E+01 1.42E+OO 2.19E+01 2.50E+01 4.89E-03 1.03E-03 5.91E-03 1.65E-01 5.00E+OO 5.17E+OO 4.94E-01 5.00E+01 5.05E+01 1.50E+OO 2.11E+01 2.41E+01 4.02E-03 9.90E-04 5.01E-03 1.36E-01 4.82E+OO 4.95E+OO 4.07E-01 4.82E+01 4.86E+01 1.58E+OO 2.04E+01 2.32E+01 3.32E-03 9.54E-04 4.2BE-03 1.12E-01 4.64E+OO 4.76E+OO 3.36E-01 4.64E+01 4.6BE+01 1.67E+OO 1.96E+01 2.24E+01 2.76E-03 9.20E-04 3.68E-03 9.30E-02 4.48E+OO 4.57E+OO 2.79E-01 4.48E+01 4.51E+01 1.75E+OO 1.90E+01 2.16E+01 2.30E-03 B.BBE-04 3.19E-03 7.76E-02 4.32E+OO 4.40E+OO 2.33E-01 4.32E+01 4.34E+01 1.83E+OO 1.B3E+01 2.09E+01 1.93E-03 8.58E-04 2.79E-03 6.51E-02 4.18E+OO 4.24E+OO 1.95E-01 4.18E+01 4.20E+01 1.92E+OO 1.77E+01 2.02E+01 1.63E-03 B.29E-04 2.46E-03 5.50E-02 4.03E+OO 4.09E+OO 1.65E-01 4.03E+01 4.05E+01 2.00E+OO 1.71E+01 1.95E+01 1.39E-03 8.02E-04 2.19E-03 4.67E-02 3.90E+OO 3.95E+OO 1 AOE-01 3.90E+01 3.92E+01 2.50E+OO 1.42E+01 1.62E+01 6.09E-04 6.65E-04 1.27E-03 2.05E-02 3.24E+OO 3.26E+OO 6.16E-02 3.24E+01 3.24E+01 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 1 Dose Rates Gas Time 100,000 µCi/sec (hrs) (rad-air/hr) (R/hr) 3.00E+OO 1.04E-02 1.19E-02 3.50E+OO 7.36E-03 8.39E-03 4.00E+OO 5.84E-03 6.66E-03 4.50E+OO 4.92E-03 5.61E-03 5.00E+OO 4.27E-03 4.87E-03 5.50E+OO 3.77E-03 4.30E-03 6.00E+OO 3.36E-03 3.84E-03 6.50E+OO 3.02E-03 3.45E-03 7.00E+OO 2.73E-03 3.12E-03 7.50E+OO 2.48E-03 2.83E-03 8.00E+OO 2.26E-03 2.58E-03 1.00E+01 1.60E-03 1.83E-03 1.20E+01 1.18E-03 1.35E-03 1.40E+01 9.05E-04 1.03E-03 1.60E+01 7.18E-04 8:19E-04 1.80E+01 5.BBE-04 6.70E-04 2.00E+01 4.95E-04 5.64E-04 2.20E+01 4.25E-04 4.85E-04 2.40E+01 3.73E-04 4.25E-04 2.80E+01 3.00E-04 3.42E-04 3.20E+01 2.51E-04 2.86E-04 3.60E+01 2.17E-04 2.48E-04 4.00E+01 1.92E-04 2.19E-04 4.40E+01 1.74E-04 1.98E-04 4.80E+01 1.BOE-04 1.82E-04 5.20E+01 1.48E-04 1.69E-04 5.60E+01 1.39E-04 1.59E-04 6.00E+01 1.32E-04 1.51E-04 6.40E+01 1.26E-04 1.44E-04 6.80E+01 1.21E-04 1.38E-04 7.20E+01 1.17E-04 1.33E-04 7.60E+01 1.13E-04 1.29E-04 8.00E+01 1.D9E-04 1.25E-04 8.40E+01 1.06E-04 1.21E-04 8.80E+01 1.03E-04 1.18E-04 9.2DE+01 1.01E-04 1.15E-04 9.60E+01 9.82E-05 1.12E-04 1.20E+02 8.51E-05 9.70E-05 1.44E+02 7.43E-05 8.47E-05 1.68E+02 6.49E-05 7.40E-05 Containment High Range Radiation Monitor CHRRM Response To Drywall Airborne Radioactivity Reactor Water Release Case 2 Dose Rates Normal Reactor Water High Reactor Water Reactor Water Iodine NG DEl131 NG DEl131 Time DEl131=1 µCi/gm 2967 µCi/s 4.1 E-5 µCi/g Total 100000 µCi/s 0.2 µCi/g Total (hrs) (rad-air/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) 3.00E+OO 1.20E+01 1.37E+01 3.52E-04 5.64E-04 9.16E-04 1.19E-02 2.75E+OO 2.76E+OO 3.50E+OO 1.04E+01 1.19E+01 2.49E-04 4.88E-04 7.37E-04 8.39E-03 2.38E+OO 2.38E+OO 4.00E+OO 9.18E+OO 1.05E+01 1.98E-04 4.30E-04 6.2BE-04 6.66E-03 2.09E+OO 2.10E+OO 4.50E+OO 8.21E+OO 9.36E+OO 1.66E-04 3.85E-04 5.51E-04 5.61E-03 1.87E+OO 1.88E+OO 5.00E+OO 7.43E+OO 8.47E+OO 1.44E-04 3.48E-04 4.93E-04 4.87E-03 1.69E+OO 1.70E+OO 5.50E+OO 6.79E+OO 7.75E+OO 1.27E-04 3.18E-04 4.46E-04 4.30E-03 1.55E+OO 1.55E+OO 6.00E+OO 6.26E+OO 7.14E+OO 1.14E-04 2.93E-04 4.07E-04 3.84E-03 1.43E+OO 1.43E+OO 6.50E+OO 5.81E+OO 6.63E+OO 1.02E-04 2.72E-04 3.75E-04 3.45E-03 1.33E+OO 1.33E+OO 7.00E+OO 5.42E+OO 6.18E+OO 9.25E-05 2.54E-04 3.47E-04 3.12E-03 1.24E+OO 1.24E+OO 7.50E+OO 5.08E+OO 5.79E+OO 8.39E-05 2.38E-04 3.22E-04 2.83E-03 1.16E+OO 1.16E+OO 8.00E+OO 4.78E+OO 5.45E+OO 7.65E-05 2.24E-04 3.01E-04 2.58E-03 1.09E+OO 1.09E+OO 1.00E+01 3.85E+OO 4.39E+OO 5.42E-05 1.BOE-04 2.34E-04 1.83E-03 8.78E-01 8.79E-01 1.20E+01 3.19E+OO 3.64E+OO 4.00E-05 1.49E-04 1.89E-04 1.35E-03 7.27E-01 7.28E-01 1.40E+01 2.69E+OO 3.07E+OO 3.06E-05 1.26E-04 1.57E-04 1.03E-03.

6.13E-01 6.14E-01 1.60E+01 2.30E+OO 2.62E+OO 2.43E-05 1.0BE-04 1.32E-04 8.19E-04 5.25E-01 5.26E-01 1.80E+01 1.99E+OO 2.26E+OO 1.99E-05 9.31E-05 1:12E-04 6.70E-04 4.53E-01 4.54E-01 2.00E+01 1.73E+OO 1.97E+OO 1.67E-05 8.10E-05 9.78E-05 5.64E-04 3.94E-01 3.95E-01 2.20E+01 1.51E+OO 1.73E+OO 1.44E-05 7.10E-05 8.53E-05 4.85E-04 3.45E-01 3.46E-01 2.40E+01 1.33E+OO 1.52E+OO 1.26E-05 6.25E-05 7.51E-05 4.25E-04 3.04E-01 3.04E-01 2.80E+01 1.05E+OO 1.20E+OO 1.01E-05 4.92E-05 5.93E-05 3.42E-04 2.39E-01 2.40E-01 3.20E+01 8.40E-01 9.57E-01 8.50E-06 3.93E-05 4.78E-05 2.86E-04 1.91E-01 1.92E-01 3.60E+01 6.83E-01 7.79E-01 7.35E-06 3.20E-05 3.94E-05 2.48E-04 1.56E-01 1.56E-01 4.00E+01 5.64E-01 6.43E-01 6.51E-06 2.64E-05 3.29E-05 2.19E-04 1.29E-01 1.29E-01 4.40E+01 4.72E-01 5.38E-01 5.88E-06 2.21E-05 2.BOE-05 1.98E-04 1.0BE-01 1.0BE-01 4.80E+01 4.00E-01 4.56E-01 5.40E-06 1.87E-05 2.41E-05 1.82E-04 9.12E-02 9.14E-02 5.20E+01 3.43E-01 3.91E-01 5.02E-06 1.61E-05 2.11E-05 1.69E-04 7.82E-02 7.84E-02 5.60E+01 2.98E-01 3.39E-01 4.72E-06 1.39E-05 1.87E-05 1.59E-04 6.78E-02 6.BOE-02 6.00E+01 2.61E-01 2.97E-01 4.47E-06 1.22E-05 1.67E-05 1.51E-04 5.94E-02 5.96E-02 6.40E+01 2.30E-01 2.62E-01 4.27E-06 1.0BE-05 1.50E-05 1.44E-04 5.25E-02 5.26E-02 6.80E+01 2.05E-01 2.34E-01 4.09E-06 9.BOE-06 1.37E-05 1.38E-04 4.67E-02 4.69E-02 7.20E+01 1.84E-01 2.09E-01 3.95E-06 8.61E-06 1.26E-05 1.33E-04 4.19E-02 4.20E-02 7.60E+01 1.66E-01 1.89E-01 3.82E-06 7.77E-06 1.16E-05 1.29E-04 3.78E-02 3.BOE-02 8.00E+01 1.51E-01 1.72E-01 3.70E-06 7.06E-06 1.0BE-05 1.25E-04 3.44E-02 3.45E-02 8.40E+01 1.38E-01 1.57E-01 3.60E-06 6.46E-06 1.01E-05 1.21E-04 3.14E-02 3.15E-02 8.80E+01 1.27E-01 1.44E-01 3.50E-06 5.93E-06 9.43E-06 1.18E-04 2.BBE-02 2.90E-02 9.20E+01 1.17E-01 1.33E-01 3.41E-06 5.47E-06 8.88E-06 1.15E-04 2.66E-02 2.68E-02 9.60E+01 1.0BE-01 1.23E-01 3.32E-06 5.0BE-06 8.40E-06 1.12E-04 2.47E-02 2.4BE-D2 1.2DE+02 7.48E-02 8.53E-02 2.88E-06 3.51E-06 6.38E-06 9.70E-05 1.71E-02 1.72E-02 1.44E+02 5.74E-02 6.55E-02 2.51E-06 2.69E-06 5.20E-06 8.47E-05 1.31E-02 1.32E-02 1.68E+02 4.72E-02 5.38E-02 2.20E-06 2.21E-06 4.41E-06 7.40E-05 1.0BE-02 1.0BE-02 Attachment C Page CS of C7 Tech Spec Reactor Water NG DEl131 300000 µCi/s 2.0 ftCi/g Total (R/hr) (R/hr) (R/hr) 3.56E-02 2.75E+01 2.75E+01 2.52E-02 2.38E+01 2.38E+01 2.00E-02 2.09E+01 2.10E+01 1.68E-02 1.87E+01 1.87E+01 1.46E-02 1.69E+01 1.70E+01 1.29E-02 1.55E+01 1.55E+01 1.15E-02 1.43E+01 1.43E+01 1.03E-02 1.33E+01 1.33E+01 9.35E-03 1.24E+01 1.24E+01 8.49E-03 1.16E+01 1.16E+01 7.73E-03 1.09E+01 1.09E+01 5.48E-03 8.78E+OO 8.78E+OO 4.04E-03 7.27E+OO 7.27E+OO 3.10E-03 6.13E+OO 6.14E+OO 2.46E-03 5.25E+OO . 5.25E+OO 2.01E-03 4.53E+OO 4.53E+OO 1.69E-03 3.94E+OO 3.94E+OO 1.46E-03 3.45E+OO 3.45E+OO 1.28E-03 3.04E+OO 3.04E+OO 1.02E-03 2.39E+OO 2.39E+OO 8.59E-04 1.91E+OO 1.92E+OO 7.43E-04 1.56E+OO 1.56E+OO 6.58E-04 1.29E+OO 1.29E+OO 5.95E-04 1.08E+OO 1.0BE+OO 5.46E-04 9.12E-01 9.13E-01 5.07E-04 7.B2E-01 7.83E-01 4.77E-04 6.78E-01 6.79E-01 4.52E-04 5.94E-01 5.95E-01 4.31E-04 5.25E-01 5.25E-01 4.14E-04 4.67E-01 4.BBE-01 3.99E-04 4.19E-01 4.19E-01 3.86E-04 3.78E-01 3.79E-01 3.74E-04 3.44E-01 3.44E-01 3.64E-04 3.14E-01 3.15E-01 3.54E-04 2.BBE-01 2.89E-01 3.44E-04 2.66E-01 2.67E-01 3.36E-04 2.47E-01 2.47E-01 2.91E-04 1.71E-01 1.71E-01 2.54E-04 1.31E-01 1.31E-01 2.22E-04 1.0BE-01 1.0BE-01 CA-04-194, "Containment High Range Radiation Monitor (CHRRM) Response to Drywell Airborne Activity" Cale. 2004-07060 Rev.2 S/R Case 1 Dose Rates Gas Time 100,000 µCi/sec (hrs) (rad-air/hr) (R/hr) 1.92E+02 5.69E-05 6.49E-05 2.16E+02 4.99E-05 5.69E-05 2.40E+02 4.38E-05 5.00E-05 2.64E+02 3.86E-05 4.40E-05 2.8BE+02 3.40E-05 3.BBE-05 3.12E+02 3.01E-05 3.43E-05 3.36E+02 2.66E-05 3.03E-05 3.60E+02 2.36E-05 2.69E-05 3.84E+02 2.10E-05 2.40E-05 4.0BE+02 1.87E-05 2.14E-05 4.32E+02 1.68E-05 1.91E-05 4.56E+02 1.50E-05 1.71E-05 4.80E+02 1.35E-05 1.54E-05 5.04E+02 1.22E-05 1.39E-05 5.2BE+02 1.11E-05 1.26E-05 5.52E+02 1.01E-05 1.15E-05 5.76E+02 9.17E-06 1.05E-05 6.00E+02 B.40E-06 9.57E-06 6.24E+02 7.71E-06 B.79E-06 6.48E+02 7.11E-06 8.11E-06 6.72E+02 6.5BE-06 7.50E-06 6.96E+02 6.11E-06 6.97E-06 7.20E+02 5.69E-06 6.49E-06 Containment High Range Radiation Monitor CHRRM Response To Drywell Airborne Radioactivity Reactor Water Release Case 2 Dose Rates Normal Reactor Water High Reactor Water Reactor Waler Iodine NG DEl131 NG DEl131 Time DEl131 = 1 µCi/gm 2967 µCi/s 4.1 E-5 µCi/g Total 100000 µCi/s 0.2 µCi/g (hrs) (rad-air/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) (R/hr) 1.92E+02 4.03E-02 4.59E-02 1.92E-06 1.89E-06 3.81E-06 6.49E-05 9.19E-03 2.16E+02 3.52E-02 4.01E-02 1.69E-06 1.65E-06 3.34E-06 5.69E-05 8.03E-03 2.40E+02 3.11E-02 3.54E-02 1.48E-06 1.46E-06 2.94E-06 5.00E-05 7.09E-03 2.64E+02 2.76E-02 3.15E-02 1.30E-06 1.29E-06 2.60E-06 4.40E-05 6.30E-03 2.88E+02 2.46E-02 2.81E-02 1.15E-06 1.15E-06 2.30E-06 3.BBE-05 5.61E-03 3.12E+02 2.20E-02 2.51E-02 1.02E-06 1.03E-06 2.05E-06 3.43E-05 5.02E-03 3.36E+02 1.97E-02 2.24E-02 9.00E-07 9.22E-07 1.82E-06 3.03E-05 4.49E-03 3.60E+02 1.76E-02 2.01E-02 7.99E-07 8.25E-07 1.62E-06 2.69E-05 4.02E-03 3.84E+02 1.58E-02 1.BOE-02 7.11E-07 7.40E-07 1.45E-06 2.40E-05 3.60E-03 4.0BE+02 1.41E-02 1.61E-02 6.34E-07 6.63E-07 1.30E-06 2.14E-05 3.22E-03 4.32E+02 1.27E-02 1.44E-02 5.67E-07 5.94E-07 1.16E-06 1.91E-05 2.89E-03 4.56E+02 1.14E-02 1.30E-02 5.0SE-07 5.33E-07 1.04E-06 1.71E-05 2.59E-03 4.BOE+02 1.02E-02 1.16E-02 4.5BE-07 4.7BE-07 9.36E-07 1.54E-05 2.33E-03 5.04E+02 9.16E-03 1.04E-02 4.13E-07 4.29E-07 B.43E-07 1.39E-05 2.09E-03 5.2BE+02 B.22E-03 9.38E-03 3.74E-07 3.85E-07 7.60E-07 1.26E-05 1.BBE-03 5.52E+02 7.39E-03 8.42E-03 3.40E-07 3.46E-07 6.86E-07 1.15E-05 1.68E-03 5.76E+02 6.64E-03 7.57E-03 3.10E-07 3.11E-07 6.21E-07 1.05E-05 1.51E-03 6.00E+02 5.97E-03 6.81E-03 2.B4E-07 2.BOE-07 5.64E-07 9.57E-06 1.36E-03 6.24E+02 5.37E-03 6.12E-03 2.61E-07 2.52E-07 5.12E-07 B.79E-06 1.22E-03 6.48E+02 4.B3E-03 5.51E-03 2.41E-07 2.26E-07 4.67E-07 8.11E-06 1.10E-03 6.72E+02 4.34E-03 4.95E-03 2.23E-07 2.04E-07 4.26E-07 7.50E-06 9.90E-04 6.96E+02 3.91E-03 4.46E-03 2.07E-07 1.B3E-07 3.90E-07 6.97E-06 B.92E-04 7.20E+02 3.52E-03 4.01E-03 1.93E-07 1.65E-07 3.57E-07 6.49E-06 B.03E-04 Total (R/hr) 9.25E-03 8.0SE-03 7.14E-03 6.34E-03 5.65E-03 5.05E-03 4.52E-03 4.04E-03 3.62E-03 3.25E-03 2.91E-03 2.61E-03 2.34E-03 2.10E-03 1.89E-03 1.70E-03 1.52E-03 1.37E-03 1.23E-03 1.11E-03 9.98E-04 8.99E-04 8.09E-04 Attachment C Page C7 ofC7 Tech Spec Reactor Water NG DEl131 300000 µCi/s 2.0 µCi/g Total (R/hr) (R/hr) (R/hr) 1.95E-04 9.19E-02 9.21E-02 1.71E-04 8.03E-02 8.04E-02 1.50E-04 7.09E-02 7.10E-02 1.32E-04 6.30E-02 6.31E-02 1.16E-04 5.61E-02 5.63E-02 1.03E-04 5.02E-02 5.03E-02 9.10E-05 4.49E-02 4.50E-02 8.0BE-05 4.02E-02 4.02E-02 7.19E-05 3.60E-02 3.61E-02 6.41E-05 3.22E-02 3.23E-02 5.73E-05 2.B9E-02 2.90E-02 5.14E-05 2.59E-02 2.60E-02 4.63E-05 2.33E-02 2.33E-02 4.18E-05 2.09E-02 2.09E-02 3.78E-05 1.BBE-02 1.BBE-02 3.44E-05 1.68E-02 1.69E-02 3.14E-05 1.51E-02 1.52E-02 2.87E-05 1.36E-02 1.36E-02 2.64E-05 1.22E-02 1.23E-02 2.43E-05 1.10E-02 1.10E-02*

2.25E-05 9.90E-03 9.93E-03 2.09E-05 B.92E-03 1.95E-05 8.03E-03 8.05E-03

ML17095A115

Text

SUMMARY

SUMMARY

SUMMARY

2.3 Acceptance

4.1 Drywall

4.2 Noble

5.1 Geometric

SUMMARY

Subject:

7.3 Drawing

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