ML042650403

Results of Revised Control Room Radiation Monitors Analytical Limit Calculations to Reflect the Proposed Control Room Emergency Air Treatment System (Creats) Modification and Change in Dose Calculation Methodology to Alternate Source Term

ML042650403
Person / Time
Site:	Ginna
Issue date:	09/10/2004
From:	Korsnick M Constellation Energy Group
To:	Clark R Document Control Desk, Office of Nuclear Reactor Regulation
References
DA-EE-2001-013, Rev 1
Download: ML042650403 (49)

Text

Maria Korsnick 1503 Lake Road Vice President Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick@constellation.com Constellation Energy R.E. Ginna Nuclear Power Plant September 10, 2004 Mr. Robert L. Clark Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C. 20555-0001

Subject:

Results of Revised Control Room Radiation Monitors Analytical Limit Calculations to Reflect the Proposed Control Room Emergency Air Treatment System (CREATS) Modification and Change in Dose Calculation Methodology to Alternate Source Term R.E. Ginna Nuclear Power Plant Docket No. 50-244

References:

1. Letter from Robert C. Mecredy (RG&E) to Robert L. Clark (NRC) dated May 21, 2003, License Amendment Request Regarding Revision of Ginna Technical Specification Sections 1.1, 3.3.6, 3.4.16, 3.6.6, 3.7.9, 5.5.10, 5.5.16, and 5.6.7 Resulting From Modification of the Control Room Emergency Air Treatment System and Change in Dose Calculation Methodology to Alternate Source Term.

2. Letter from Robert C. Mecredy (RG&E) to Robert L. Clark (NRC) dated March 8, 2004, Response to Request for Additional Information (RAI) Regarding Proposed CREATS Modification and Change in Dose Calculation Methodology to Alternate Source Term.

Dear Mr. Clark:

In Reference 2, R.E. Ginna Nuclear Power Plant, LLC (formerly RG&E) committed to "Evaluate and revise DA-EE-2001-013 (Control Room Radiation Monitor Analytical Limit Calculation) if necessary to reflect Alternate Source Term (AST) sources and evaluate the current use of combinations of dose equivalent rate and exposure rate." Also, in order to ensure air intake radiation monitor response time, Ginna committed to "revise RG&E Calculation Sheet 10.26 (Control Room Isolation Time) using outputs of the new dose analysis and provide information to NRC.t Subsequent to this commitment it was decided to incorporate the relevant information from Calculation Sheet 10.26 into DA-EE-2001-013.

Per your request during a phone conversation on August 24, 2004, the attachment to this letter contains the revised analysis rather than a summary of the results. The analysis demonstrates that, given the source cloud concentrations assumed for the AST, the radiation monitors would function to isolate the control room and start the CREATS fans within the times assumed in the dose analysis for those accidents crediting the monitors. In the telecom, it was also requested that the inappropriate mixing of the terms dose equivalent rate and exposure rate be clarified.

This has been done.

A aI

/00 I/CI

This information should be docketed as an addendum to Reference 1. If you have questions regarding the content of this correspondence please contact Mr. Mike Ruby at (585) 771-3572 or Mr. George Wrobel at (585) 771-3535.

Very truly yours, Mary G.

orsnick STATE OF NEW YORK

TO WIT:

COUNTY OF WAYNE I, Mary G. Korsnick, being duly sworn, state that I am Vice President - R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), and that I am duly authorized to execute and file this response on behalf of Ginna LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Ginna LLC employees and/or consultants. Such information has been revie in accordance with company practice and I believe it to be reliable.

acran with U Jo

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Subscrbed and sworn before me, a Notary Public in and for the State of New York and County of

,ioIieo$

,this /o"f day of 5etj-nhteK, 2004.

WITNESS my Hand and Notarial Seal:

My Commission Expires:

On I, 2/ -6oO' U

Date Attachments:

Notary Public MICHALENE A BUNTS Notary Public, State of NewYork Registration No. 01 BU6018576 Monroe County oO' Commission Expires Jan

1.

Design Analysis DA-EE-2001-013, Revision I Cc:

Mr. Robert L. Clark (Mail Stop 0-8-C2)

Project Directorate I Division of Licensing Project Management Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Mr. Peter R. Smith New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy NYS Department of Public Service 3 Empire State Plaza, 10 th Floor Albany, NY 12223 James M. Petro Jr.

Counsel, Generation - Nuclear Constellation Energy 750 East Pratt Street, 17th Floor Baltimore, MD 21202

Attachment I Design Analysis DA-EE-2001-013 Revision I Note: To remain consistent with the examples cited in the analysis text, and to limit the size of this transmittal, only the MegaShield input and output files for the Control Rod Ejection accident (Attachments 31 - 36) are included. Data from the remaining analyzed accidents will be available for site review, or be provided upon request.

Design Analysis Ginna Station Control Room Radiation Monitors Analytical Limit Calculation DA-EE-2001-013 Revision 1 Effective Date 6__

yq/G-Prepared By:

Reviewed By:

Reviewed By:

Assigned Engineer Assigned Engineer Licensing d

bate q Z3 /O(6 Date Date DA-EE-2001-013 Page I of 21 Revri sion 1

Revision Status Sheet Revision Affected Number Sections Description of Revision 0

All Original.

1 1.2 Indicate analysis supports timing assumptions.

1 1.3 Indicate use of AST 1

2.1 Update conclusion to include all applicable accident scenarios.

1 3.3 Add AST to Design Input 1

6.2 Updated computer output to include all accident scenarios reviewed and analysis results.

1 7.1.1 Add occupancy factor derivation 1

7.2.3 Remove AP exposure from control room dose rate explanation.

1 7.2.4 Update section to include all accident evaluations and related ratios 1

7.2.6 Add discussion on analytical limit for all accidents evaluated 1

7.3.1 Updated section to utilize CRE assummed accident information.

1 8.3 Add details regarding AST.

DA-EE-2001-013 Page 2 of 21 Revi sion 1

1.0 Purpose 1.1 The purpose of this analysis is to determine the analytical limit for the Control Room Radiation Monitors R-45 and R-46 such that they will initiate control room isolation to ensure that Control Room dose stays below required limits. This will include calculations that support the installation of the radiation detectors in the air intake duct and show the relationship between "in duct" exposure rates, as measured by R-45 and R-46, and the effective dose rate for Control Room personnel.

1.2 This analysis will also demonstrate that, for those accidents crediting the Radiation Monitors, the monitors actuate the Control Room Emergency Air Treatment System (CREATS) system within the 60 seconds assumed in the dose analysis.

1.3 Verify monitor response assuming alternate source term (AST) concentrations 2.0 Conclusions 2.1 Control Room doses were analyzed per Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. Safety Injection (SI) is credited with initiating the CREATS emergency mode within the time assumed in the dose analysis for Loss of Coolant Accident (LOCA), Steam Generator Tube Rupture (SGTR) and Main Steam Line Break (MSLB) accidents. For other analyzed accidents including Control Rod Ejection (CRE), Locked RCP Rotor (LR), and the Fuel Handling Accident (FHA), the radiation monitors are credited with CREATS actuation. As can be seen from the results of this analysis, the monitors would actuate CREATS within the 60 seconds assumed in the control room dose analysis for these accidents. CREATS actuation is not required for Gas Decay Tank (GDT) Rupture or the Spent Fuel Pool Tornado Missile Accidents (TMA).

3.0 Design Inputs 3.1 PCR 99-004, Control Room Radiation Monitor Replacement.

3.2 EE-171, Control Room Radiation Monitor Specification, Ginna Station, PCR 99-004 3.3 Alternate Source Term Plume Concentrations 4.0 Referenced Documents 4.1 Drawings RG&E Drawings:

Drawing #

SK33013-2787-1 DA-EE-2001-013 Page 3 of 21 RevisRion 1

4.2 Codes And Standards 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.3 4.3.1 5.0 GDC 19 NUREG-0737, Clarification of TMI Action Plan Requirements section 11.B.2, Dose Rate Criteria NUREG-0800 Standard Review Plan section 6.4, Control Room Habitability Program ICRP #23 Report of the Task Group on Reference Man, 1975. (Pg. 15-Length of total body for reference adult male: 170 cm)

Ginna Calc. Note 10.26, Control Room Isolation Time.

Equipment Information Inovision Installation, Operation, and Maintenance Instruction Manual, Area Monitoring System, Model 955A Assumptions Assumptions made are detailed within the calculation, and have all been evaluated to be in the conservative direction, as discussed.

Computer Codes MegaShield 1.2, WMG, used to calculate dose rates for given isotope cloud and geometries. This analysis has printouts attached for the various models.

Computer Output Below is the tabulation of computer runs performed using MegaShield, identified by Source Term and Case ID. The outputs of each case run is attached to this analysis, and can be identified by the Case ID. A summary of the results are tabulated in section 7.2.3.

5.1 6.0 6.1 6.2 Source Case ID Attachment #

Description Term Large Break DA-EE-2001-Control room ductwork, short end piece when LOCA 013\\SHORT26A.MSI detector is located 26" into ductwork.

LBLOCA source term.

Large Break DA-EE-2001-Control room ductwork, long end piece when LOCA 013\\LONG26A.MSI detector is located 26" into ductwork.

LBLOCA source term.

DA-EE-2001-013 Page 4 o f 21 Revi sion I

Large Break DA-EE-2001-Area at side of detector, used for both 26" and LOCA 013\\DONUTSA.MSI 38" location. Two (2) required to cover both sides of detector. LBLOCA source term.

Large Break DA-EE-2001 -

Control room ductwork, short end piece when LOCA 013\\SHORT38A.MSI detector is located 38" into ductwork.

LBLOCA source term Large Break DA-EE-2001-Control room ductwork, long end piece when LOCA 013\\LONG38A.MSI detector is located 38" into ductwork.

LBLOCA source term.

Large Break DA-EE-2001-LBLOCA source term. Control room LOCA 013\\CONTROLR.MSI shielding run based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose.

Locked Rotor DA-EE-2001 -

Control room ductwork, short end piece wvhen 013\\CRA26SLR.MS1 detector is located 26" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-Control room ductwork, long end piece when 013\\CR26LALR.MSI detector is located 26" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-Area at side of detector, used for both 26" and 013\\CRALR.MS1 38" location. Two (2) required to cover both sides of detector. Locked rotor source term.

Locked Rotor DA-EE-2001- 0 Control room ductwork, short end piece when 013\\CRA38SLR.MSI detector is located 38" into ductwork.

Locked rotor source term.

Locked Rotor DA-EE-2001-1 Control room ductwork, long end piece when 013\\CRA38LLR.MSI detector is located 38" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-2 Locked rotor source term. Control room 013\\CRCRALR.MS I shielding run based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose.

Steam DA-EE-2001-3 Generator 013\\CRA26SSG.MSI Control room ductwork, short end piece when Tube Rupture detector is located 26" into ductwork. SGTR source term.

Steam DA-EE-2001-4 Control room ductwork, long end piece when Generator 013\\CRA26LSG.MSI detector is located 26" into ductwork. SGTR Tube Rupture source term.

Steam DA-EE-2001-5 Area at side of detector, used for both 26" and Generator 013\\CRADOSG.MSI 38" location. Two (2) required to cover both Tube Rupture sides of detector. SGTR source term.

DA-EE-2001-013 Page 5 of 21 Revrision I

Steam DA-EE-2001-6 Control room ductwork, short end piece when Generator 013\\CRA38SSG.MSI detector is located 38" into ductwork. SGTR Tube Rupture source term Steam DA-EE-2001-7 Control room ductwork, long end piece when Generator 013\\CRA38LSG.MSI detector is located 38" into ductwork. SGTR Tube Rupture source term.

Steam DA-EE-2001-8 SGTR source term. Control room shielding Generator 013\\CRACRSG.MSI run based on cutting the control room into (4)

Tube Rupture mirror rectangles and then multiplying by four to determine receptor dose.

Fuel 9 Control room ductwork, short end piece when Handling DA-EE-2001-detector is located 26" into ductwork. Fuel Accident in 013\\CRA26SFH.MSI handling accident in SFP source term.

SFP Fuel DA-EE-2001- 0 Control room ductwork, long end piece when Handling 013\\CRA26LFH.MSI detector is located 26" into ductwork. Fuel Accident in handling accident in SFP source term.

SFP Fuel DA-EE-2001-1 Area at side of detector, used for both 26" and Handling 013\\CRADOFH.MSI 38" location. Two (2) required to cover both Accident in sides of detector. Fuel handling accident in SFP SFP source term.

Fuel DA-EE-2001-2 Control room ductwork, short end piece when Handling 013\\CRA38SFH.MSI detector is located 38" into ductwork. Fuel Accident in handling accident in SFP source term.

SFP Fuel DA-EE-2001-3 Control room ductwork, long end piece when Handling 013\\CRA38LFH.MSI detector is located 38" into ductwork. Fuel Accident in handling accident in SFP source term.

SFP Fuel DA-EE-2001-4 Fuel handling accident in SFP source term.

Handling 013\\CRACRFH.MS I Control room shielding run based on cutting Accident in the control room into (4) mirror rectangles SFP and then multiplying by four to determine receptor dose Tornado DA-EE-2001-5 Control room ductwork, short end piece when Missile 013\\CRA26STM.MSI detector is located 26" into ductwork.

Tornado missile source term.

Tornado DA-EE-2001-6 Control room ductwork, long end piece when Missile 013\\CRA26LTM.MSI detector is located 26" into ductwork.

Tornado missile source term.

Tornado DA-EE-2001-7 Area at side of detector, used for both 26" and Missile 013\\CRADOTM.MSI 38" location. Two (2) required to cover both sides of detector. Tomado missile source term.

Tornado DA-EE-2001-8 Control room ductwork, short end piece when Missile 013\\CRA38STM.MSI detector is located 38" into ductvork.

Tornado missile source term.

DA-EE-2001-013 Page 6 of 21 Revision I

Tomado DA-EE-2001-9 Control room ductwork, long end piece when Missile 013\\CRA38LLR.MSI detector is located 38" into ductwork.

Tornado missile source term.

Tornado DA-EE-2001- 0 Tornado missile source term. Control room Missile 013\\CRACRTM.MSI shielding run based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Control Rod DA-EE-2001-1 Control room ductwork, short end piece when Ejection 013\\CR26SACR.MSI detector is located 26" into ductwork. Control rod ejection source term.

Control Rod DA-EE-2001-2 Control room ductwork, long end piece when Ejection 013\\CR26LACR.MSI detector is located 26" into ductwork. Control rod ejection source term.

Control Rod DA-EE-2001-3 Area at side of detector, used for both 26" and Ejection 013\\DOACRE.MSI 38" location. Two (2) required to cover both sides of detector. Control rod ejection source term.

Control Rod DA-EE-2001-4 Control room ductwork, short end piece when Ejection 013\\CR38SACR.MSI detector is located 38" into ductwork.

Control room ejection source term Control Rod DA-EE-2001-5 Control room ductwork, long end piece when Ejection 013\\CR38LACR.MSI detector is located 38" into ductwork. Control Room ejection source term.

Control Rod DA-EE-2001-6 Control rod ejection source term. Control Ejection 013\\CAACRE.MSI room shielding run based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Steam Line DA-EE-2001-7 Control room ductwork, short end piece *vhen Break 013\\CRA26SSL.MSI detector is located 26" into ductwork. Steam line break, accident initiated spike source term.

Steam Line DA-EE-2001-8 Control room ductwork, long end piece when Break 013\\CRA26LSL.MSI detector is located 26" into ductwork. Steam line break, accident initiated spike source term.

Steam Line DA-EE-2001-9 Area at side of detector, used for both 26" and Break 013\\CRADOSL.MSI 38" location. Two (2) required to cover both sides of detector. Steam line break, accident initiated spike source term.

Steam Line DA-EE-2001- 0 Control room ductwork, short end piece when Break 013\\CRA38SSL.MSI detector is located 38" into ductwork. Steam line break, accident initiated spike source term.

Steam Line DA-EE-2001-1 Control room ductwork, long end piece when Break 013\\CRA38LSL.MSI detector is located 38" into ductwork. Steam line break, accident initiated source term DA-EE-2001-013 Page 7 of 21 Revision I

Steam Line DA-EE-2001-2 Steam line break, accident initiated source Break 013\\CRACRSL.MSI term. Control room shielding run based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Fuel DA-EE-2001-3 Control room ductwork, short end piece when Handling 013\\CA26SFHC.MSI detector is located 26" into ductwork. Fuel Accident in handling accident in containment source term.

Containment Fuel DA-EE-2001-4 Control room ductwork, long end piece when Handling 013\\CA26LFHC.MS1 detector is located 26" into ductwork. Steam Accident in line break, accident initiated spike source Containment term. Fuel handling accident in containment source term.

Fuel DA-EE-2001-5 Area at side of detector, used for both 26" and Handling 013\\CRADOFHC.MSI 38" location. Two (2) required to cover both Accident in sides of detector. Steam line break, accident Containment initiated spike source term. Fuel handling accident in containment source term.

Fuel DA-EE-2001-6 Control room ductwork, short end piece when Handling 013\\CA38SFHC.MSI detector is located 38" into ductwork. Steam Accident in line break, accident initiated spike source Containment term. Fuel handling accident in containment source term.

Fuel DA-EE-2001-7 Control room ductwork, long end piece when Handling 013\\CA38LFHC.MSI detector is located 38" into ductwork. Steam Accident in line break, accident initiated source term. Fuel Containment handling accident in containment source term.

Fuel DA-EE-2001-8 Fuel handling accident in SFP source term.

Handling 013\\CRACRFHC.MSI Control room shielding run based on cutting Accident in the control room into (4) mirror rectangles Containment and then multiplying by four to determine receptor dose 7.0 Analvsis 7.1 Control Room Dose Rate Limit Determination 7.1.1 Per references 4.2.1, 4.2.2, and 4.2.3, areas that require continuous occupancy are to be designed for a maximum of 5 rem whole body dose. This is further defined as a 30 day weighted average dose rate of less than 15 mrem/hr. The 15 mrem/hr will be considered the analytical dose limit for inside the Control Room. Fifteen (15) mrem/hr times 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> equals 10.8 rem, with occupancy factor the resulting dose will be < 5 rem.

7.2 In Duct Conversion Factor 7.2.1 Radiation Monitors R-45 and R-46 are GM Tube type detectors. Reference 4.3.1 EE-171 design specification describes the requirements for operation of the detection equipment.

DA-EE-2001-013 Page 8 of 21 Revision I

One of the variables in measuring dose rates is the size of the cloud of radioactive gas that envelopes the detector. For a constant concentration of noble gas and radioiodine in air, up to a certain size based on photon energy, the larger the cloud that the detector is immersed in, the greater the exposure and resulting dose rate. The detectors are mounted in the Control Room HVAC air intake duct. This mounting limits the size of the cloud that the detector will be immersed in due to the physical dimensions of the duct work.

Conservatively assuming that the walls of the duct provide 100% shielding from any source outside of the duct, the detector will only be exposed to, and thus measure, the activity imposed on it by a volume of radioactive gas contained within a cylinder measuring 42" diameter by 151 " in length, which is the vertical section in the turbine building, between two 90 degree elbows. For the same concentration and radio-isotopic mix of radioactive gas in a much larger volume the detector would read significantly higher.

The control room more closely approaches a semi-infinite configuration than the control room ductwork; therefore, calculations were required to determine the dose rate differences due to geometry considerations. The conclusion is that, due to the difference in cloud sizes from the semi-infinite cloud geometry, the detector mounted in the duct will not display an adequate exposure rate that reflects the dose rate that an operator in the Control Room would receive, without computational correction.

7.2.2 Calculations were performed to determine the relationship between an in-duct exposure rate indication and a control room dose rate. The initial condition is for a uniform cloud representative of one of our assumed accidents characterized by a release of different isotopes and concentrations of each isotope. The calculation considers the detector exposed to that uniform cloud in the in-duct position, and then exposed to the same cloud in the center of the Control Room, assuming: there is no isolation; no dilution; and the cloud has instantaneously and uniformly filled the Control Room to the assumed accident cloud concentrations, for all accident source noble gas and radiodine isotopes.

7.2.3 R-45 and R-46 exposure rates were determined utilizing the MegaShield shielding code.

Three runs were required per detector location per accident analysis to accurately model the right cylinder geometry of the air intake duct to an assumed accident. The first set of calculations determined the exposure rate response of a detector located approximately 26 inches from the bottom of the vertical run of ductwork exposed to an assumed accident cloud, as shown in reference drawing 4.1. The second set of calculations assumed the detector was located 38" from the bottom of the vertical run. Each location (26" and 38" above the bottom of the vertical run) had a computer run to mimic the duct area below the detector, one to mimic the duct area above the detector, and a third to mimic the area between the detector and the duct wall to the side. The results of each run were in mR/hr assuming geometric build up.

Computer Run Results Summary:

DA-EE-2001-013 Page 9 of 21 Revis8ion 1

Detector at 26?? height Source term Case ID Exposure Rate Desription (mR/hr)

Large Break LOCA DA-EE-2001-9.376E-3 Control room 013\\SHORT26A.MS1 ductwork, short end piece when detector is (Attachment 1) located 26" into ductwork. LBLOCA source term.

Large Break LOCA DA-EE-2001-1.026E-2 Control room 013\\LONG26A.MSI ductwork, long end piece when detector is (Attachment 2) located 26" into ductwork. LBLOCA source term.

Large Break LOCA DA-EE-2001-4.072E-3 Area at side of 013\\DONUTSA.MSI detector, used for both (X 2) 26" and 38" location.

(Attachment 3)

Two (2) required to cover both sides of detector. LBLOCA source term.

Large Break LOCA (26" total) 0.028 Locked Rotor DA-EE-2001-5.356E0 Control room 013\\CRA26SLR.MSI ductwork, short end piece when detector is (Attachment 7) located 26" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-5.953E0 Control room 013\\CR26LALR.MS1 ductwork, long end piece when detector is (Attachment 8) located 26" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-2.305E0 Area at side of 013\\CRCRALR.MSI detector, used for both (X 2) 26" and 38" location.

(Attachment 9)

Two (2) required to cover both sides of detector. Locked rotor source term.

Locked Rotor (26"total) 15.92 Steam Generator Tube DA-EE-2001-8.576E-1 Control room Rupture 013\\CRA26SSG.MS1 ductwork, short end piece when detector is (Attachment 13) located 26" into ductwork. SGTR source term.

DA-EE-2001-013 Page 10 of 21 Revision I

Steam Generator Tube DA-EE-2001-9.537E-1 Control room Rupture 013\\CRA26LSG.MSI ductwork, long end piece when detector is (Attachment 14) located 26" into ductwork. SGTR source term.

Steam Generator Tube DA-EE-2001-3.6901E-1 Area at side of Rupture 013\\CRADOSG.MSI detector, used for both (X 2) 26" and 38" location.

Two (2) required to (Attachment 15) cover both sides of detector. SGTR source term.

SGTR ( 26"total) 2.55 Fuel Handling Accident 1.976E0 Control room in SFP DA-EE-2001-ductwork, short end 013\\CRA26SFFH.MS1 piece when detector is located 26" into (Attachment 19) ductwork. Fuel handling accident source term.

Fuel Handling Accident DA-EE-2001-2.182E0 Control room in SFP 013\\CRA26LFH.MSI ductwork, long end piece when detector is located 26" into (Attachment 20) ductwork. Fuel handling accident source term.

Fuel Handling Accident DA-EE-2001-8.505E-1 Area at side of in SFP 013\\CRADOFH.MS1 detector, used for both (X 2) 26" and 38" location.

Two (2) required to (Attachment 21) cover both sides of detector. Fuel handling accident source term.

Fuel Handling Accident in SFP (26"total) 5.86 Tornado Missile DA-EE-2001-1.447E0 Control room 013\\CRA26STM.MSI ductwork, short end piece when detector is (Attachment 25) located 26" into ductwork. Tornado missile source term.

Tomado Missile DA-EE-2001-1.609E0 Control room 013\\CRA26LTM.MS1 ductwork, long end piece when detector is (Attachment 26) located 26" into ductwork. Tornado missile source term.

DA-EE-2001-013 Page 11 of 21 Revision I

Tornado Missile DA-EE-2001-6.227E-1 Area at side of 013\\CRADOTM.MSI detector, used for both (X 2) 26" and 38" location.

Two (2) required to (Attachment 27) cover both sides of detector. Tornado missile source term.

Tornado Missile (26"total) 4.30 Control Rod Ejection DA-EE-2001-4.325E0 Control room 013\\CR26SACR.MSI ductwork, short end piece when detector is (Attachment 31) located 26" into ductvork. Control rod ejection source term.

Control Rod Ejection DA-EE-2001-Control room 013\\CR26LACR.MSI 4.807E0 ductwork, long end piece when detector is (Attachment 32) located 26" into ductwork. Control rod ejection source term.

Control Rod Ejection DA-EE-2001-Area at side of 013\\DOACRE.MSI 1.862E0 detector, used for both 26" and 38" location.

(Attachment 33)

(X 2)

Two (2) required to cover both sides of detector. Control rod ejection source term.

Control Rod Ejection (26" total) 12.86 Steam Line Break DA-EE-2001-7.972E-2 Control room 013\\CRA26SSL.MSI ductwork, short end piece when detector is located 26" into (Attachment 37) ductwork. Steam line break, accident initiated spike source term.

Steam Line Break DA-EE-2001-8.865E-2 Control room 013\\CRA26LSL.MSI ductwork, long end piece when detector is located 26" into (Attachment 38) ductwork. Steam line break, accident initiated spike source term.

Steam Line Break DA-EE-2001-Area at side of 013\\CRADOSL.MSI 3.430E-2 detector, used for both 26" and 38" location.

(X 2)

Two (2) required to (Attachment 39) cover both sides of detector. Steam line break, accident initiated spike source term.

DA-EE-2001-013 Page 12 of 21 Revision I

Steam Line Break (26" total) 0.237 l

Fuel Handling Accident 2.667E0 Control room in Containment DA-EE-2001-ductwork, short end 013\\CA26SFHC.MSI piece when detector is located 26" into (Attachment 43) ductwork. Fuel handling accident in containment source term.

Fuel Handling Accident DA-EE-2001-2.965E0 Control room in Containment 013\\CA26LFHC.MSI ductwork, long end piece when detector is located 26" into (Attachment 44) ductwork. Fuel handling accident in containment source term.

Fuel Handling Accident DA-EE-2001-1.147E0 Area at side of in Containment 013\\CRADOFHC.MS1 detector, used for both (X 2) 26" and 38" location.

(Attachment 45)

Two (2) required to cover both sides of detector. Fuel handling accident in containment source term.

Fuel Handling Accident in Containment (26" total) 7.93 Detector at 38" height Case Case ID Exposure Rate Description (mR/hr)

Large Break LOCA DA-EE-2001-1.079E-2 Control room 013\\SHORT38A.MSI ductwork, short end piece when detector is (Attachment 4) located 38" into ductwork. LBLOCA source term Large Break LOCA DA-EE-2001-1.329E-2 Control room 013\\LONG38A.MSI ductwork, long end piece when detector is (Attachment 5) located 38" into ductwork. LBLOCA source term.

DA-EE-2001-013 Page 13 of 21 Revision I

Large Break LOCA DA-EE-2001-4.072E-3 Area at side of 013\\DONUTSA.MSI detector, used for both (X 2) 26" and 38" location.

Two (2) required to (Attachment 3) cover both sides of detector. LBLOCA source term.

Large Break LOCA (38" total) 0.032 Locked Rotor DA-EE-2001-6.176E0 Control room 013\\CRA38SLR.MSI ductwork, short end piece when detector is (Attachment 10) located 38" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-7.624E0 Control room 013\\CRA38LLR.MSI ductwork, long end piece when detector is (Attachment 11) located 38" into ductwork. Locked rotor source term.

Locked Rotor DA-EE-2001-2.305E0 Area at side of 013\\CRCRALR.MSI detector, used for both (X 2) 26" and 38" location.

Two (2) required to (Attachment 9) cover both sides of detector. Locked rotor source term.

Locked Rotor (38" total) 18.41 Steam Generator Tube DA-EE-2001-9.890E-1 Control room Rupture 013\\CRA38SSG.MSI ductwork, short end piece when detector is (Attachment 16) located 38" into ductwork. SGTR source term Steam Generator Tube DA-EE-2001-1.221E0 Control room Rupture 013\\CRA38LSG.MSI ductwork, long end piece when detector is (Attachment 17) located 38" into ductwork. SGTR source term.

Steam Generator Tube DA-EE-2001-3.690E-1 Area at side of Rupture 013\\CRADOSG.MSI detector, used for both (X 2) 26" and 38" location.

(Attachment 15)

Two (2) required to cover both sides of detector. SGTR source term.

SGTR (38" total) 2.95 DA-EE-2001-013 Page 14 of 21 Revis~ion 1

Fuel Handling DA-EE-2001-Control room Accident in SFP 013\\CRA38SFH.MSI ductwork, short end 2.279E0 piece when detector is located 38" into (Attachment 22) ductwork. Fuel handling accident source term Fuel Handling DA-EE-2001-Control room Accident in SFP 013\\CRA38LFH.MSI 2.814E0 ductwork, long end piece when detector is located 38" into (Attachment 23) ductwork. Fuel handling accident source term.

Fuel Handling DA-EE-2001-8.505E-1 Area at side of Accident in SFP 013\\CRADOFH.MS1 detector, used for both (X 2) 26" and 38" location.

(Attachment 21)

Two (2) required to cover both sides of detector. Fuel handling accident source term.

Fuel Handling Accident in SFP (38" total) 6.80 Tornado Missile DA-EE-2001-1.669E0 Control room 013\\CRA38STM.MSI ductwork, short end piece when detector is (Attachment 28) located 38" into ductwork. Tornado missile source term.

Tornado Missile DA-EE-2001-Control room 013\\CRA38LLR.MSI 2.060E0 ductwork, long end piece when detector is (Attachment 29) located 38" into ductwork. Tornado missile source term.

Tornado Missile DA-EE-2001-6.227E-1 Area at side of 013\\CRADOTM.MSI detector, used for both (X 2) 26" and 38" location.

(Attachment 27)

Two (2) required to cover both sides of detector. Tornado missile source term.

Tornado Missile (38" total) 4.97 Control Rod Ejection DA-EE-2001-Control room 013\\CR38SACR.MS1 4.987E0 ductwork, short end piece when detector is (Attachment 34) located 38" into ductwork. Control room ejection source term DA-EE-2001-013 Page 15 of 21 Revision I

Control Rod Ejection DA-EE-2001-Control room 013\\CR38LACR.MSI 6.157E0 ductwork, long end piece when detector is located 38" into (Attachment 35) ductwork. Control Room ejection source term.

Control Rod Ejection DA-EE-2001-Area at side of 013\\DOACRE.MS1 1.862E0 detector, used for both 26" and 38" location.

(Attachment 33)

(X 2)

Two (2) required to cover both sides of detector. Control rod ejection source term.

CRE (38" total) 14.87 Steam Line Break DA-EE-2001-9.193E-2 Control room 013\\CRA38SSL.MSI ductwork, short end piece when detector is located 38" into (Attachment 40) ductwork. Steam line break, accident initiated spike source term.

Steam Line Break DA-EE-2001-1.135E-1 Control room 013\\CRA38LSL ductwork, long end piece when detector is (Attachment 41) located 38" into ductwork. Steam line break, accident initiated source term Steam Line Break DA-EE-2001-Area at side of 013\\CRADOSL.MS I 3.430E-2 detector, used for both 26" and 38" location.

(X 2)

Two (2) required to (Attachment 39) cover both sides of detector. Steam line break, accident initiated spike source term.

Steam Line Break, (38" total) 0.274 Fuel Handling DA-EE-2001-Control room Accident in 013\\CA38SFHC.MS1 ductwork, short end Containment 3.075E0 piece when detector is (Attachment 46) located 38" into ductwork. Fuel handling accident in containment source term DA-EE-2001-013 Page 16 of 21 Revision 1,

Fuel Handling DA-EE-2001-Control room Accident in 013\\CA38LFHC.MSI 3.797E0 ductwork, long end Containment piece when detector is located 38" into (Attachment 47) ductwvork. Fuel handling accident in containment source term.

Fuel Handling DA-EE-2001-1.147E0 Area at side of Accident in 013\\CRADOFHC.MSI detector, used for both Containment (X 2) 26" and 38" location.

Two (2) required to (Attachment 45) cover both sides of detector. Fuel handling accident in containment source term.

Fuel Handling Accident in Containment (38" total) 9.17 The control room dose rate was also determined using MegaShield. The calculation for the control room assumed the detector was located in the center of the room at an elevation equal to the height of reference man (ICRP #23). The results of the computer runs are in mremlhr or dose equivalent.

Detector in Control Room Model Case Case ID Dose Equivalent Description Rate Rate (mrem/lr)

Large Break LOCA DA-EE-2001-LBLOCA source term.

013\\CONTROLR.MSI (1.083E-1)(4) = 0.43 Control room shielding run based on cutting the (Attachment 6) control room into (4) mirror rectangles and then multiplying by four to determine receptor dose.

Steam Generator Tube DA-EE-2001-SGTR source term.

Rupture 013\\CRACRSG.MSI Control room shielding (1.035E+1)(4) 41.4 run based on cutting the control room into (4)

(Attachment 18) mirror rectangles and then multiplying by four to determine receptor dose.

DA-EE-2001-013 Page 17 of 21 Revis8ion 1

Fuel Handling DA-EE-2001-Fuel handling accident Accident in SFP 013\\CRACRFH.MSI in SFP source term.

(2.37E+1)(4) 94.8 Control room shielding run based on cutting the (Attachment 24) control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Tornado Missile DA-EE-2001-Tornado missile 013\\CRACRTM.MSI source term. Control (1.74E+1)(4) = 69.6 room shielding run based on cutting the (Attachment 30) control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Control Rod Ejection DA-EE-2001-Control rod ejection 013\\CAACRE.MSI source term. Control (5.089E+l)(4) = 203.6 room shielding run based on cutting the (Attachment 36) control room into (4) mirror rectangles and then multiplying by four to determine receptor dose Locked Rotor DA-EE-2001-Locked rotor source 013\\CRCRALR.MSI term. Control room (6.309E+1)(4) = 252.4 shielding run based on cutting the control (Attachment 12) room into (4) mirror rectangles and then multiplying by four to determine receptor dose.

Steam Line Break DA-EE-2001-Steam line break, 013\\CRACRSL.MS I accident initiated (9.662E-1)(4) = 3.9 source term. Control room shielding run (Attachment 42) based on cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose DA-EE-2001-013 Page 18 of 21 Revis8ion 1

Fuel Handling DA-EE-2001-Fuel handling accident Accident in 013\\CRACRFHC.MSI in Containment source Containment term. Control room (3.205E+1)(4) = 128.2 shielding run based on (Attachment 48) cutting the control room into (4) mirror rectangles and then multiplying by four to determine receptor dose 7.2.4 For the various assumed accidents and resulting cloud concentrations the 26" and 38" detector values and related control room values are shown in the following table.

Source term 26" exposure 38" exposure Control Room CR/26"ratio CR/38" Analytical rate (mR/hr) rate (mR/hr) dose rate (mremImR) ratio Limit (mremnhr)

(mrem/

(mR/hr) mR)

Large Break 0.028 0.032 0.43 15.4 13.4 0.97 LOCA LR 15.92 18.41 252.4 15.9 13.7 0.94 SGTR 2.55 2.95 41.4 16.2 14.0 0.93 FHA in SFP 5.86 6.80 94.8 16.2 13.9 0.93 Tornado 4.30 4.97 69.6 16.2 14.0 0.93 Missile CRE 12.86 14.87 203.6 15.9 13.7 0.94 SLB 0.237 0.274 3.9 16.5 14.2 0.91 FHA in 7.93 9.17 128.2 16.2 14.0 0.93 Containment Using the control rod ejection (CRE) as an example, the isotopic concentration in the Control Room that would expose control room personnel to 203.6 mrem/hr would equate to exposure rates of 12.86 mR/hr at the 26" and 14.87 mR/hr at the 38" locations.

The ratio of CR dose to in-duct detectors at the 26" and 38" locations is 15.9 mrem/lnR and 13.7 mrem/mR respectively.

The 26" ratio of 15.9 is the more conservative value of the two calculated and will be used. The closer to the end of the cylinder the detector is located, the ratio becomes larger, which is in the conservative direction. Therefore, the 15.9 ratio will be used as the limiting value for any detector installed in the duct as long as it is a minimum of 26" from the end of the duct cylinder. With this assumption, actual duct installation can vary from the 26" and 38" distances and still be enveloped by this calculation, as long as no closer than 26".

This ratio of 15.9 will be linear throughout the measurement range of the radiation DA-EE-2001-013 Page 19 of 21 Revi sion I

monitoring system for CRE. Therefore, it will be considered a constant, such that for any value of mR/hr read in the duct, the control room dose will be determined by multiplying the in-duct value by 15.9. The following sections illustrate this conversion method.

The 30 day weighted average dose rate limit is 15 mremlhr in the Control Room.

Applying the in-duct conversion factor of 15.9 mrem/mR, the in-duct reading equivalent to the 15 mr/hr analytical limit is 15 divided by 15.9 = 0.94 mRlhr. Therefore, the analytical limit for the alarm setpoint as detected in the duct is 0.94 mr/hr. The analytical limits for the remaining accident scenarios is found in the table in section 7.2.4 and range between 0.91 and 0.97 mR/hr.

7.3 Design Basis Accident Cloud Response 7.3.1 The total response time of the system to a step change in the radiation exposure value is 60 seconds, which is the total averaging time of the detector due to the pulse counting algorithm. As an example, the cloud for the CRE analysis would have a concentration of radioactive gas that would result in an in-duct reading of 12.86 mr/hr, as described above. With a 60 second rolling average that is at 0 mr/hr at time zero, and is exposed to a concentration of radioactive gas exhibiting 12.86 mr/hr, it would take 4.4 seconds to reach a reading of 0.94 mr/hr. Similar calculations for the Locked Rotor and Fuel Handling Accidents indicate 3.5 seconds and 9.5 seconds respectively to reach the analytical limit. Given a 10 second delay for damper travel and fan acceleration (Ref.

4.2.5) it is shown that CREATS will actuate within the 60 second assumption for those accidents crediting the radiation monitors.

Two factors make that delay in reaching the analytical limit conservative. First, the transit time for the air to get from the in-duct detector location to the Control Room isolation dampers is greater than 30 seconds, so the cloud will not have reached the Control Room in that time period. Secondly, if the transit time is not considered and it is assumed that the cloud is dumping into the Control Room for the complete 4.4 seconds, that air is diluted into the total Control Room volume, dramatically reducing the cloud concentration and hence effective dose. Mathematically, 4.4 seconds of air at 2,000 cfm is 147 cu. ft., diluted into the CR volume of 36,000 cu. ft. The resulting concentration of noble gas in the CR is approximately 1% of the assumed accident concentration, or less than 2.0 mr/hr actual Control Room dose which is insignificant when compared to the 30 day dose rate of 15 mr/hr.

8.0 Conclusions 8.1 This calculation demonstrates that the analytical limit is between 0.91 and 0.97 mr/hr for the Control Room Radiation Monitors mounted in the duct. These setpoints will envelope all assumed events, except large break LOCA and SLB, that releases airborne radiation that could enter the Control Room via the CR air intake system. Safety injection is credited for actuation of CREATS for these two accidents.

8.2 This analysis also demonstrates that the radiation monitoring system will isolate the DA-EE-2001-013 Page 20 of 21 Revision 1

Control Room for the worst case non-safety injection actuated cloud entering the air intake duct before the cloud can enter the Control Room to a level to cause Control Room dose levels to reach 15 mr/hr.

8.3 Control Room doses were analyzed per Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. Safety Injection is credited with initiating the CREATS emergency mode within the time assumed in the dose analysis for LOCA, SGTR and MSLB accidents.

For other analyzed accidents (CRE, LR and FHA), the radiation monitors are credited with CREATS actuation. As can be seen from the results of this analysis, the monitors would actuate CREATS within the 60 seconds assumed in the control room dose analysis for these accidents. CREATS actuation is not required for GDT Rupture or the Spent Fuel Pool TMA.

DA-EE-200J1-013 Page 21 of 21 Revi sion 1

1 t.,

0 MegaShield 1.2 - Source Input Data Case

Title:

Detector 26', short piece, Alt. Source Term, Control Rod EjechuT) By:

File Name: C:\\DA-EE--1\\CR26SACR.MSI Run Date: 07/27/2004 9:36:32 AM To Reviewed By: L. C.,

ital Run Time:41 seconds Case Model I Source Data Geometby Cylinder-Hrz Radius:

21.00 in Height:

22.72 in Mass:

6.293E+02 gm Volume:

. 3.148E+04, InA3 Material/Density Air &e9' N

Integration Parameters Radial:

50 Circumferential:

50 Axial:

50 Case Data Buildup Region:.

Source Energy Grouping:

Std.

Minimum Energy.

1.000E-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curies mill[Curies uClI/cc l

uCl/gm, Bequerels Bqfcc l

Bq/gm Cs-134 3.508E-06 3.508E-03 6.800E-06 5.574E-03 1.298E+05 2.516E-01 2.062E+02 Cs-136 9.233E-07 9.233E-04 1.790E-06 1.467E-03 3.416E+04 6.623E202 5.429E+01 CsO137 2.017E-06 2.017E-03 3.910E-06 3.205E-03 7.462E+04 1.447E-01 1.186E+02 1-131 1.640E-05 1.640E-02 3.180E-05 2.607E-02 6.069E+05 1.177E+00 9.644E+02 I-132 2.326E-05 j 2.326E-02 4.510E-05 3.6972-02 8.607E+05 1.669E+00 1.368E+03 1-133 3286E-05 3.286E-02 6.370E-05 5.221E-02 1.216E+06 2.357E+00 1.932E+03 1-134 3.585E-05 3.585E-02 6.950E-05 5.697E-02 1.326E+06 2.571 E+00 2.108E+03 1-135 3.064E-05 3.064E-02 5.940E-05 4.869E-02 1.134E+06 2.198E+00 1.801 E+03 Kr-85 6.654E.06 6.654E-03 1.290E-05 1.057E-02 2A62E+05 4.773E-01 3.912E+02 Kr-85m 1.346E-04 1.346E-01 2.610E-04 2.139E-01 4.981E+06 9.657E+00 7.916E+03 Kr-87 2.584E-04 2.584E-01 5.010E-04 4.107E-01 9.562E+06 1.854E+01 1.519E+04 Kr-88 3.647E-04 3.647E-01 7.070E-04 5.795E-01 1.349E+07 2.616E+01 2.144E+04 Rb-86 3.740E-08 3.740E-05 7.250E-08 5.943E-05 1.384E+03 2.683E-03 2.199E+00 Xe-131m 5.777E-06 5.777E-03 1.120E-05 9.180E-03 2.138E+05 4.144E-01 3.397E+02 Xe-133 1.016E-03 1.016E+00 1.970E-03 1.615E+00 3.760E+07 7289E+01 5.975E+04 Xe-133m 3.275E-05 3.275E-02 6.350E-05 5.205E-02 1.212E+06 2.349E+00 1.926E+03 Xe-135 2.646E-04 2.646E-01 5.130E-04 4.205E-01 9.791E+06 1.898E+01 1.556E+04 Xe-135m 1.986E-04 1.986E-01 j

3.850E-04 3.156E-01 7.348E+06 1.425E+01 E 1.168E+04 Xe-138

[8.356E-04 8.356E-01 1.620e-03 1.3282+00n 3.0922+07 5.9942+01 [ 4.9132+04 T otals:

1 ti:

3.zb3F-O3 3.253E+00 6.327E-03 5.186E400 1.207E+08 2.341E402 1.919E+05

MegaShield 1.2 - Shield Input Data Case

Title:

Detector 26', short piece, Alt. Source Term, Control Rod Ejection, File Name: C:\\DA-EE--i\\CR26SACR.MS1 Run Date: 07/27/2004 9:36:32 AM Total Run Time:41 seconds This case has no shields.

19&C411-G

'l Ix/

ChicC

?

0, MegaShield 1.2 - Material Input Data Case

Title:

Detector 26', short piece, Alt. Source Term, Control Rod Ejection, File Name: C:\\DA-EE--1CR26SACR.MS1 Buildup Region: Source Outer Run Date:

07/27/2004 9:36:32 AM Total Run Time:41 seconds Buildup Method: Average Region Composition Density Table All densities in gm/cc I

Material l Source Outer l Gap Air I

1.220E-03 1.220E-03 Totals:

1.220E.03 1.220E-03

I 1

$dcO/

t%,7L

'/

t

~

CY MegaShield 1.2 - Dose Results Case

Title:

Detector 26', short piece, Alt. Source Term, Control Rod Ejection, File Name: C:\\DA-EE--1\\CR26SACR.MS1 Run Date: 07/27/2004 9:36:32 AM Total Run Time:41 seconds Standard Grouping Detector #1:

X = 11.36 in Y = 21.00 in Z = 0.00 in Total Dose Equivalent Rate for AP Exposure in mRemlhr, wlo Buildup: 3.972E+00 with Buildup: 3.983E+OO Flux Fluence Exposure Energy Disintegrations (photons/sq cmlsec)

(MeV/sq cmlsec)

(mRlhr)

(MeV)

(photons/sec) w/o Buildup with Buildup w/o Buildup with Buildup w/o Buildup with Buildup 1.OOOE-01 2.675E+04 8.509E-01 8.635E-01 8.509E-02 8.635E-02

. 1.296E-04 1.315E-04 1.500E-01 6.127E+06 1.951 E+02 1.973E+02 2.926E+01 2.959E+01 4.793E-02 4.847E-02 2.000E-01 1.364E+07 4.347E+02 4.386E+02 8.694E+01 8.773E+01.

1.526E-01 1.540E-01 3.OOOE-01 1.077E+07 3.435E+02 3.458E+02 1.031 E+02 1.038E+02 1.943E-01 1.956E-01 4.000E-01 1.500E+07 4.785E+02 4.811E+02 ^

1.914E+02

1.924E+02 3.707E-01 3.726E-01 5.000E-01 7.824E+06 2.497E+02 2.509E+02 1.249E+02 1.254E+02 2.432E-01 2.443E-01 6.000E-01 2.507E+06 8.004E+01 8.036E+01

-4.803E+01 4.821E+01 9.315E-02 9.352E-02 8.000E-01 6.560E+06 2.096E+02 2.102E+02 1.677E+02 1.682E+02 3.174E-01 3.184E-01 1.OOOE+00 4.686E+06 1.497E+02 1.502E+02 1.497E+02 1.502E+02 2.741E-01 2.748E-01 1.500E+00 3.885E+06 1.242E+02 1.245E+02 1.863E+02 1.867E+02 3.115E-01 3.121E-01 2.OOOE+00 2.155E+07 6.895E+02 6.906E+02 1.379E+03 1.381E+03 2.121E+00 2.124E+00 3.000E+00 1.441E+06 4.612E+01 4.618E+01 1.384E+02 1.385E+02 1.866E-01 1.869E-01 I otais:

V.4UJL+U7 3.UUzL+U3 3.017E+U3 2.605E+03 2.612E+03 4.312E+00 4.325E+00

" " `7 1

/M4e-//kL g -? -

/, S Y MegaShield 1.2 - Source Input Data Case

Title:

26', long piece, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR26LACR.MS1 Run Date:

07/26/2004 3:24:32 PM Total Run Time:41 seconds Run By:

Reviewed By:

L-C.RP Source Data Geometry.

-Cylinder-Hrz Radius:

21.00 in Height:

121.72 in Mass:

3.371E+03 gm Volume:

-1.686E+05 inA3 Material/Density.

Air 4-0OA1 Integration Parameters Radial:

50 Circumferential:

50 Axial:

50 Case Data Buildup Region:

Source Energy Grouping:

Std.

Minimum Energy.

1.000E-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curles milliCuries 1 uCUcc ucl/gm 1 Bequerels Bq/cc Bq/gm Cs-134 1.879E-05 1.879E-02 l

6.800E-06 5.574E-03 6.953E+05 2.516E-01 2.062E+02 Cs-136 4.947E-06 4.947E-03 1.790E-06 1.467E-03 1.830E+05 6.623E-02 5.429E+01 Cs-137 1.081E-05 1.081 E-02 j

3.91 0E-06 3.205E-03 3.998E+05 1.447E-01 1.186E+02 1-131 8.788E-05 8.788E-02 3.18OE-05 2.607E-02 3.251E+06 1.177E+00 9.644E+02 1-132 1.246E-04 1.246E-01 4.510E-05 3.697E-02 4.611 E+06 l

1.669E+00 1.368E+03 1-133 1.760E-04 1.760E-01 6.370E-05 5.221 E-02 6.513E+06 2.357E+00 1.932E+03 1-134 1.921 E-04 1.921E-01 6.950E-05 5.697E-02 7.106E+06 2.572E+00 2.108E+03 1-135 1.641 E-04 1.641 E-01 5.940E-05 4.869E-02 6.074E+06 2.198E+00 1.801E+03 Kr-85 3.565E-05 3.565E-02 1.290E-05 1.057E-02 1.319E+06 4.773E-01 3.912E+02 Kr-85m 7.213E-04 7.213E-01 2.610E-04 2.139E-01 2.669E+07 9.657E+00 7.916E+03 Kr-87 1.384E-03 1.384E+00 l_5.01OE-04 4.107E-01 5.123E+07 1.854E+01 1.519E+04 Kr-88 1.954E-03 1.954E+00 7.070E-04 5.795E-01 7.229E+07 2.616E+01 2.144E+04 Rb-86 2.004E-07 2.004E-04 7.250E-08 5.943E-05 7A13E+03 2.683E-03 2.199E+00 Xe-131m 3.095E-05 3.095E-02 1.120E-05 9.180E-03 1.145E+06 4.144E-01 3.397E+02 Xe-133 5.444E-03 5.444E+00 1.970E-03 1.615E+00 2.014E+08 7.289E+01 5.975E+04 Xe-133m 1.755E-04 1.755E-01 6.350E-05 5.205E-02 6.493E+06 2.350E+00 1.926E+03 Xe-135 1A18E-03 1.418E+00 5.130E-04 4.205E-01 5.245E+07 1.898E+01 1.556E+04 Xe-135m 1.064E-03 1.064E+00 3.850E-04 3.156E-01 3.937E+07

1A24E+01 1.168E+04 Xe-138

. l 4.477E-03 [ 4.477E+00 j 1.620E-03 1.328E+00 l

1.656E+08 5.994E+01 l4.913E+04 T otals:

ots:

1.74UL-02 1.748E+01.-

6.327E-03 5.186E+00 6.469E+08 2.341 E+02 1.919E+05

4so MegaShield 1.2 - Shield Input Data Case

Title:

26', long piece, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR26LACR.MS1 Run Date: 07/26/2004 3:24:32 PM Total Run Time:41 seconds This case has no shields.

Meahil C X,

1.

/

Matria, npt ata MegaShield 1.2 - Material Input Data Case

Title:

26', long piece, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR26LACR.MS1 Run Date: 07/26/2004 3:24:32 PM Total Run Time:41 seconds Buildup Region: Source Outer Buildup Method: Average Region Composition Density Table All densities in gm/cc I

Material

@ Source Outer I Gap Air I

1.220E-03 1.220E-03 Totals:

1.220E-03 1.220E.03

MegaShield 1.2 - Dose Results Case

Title:

26', long piece, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR26LACR.MS1 Run Date: 07/26/2004 3:24:32 PM Total Run Time:41 seconds Standard Grouping Detector #1:

X = 64.14 in Y = 21.00 in Z = 0.00 In Total Dose Equivalent Rate for AP Exposure In mRem/hr, w/o Buildup: 4.400E+OO with Buildup: 4.427E+OO Flux Fluence Exposure Energy Disintegrations (photons/sq cm/sec)

(MeV/sq cm/sec)

(mR/hr)

(MeV)

(photons/sec) w/o Buildup with Buildup w/o Buildup with Buildup w/o Buildup with Buildup 1.OOOE-01 1.A33E+05 9.378E-01 9.673E-01

-,9.378E-02 9.673E-02

,,1.A28E-04 1.A73E-04 1.50E-01 3.282E+07 2.152E+02 2.203E+02 3.228E+01 3.305E+01 5.288E-02 5.413E-02 2.OOOE-01 7.310E+07 4.799E+02 4.891E+02 9.598E+01 9.783E+01 1.685E-01 1.717E-01 3.O0OE-01 5.772E+07 3.796E+02 3.850E+02 1.139E+02 1.155E+02 2.148E-01 2.178E-O1 4.OOOE-01 8.036E+07 5.292E+02 5.351 E+02

.,2.117E+02 2.140E+02 4.099E-01 4.145E-01 5.OOOE-01 4.192E+07 2.763E+02 2.789E+02 1.381 E+02 1.394E+02 2.691E-01 2.716E-01 6.OOE-01 1.343E+07 8.858E+01 8.931E+01

5.315E+01 5.359E+01 1.031E-01 1.039E-01 8.000E-01 3.515E+07 2.321 E+02 2.336E+02 1.857E+02 1.869E+02 3.514E-01 3.538E-01 1.OOOE+00 2.51 0E+07 1.659E+02 1.668E+02.

1.659E+02 1.668E+02 3.036E-01 3.053E-01 1.500E+00 2.081 E+07 1.377E+02 1.383E+02 2.065E+02 2.074E+02 3.452E-01 3.467E-01 2.OOOE+00 1.155E+08 7.646E+02 7.672E+02 1.529E+03 1.534E+03 2.352E+00 2.360E+OO 3.OOOE+00 7.721 E+06 5.117E+01 5.130E+01 1.535E+02 1.539E+02 2.071E-01 2.076E-01 Totals:

5.037E+08 3.321E+03 3.356E+03 2.886E+03 2.903E+03 4.778E+00 4.807E+oo

-.

I x111e4%'j A,-??

194'
e

/ '7s5~

MegaShield 1.2 - Source Input Data Case

Title:

Control room donut (2 required) for 26' or 38', Alt. Source terrntI;Blpol Rod Ejection 4 L.

File Name: C:\\DA-EE--1\\DOACRE.MS1 Run Dlat:- 07t27/2004 9:29:22 AM Reviewed By: L. C. 9, Total Run Time:38 seconds Case Model i..

-- Source Data Geometry.

Rectangle,-.

Length:

21.00 in Width:

3.20 in Height:

42.00 In Mass:

5.643E+01 gm Volume:

2.822E+03 InA3 MateriaVlDensity:'

Air

/.'; Ct-3 Integration Parameters Length:

50 Width:

50 Height:

50 Case Data Buildup Region:

Source Energy Grouping:

Std.

Minimum Energy 1.000E-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curies milliCurles l

uCi/cc ucCUgm Bequerels Bqtcc Bqlgm Cs-134 3.145E207 3.145E-04 6.800E-06 5.574E-03 1.164E+04 2.516E-01 2.062E+02 Cs-136 8.279E-08 8.279E-05 1.790E-06 1.467E-03 3.063E+03 6.623E-02 5.429E+01 Cs-137 1.808E-07 1.808E-04 J 3.910E-06 3.205E-03 6.691E+03 1.447E-01 1.186E+02 1-131 l.471 E-06 1.471 E-03 3.180E-05 2.607E-02 5.442E+04 1.177E+00 9.644E+02 1-132 2.086E-06 2.086E-03 4.510E-05 3.697E-02 7.718E+04 1 1.669E+00 1.368E+03 1-133 2.946E206 2.946E-03 6.370E-05 5.221 E-02 1.090E+05 2.357E+00 1.932E+03 1-134 3.214E-06 3.214E-03 6.950E-05 5.697E-02 1.189E+05 2.571E+00 2.108E+03 1-135 2.747E-06 2.747E-03 5.940E-05 4.869E-02 1.017E+05 2.198E+00 1.801E+03 Kr-85 5.966E-07 5.966E-04 1.290E-05 1.057E-02 2.208E+04 4.773E-01 3.912E+02 Kr-85m 1.207E-05 1.207E-02 2.610E-04 2.139E-01 4.466E+05 9.657E+00 7.916E+03 Kr-87 2.317E-05 2.317E-02 5.010E-04 4.107E-01 8.574E+05 1.854E+01 1.519E+04 Kr-88 3.270E-05 3.270E-02 7.070E-04 5.795E-01 1.210E+06 2.616E+01 2.144E+04 Rb-86 3.353E.09 3.353E-06 7.250E-08 5.943E-05 1.241E+02 2.683E-03 2.199E+00 Xe-131m 5.180E-07 5.180E-04 1.120E-05 9.180E-03 1.917E+04 4.144E-01 3.397E+02 Xe-133 9.111E-05 9.111E-02 1.970E-03 1.615E+00 l

3.371E+06 7.289E+01 5.975E+04 Xe-133m 2.937E-06 2.937E-03 6.350E-05 5205E-02 1.087E+05 2.350E+00 1.926E+03 Xe-135 2.373E-05 2.373E-02 5.130E-04 4205E-01 8.779E+05 1.898E+01 1.556E+04 Xe-135m 1.781E-05 1.781E-02 3.850E-04 3.156E-01 I 6.588E+05 j

1.425E+01 1.168E+04 Xe-138 7.A93-05 7.4932-02 1.6202-03 1.3282+00 2.7722+06 5.9942+01

[

4.9132+04 Totals:.

2.926E-04 2.926E-01 6.327E 03 s.186E+Oo 1.083E+07 2.341E+02 1.919E-+05

MegaShield 1.2 - Shield Input Data Case

Title:

Control room donut (2 required) for 26' or 38', Alt. Source term, Control Rod Ejection File Name: C:\\DA-EE--1\\DOACRE.MS1 Run Date: 07/27/2004 9:29:22 AM Total Run Time:38 seconds This case has no shields.

• 97e X nc&

3n, f MegaShield 1.2 - Material Input Data Case

Title:

Control room donut (2 required) for 26' or 38', Alt. Source term, Control Rod Ejection File Name: C:\\DA-EE--1\\DOACRE.MS1 Buildup Region: Source Outer Run Date: 07/27/2004 9:29:22 AM Total Run Time:38 seconds Buildup Method: Average Region Composition Density Table All densities in gm/cc Material Source Outer Gap Air 1.220E-03 1

.220E-03 Totals:

1.220E-03 1.220E103

/t11

, /,.- 1 4 3 3 j /0, 4

4 /

MegaShield 1.2 - Dose Results Case

Title:

Control room donut (2 required) for 26' or 38', Alt. Source term, Control Rod Ejection File Name: C:\\DA-EE--1\\DOACRE.MS1 Run Date: 07127/2004 9:29:22 AM Total Run Time:38 seconds Standard Grouping Detector #1:

X = 10.50 In Y = 21.00 in Z = 0.00 In Toal Dose Equi lent Rate for AP Exposure in mRemlhr, wlo Builduo: 1.713E+OO with Buildup: 1.715 E+OO Flux Fluence Exposure Energy Disintegrations (photonslsq cmlsec)

(MeV/sq cmnsec)

(mRlhr)

(MeV)

(photonslsec) w/o Buildup with Buildup w/o Buildup with Buildup wlo Buildup with Buildup 1.OOOE.01 2.399E+03 3.680E-01 3.701E-01

.:3.680E-02 3.701 E-02 5.603E-05 5.636E-05 1.500E-O1 5.494E+05 8.431E+O1 8.468E+01 1.265E+01 1.270E+01 2.071 E-02 2.080E-02 2.OOOE-01 1.223E+06 1.878E+02 1.885E+02 3.756E+01 3.769E+01 6.593E-02 6.616E-02 3.000E-01 9.661 E+05 1.483E+02 1.487E+02 4.450E+01 4.462E+01 8.392E-02 8.413E-02 4.OOOE-01 1.345E+06 2.066E+02 2.070E+02 :

,8.262E+01 8.279E+01 1.600E-01 1.603E-01 5.000E-01 7.015E+05 1.078E+02 1.080E+02 5.388E+01 5.398E+01 1.050E-01 1.051E-01 6.000E-01 2.248E+05 3.453E+01 3.459E+01 2.072E+01 2.075E+01 4.019E-02 4.025E-02 8.OOOE-01 5.882E+05 9.039E+01 9.050E+01 7.231E+01 7.240E+01 1.369E-01 1.370E-01 1.OOOE+00 4.202E+05 6.457E+01 6.464E+01 6.457E+01 6.464E+01 1.182E-01 1.183E-01 1.500E+00 3.483E+05 5.355E+01 5.359E+01 8.032E+01 8.038E+01 1.342E-01 1.344E-01 2.OOOE+00 1.933E+06 2.971 E+02 2.973E+02 5.943E+02 5.947E+02 9.140E-01 9.145E-01 3.OOOE+00 1.292E+05 1.987E+01 1.988E+01 5.961E+01 5.964E+01 8.041 E-02 8.045E-02 Totals:

8.431E+06 1.295E+03 1.298E+03 1.123E+03 1.124E+03 1.859E+00 1.862E+OO v

14111CA K3

'e' 1.F

/ /O 5c / O f ~y MegaShield 1.2 - Source Input Data Case

Title:

38', short piece, alt. source term, Control Rod ejection File Name: C:\\DA-EE--1\\CR38SACR.MS1 Run Date: 07/26/2004 3:07:02 PM Total Run Time:40 seconds Run By:

R7 /

Reviewed By:

L C 2,

• Case Model U

Source Data Geometry.

Cylinder-Hrz Radius:

21.00 in Height:

34.72 in Mass:

9.617E+02 gm Volume:

4.810E+04 inA3 MateriaUDensityr Air o e 0

Integration Parameters Radial:

50 Circumferential:

50 Axial:

50 Case Data Buildup Region:

Source Energy Grouping:

Std.

Minimum Energy:

1.000E-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curies milliCurles uCilcc uCi/gm Bequerels Bqfcc Bq/gm Cs-134 5.360E-06 5.360E-03 6.800E-06 5.574E-03 1.983E+05 2.516E-01 2.062E+02 Cs-136 1.411E-06 1.411E-03 1.790E-06 1.467E-03 5.221E+04 6.623E-02 5.429E+01 Cs-137 3.082E-06 3.082E-03 3.910E-06 3205E-03

[

1.140E+05 1.447E-01 1.186E+02 1-131 2.507E-05 2.507E-02 3.180E-05 2.607E-02 9.275E+05 I 1.177E+00 9.644E+02 1-132 3.555E-05 3.555E-02 4.510E-05 3.697E-02 1.315E+06 1.669E+00 1.368E+03 1-133 5.021E-05 5.021 E-02 6.370E-05 5.221E-02 1.858E+06 2.357E+00 1.932E+03 1-134 5.478E-05 5.478E-02 6.950E-05 5.697E-02 2.027E+06 2.572E+00 2.108E+03 1-135 4.682E.05 4.682E-02 5.940E-05 4.869E-02 1.732E+06 2.198E+00 1.801 E+03 Kr-85 1.017E-05 1.017E-02 1.290E-05 1.0572-02 3.762E+05 4.773E-01 3.912E+02 Kr-85m 2.057E-04 2.057E-01 2.61 OE-04 2.139E-01 I 7.612E+06 9.657E+00 7.916E+03 Kr-87 3.949E-04 3.949E-01 5.010E-04 4.107E-01 l

1.461E+07 1.854E+01 1.519E+04 Kr-88 5.573E-04 5.573E-01 7.070E-04 I

5.795E-01 2.062E+07 2.616E+01 2.144E+04 Rb-86 5.715E-08 5.715E-05 7.250E-08 5.943E-05 2.115E+03 2.683E-03 2.199E+00 Xe-131m 8.829E-06 8.829E-03 1.120E-05 9.180E-03 3.267E+05 4.144E-01 3.397E+02 Xe-133 1.553E-03 1.553E+00 1.970E-03 1.615E+00 5.746E+07 7.289E+01 5.975E+04 Xe-133m 5.005E-05 5.005E-02 6.350E-05 5.205E-02 1.852E+06 2.349E+00 1.926E+03 Xe-135 4.044E-04 4.044E-01 5.130E-04 4.205E-01 1.A96E+07 1.898E+01 1.556E+04 Xe-135m 3.035E-04 3.035E-01 3.850E-04 3.156E-01 1.123E+07 1.425E+01 1.168E+04 Xe-138 1.277E-03 1.277E+00 1.620E-03 1.328E+00 4.725E+07 l

5.994E+01 4.913E+04 T otals:

Coas

.UBIL-03 4.VU7L400 6.327E=-03 5.1 86E+00 I1.845E+08 2.341 E+02 1.91 9E+05

."'/

'E

/B ex

.-f y C

MegaShield 1.2 - Shield Input Data Case

Title:

38', short piece, alt. source term, Control Rod ejection File Name: C:\\DA-EE--1\\CR38SACR.MS1 Run Date: 07/26/2004 3:07:02 PM Total Run Time:40 seconds This case has no shields.

k I

A'4'/c4./ #yy c D f MegaShield 1.2 - Material Input Data Case

Title:

File Name:

Run Date:

38', short piece, alt. source term, Control Rod ejection C:XDA-EE--1\\CR38SACR.MS1 07/26/2004 3:07:02 PM Total Run Time:40 seconds Buildup Region: Source Outer Buildup Method: Average Region Composition Density Table All densities in gm/cc I

Material I Source Outer I Gap Air I 1.220E-03 I

1.220E-03 Totals:

1.220E-03 1.220E-03

MegaShield 1.2 - Dose Results Case

Title:

38', short piece, alt. source term, Control Rod ejection File Name: C:\\DA-EE--1\\CR38SACR.MSI Run Date: 07/26/2004 3:07:02 PM Total Run Time:40 seconds Standard Grouping Detector #1:

X = 17.36 in Y = 21.00 in Z = 0.00 in Total Dose Equivalent Rate for AP Exposure in mRem/hr, wlo Build

4.578E+D0 with Buildup: 4.593 E+00 Flux Fluence Exposure Energy Disintegrations (photons/sq cm/sec)

(MeVisq cm/sec)

(mR/hr)

(MeV)

(ptonsiec) w/o Buildup with Buildup w/o Buildup with Buildup w/o Buildup with Buildup 1.000E-01 4.088E+04 9.800E-01 9.968E-01

- 9.800E-02 9.968E-02 1.492E-04 1.518E-04 1.500E-01 9.363E+06 2.247E+02 2.276E+02 3.371E+01 3.414E+01 5.521 E-02 5.592E-02 2.OOOE-01 2.085E+07 5.008E+02 5.060E+02 1.002E+02 1.012E+02

1.758E-01 1.776E-01 3.OOOE-01 1.646E+07 3.958E+02 3.989E+02 1.187E+02 1.197E+02 2.239E-01 2.256E-01 4.OOOE-01

.2.292E+07 5.514E+02

.5.548E+02 2.206E+02 2.219E+02 4.271 E-01 4.297E-01 5.OOOE-01 1.196E+07 2.878E+02 2.893E+02 1.439E+02 1.446E+02 2.803E-01 2.817E-41 6.OOOE-01 3.831E+06 9.224E+01 9.266E+01 5.534E+01 5.559E+01 1.074E-01 1.078E-01 8.OOOE-01 1.003E+07 2.415E+02 2.424E+02 1.932E+02 1.939E+02 3.658E-01 3.671 E-01 1.OOOE+00 7.161E+06 1.726E+02 1.731E+02 1.726E+02 1.731E+02 3.159E-01 3.169E-01 1.500E+00 5.937E+06 1.432E+02 1.435E+02 2.148E+02 2.153E+02 3.590E-01 3.598E-01 2.00E+00 3.294E+07 7.948E+02 7.963E+02 1.590E+03 1.593E+03 2.445E+00 2.449E+00 3.OOOE+00 2.202E+06 5.317E+01 5.324E+01 1.595E+02 1.597E+02 2.152E-01 2.155E-01 Totals:

1.437E+08 3.459E+03 3.479E+03 3.002E+03 3.012E+03 4.970E+00 4.987E+00

Af1tt4./

/ 0 f 'I MegaShield 1.2 - Source Input Data Case

Title:

38', long piece, alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR38LACR.MS1 Run Date: 07/26/2004 2:51:46 PM Total Run Time:41 seconds Run By:

4J J, *

.LL rwu _

Reviewed By:

L. C, R Case Model Source Data Geometry:

Cylinder-Hrz

.7 Radius:

21.00 in Height 109.72 In Mass:

3.039E+03 gm Volume:

1.520E+05 inA3 Material/Density:

Air 'e8 1

Integration Parameters Radial:

50 Circumferential:

50 Axial:

50 Case Data Buildup Region:.

Source Energy Grouping:

Std.

Minimum Energy.

1.000E-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curles milliCurles uClcc ucl/gm Bequerels Bq/cc Bq/gm Cs-134 1.694E-05 1.694E-02 6.800E-06 5.574E-03 6.267E+05 2.516E-01 2.062E+02 Cs-136 4.459E-06 4.459E-03 1.790E-06 1.467E-03 1.650E+05 6.623E-02 5.429E+01 Cs-137 9.740E-06 9.740E-03 3.910E-06 3.205E-03 3.604E+05 j

1.447E-01 1.186E+02 1-131 7.921 E-05 7.921E-02 3.1BOE-05 2.607E-02 2.931 E+06 1.177E+00 9.644E+02 1-132 1.123E-04 1.123E-01 4.510E-05 3.697E-02 4.157E+06 1.669E+00 1.368E+03 1-133 1.587E-04 1.587E-01 6.370E-05 5.221 E-02 5.871 E+06 2.357E+00 1.932E+03 1-134 1.731E-01 6.950E-05 5.697E-02 6.406E+06 2.572E+00 2.108E+03 1-135 1.480E-04 1.480E-01 5.940E-05 4.869E-02 5.475E+06 2.198E+00 1.801E+03 Kr-85 3.213E-05 3.213E-02 1.290E-05 1.057E-02 1.189E+06 4.773E-01 3.912E+02 Kr-85m 6.502E-04 6.502E-01 2.610E-04 2.139E-01 2.406E+07 9.657E+00 7.916E+03 Kr-87 1.248E-03 1.248E+00 5.01OE-04 4.107E-01 4.618E+07 1.854E+01 1.519E+04 Kr-88 1.761 E-03 1.761 E+00 7.070E-04 5.795E-01 6.516E+07 2.616E+01 2.144E+04 Rb-86 1.806E-07 1.806E-04 7.250E-08 l

5.943E-05 6.682E+03 2.682E-03 2.199E+00 Xe-131m 2.790E-05 2.790E-02 1.120E-05 9.180E-03 1.032E+06 4.144E-01 3.397E+02 Xe-133 4.907E-03

[

4.907E+00 1.970E-03 1.615E+00_l 1.816E+08 7.289E+01 s.g75E+04 Xe-133m 1.582E-04 1.582E-01 6.350E-05 5.205E-02 5.853E+06 2.349E+00 1.926E+03 Xe-135 1.278E-03 1.278E+00 5.130E-04 4.205E-01 4.728E+07 1.898E+01 1.556E+04 Xe-135m 9.590E-04 9.590E-01 3.850E-04 3.156E-01 3.548E+07 1.424E+01 1.168E+04 Xe-138 4.035E-03 4.035E+00 1.620E-03 1.328E+00 1.493E+08 5.994E+01 4.913E+04 Totals:

1.576E-02 1.576E+01 6.327E-03 5.186E+00 5.831E+08 2.341E+02 1.919E+05

MegaShield 1.2 - Shield Input Data Case

Title:

38', long piece, alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR38LACR.MS1 Run Date: 07/26/2004 2:51:46 PM Total Run Time:41 seconds This case has no shields.

d 3 7

o r ?.*Y MegaShield 1.2 - Material Input Data Case

Title:

38', long piece, alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR38LACR.MS1 Buildup Region: Source Outer Run Date: 07/26/2004 2:51:46 PM Total Run Time:41 seconds Buildup Method: Average Region Composition Density Table All densities In gm/cc Material Source Outer Gap l

A l

1.220E-03 l1.220E-03 Totals:

1.220E-03 1.220E.03

/011 CAz ^c f 93,

/)~

4>ee -X MegaShield 1.2 - Dose Results Case

Title:

38', long piece, alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CR38LACR.MS1 Run Date: 07/26/2004 2:51:46 PM Total Run Time:41 seconds Standard Grouping Detector #1:

X = 54.86 in Y = 21.00 in Z = 0.00 in Total Dose E uivalent Rate for AP Exposure in mRem/hr, w/o Buildu :5.642E+OO with Buildup: 5.670E+00 Flux Fluence Exposure Energy Disintegrations (photons/sq cm/sec)

(MeV/sq cm/sec)

(mR/hr)

(MeV)

(photons/sec) w/o Buildup with Buildup w/o Buildup with Buildup w/o Buildup with Buildup 1.OOOE-01 1.292E+05 1.205E+00 1.235E+00 1.205E-01 1.235E-01 1 1.835E-04 1.881 E-04 1.500E-01 2.959E+07 2.764E+02 2.817E+02 4.146E+01 4.225E+01 6.792E-02 6.920E-02 2.OOOE-01 6.589E+07 6.162E+02 6.257E+02 1.232E+02 1.251E+02 2.163E-01 2.197E-01 3.OOOE-01 5.203E+07 4.873E+02 4.928E+02 1.462E+02 1.478E+02 2.757E-01 2.788E-01 4.000E-01 7.243E+07 6.790E+02 6.6522+02

.2.716E+02 2.741 E+02 5.260E-01 5.307E-01 5.OOOE-01 3.778E+07 3.545E+02 3.572E+02 1.772E+02 1.786E+02 3.452E-01 3.479E-01 6.000E-01 1.211E+07 l

1.136E+02 1.144E+02

- 6.818E+01 6.863E+01 1.323E-01

-1.331E-01 8.0002E01 3.168E+07 2.976E+02 2.992E+02 2.381E+02 2.394E+02 4.507E-01 4.531E-01 1.OOOE+00 2.263E+07 2.127E+02 2.137E+02 2.127E+02 2.137E+02 3.893E-01 3.911E-01 1.500E+00 1.876E+07 1.765E+02 1.771E+02 2.648E+02 2.657E+02 4.426E-01 4.441 E-01 2.000E+00 1.041E+08 9.801E+02 9.828E+02 1.960E+03 1.966E+03 3.015E+00 T 3.023E+00 3.000E+00 6.960E+06 6.558E+01 6.571E+01 1.968E+02 1.971E+02 [ 2.654E-01 j

2.659E-01 Totals:

4.541E+08 4.261E+03 4.297E+03 3.701 E+03 3.718E+03 6.126E+00 6.157E+00

/44hCktj f 3, t

' / l.*Y MegaShield 1.2 - Source Input Data Case

Title:

Control Room, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CAACRE.MS1 Run Date: 07/27/2004 10:12:21 AM Total Run Time:41 seconds Run By:

,R. 4.

f Reviewed By: L C. P.

Case Model I.

Source Data Geometry Rectangle Length:

24.40 ft Width:

19.50 ft Height:

19.00 ft Mass:

. 3.123E+05 gm Volume:

9.040E+03 ftA3 MateriaUDenslty.

Air

O00' Integration Parameters Length:

50 Width:

50 Height:

50 Case Data Buildup Region:

Source Energy Grouping:

Std.

Minimum Energy-.

1.0002-01 MeV Minimum %:

0.00 Source Nuclides Nuclide Curies milliCurles uClcc uClgm l

Bequerels Bq/cc Bq/gm Cs-134 1.741 E-03 1.741 E+00 6.800E-06 5.574E-03 6.441 E+07 2.516E-01 2.062E+02 Cs-136 4.582E-04 4.582E-01 1.790E-06 1.467E-03 1.695E+07 6.623E-02 5.429E+01 Cs-137 1.001E-03 1.001E+00 j_3.9102-06 3.205E-03 3.703E+07 1.447E-01 1.186E+02 1-131 8.140E-03 8.140E+00 3.180E-05 2.607E-02 3.012E+08 1.177E+00 9.644E+02 1-132 1.155E-02 1.155E+01 4.510E-05 3.697E-02 4.272E+08 ] 1.669E+00 1.368E+03 1-133 1.631E-02 1.631E+01 6.370E-05 5.221 E-02 6.033E+08 j

2.357E+00 1.932E+03 1-134 1.779E-02 1.779E+01 6.950E-05 5.697E-02 6.583E+08 2.571E+00 2.108E+03 1-135 1.521 E-02 1.521E+01 5.940E-05 4.869E-02 5.626E+08 2.198E+00 1.801 E+03 Kr-85 3.302E-03 3.302E+00 1.290E-05 1.057E-02 1.222E+08 4.773E-01 3.912E+02 Kr-85m 6.681E-02 6.681E+01 2.610E-04 2.139E-01 2.472E+09 9.657E+00 7.916E+03 Kr-87 1.283E-01 1.283E+02 5.010E-04 4.107E-01 4.745E+09 1.854E+01 1.519E+04 Kr-88 1.810E-01 1.810E+02 7.070E-04 5.795E.01 6.696E+09 2.616E+01 2.144E+04 Rb-86 1.856E-05 1.856E-02 7.250E-08 5.943E-05 6.867E+05 2.682E-03 2.199E+00 Xe-131m 2.867E-03 2.867E+00 1.120E-05 9.180E-03 j

1.061E+08 4.144E-01 3.397E+02 Xe-133 5.043E-01 5.043E+02 1.970E-03 1.615E+00 1.866E+10 7.289E+01 5.975E+04 Xe-133m 1.626E-02 1.626E+01 6.350E-05 5.205E-02 j

6.014E+08 2.349E+00 1.926E+03 Xe-135 j

1.313E-01 1.313E+02 5.130E-04 4.205E-01 l

4.859E+09 1.898E+01 1.556E+04 Xe-135m 9.856E.02 I 9.856E+01 3.850E-04 l

3.156E-01 I 3.647E+09 1.424E+01 1.168E+04 Xe-138 4.147E-01 4.147E+02 1.620E-03 1.328E+00 1.534E+10 5.994E+01 [ 4.913E+04 Totals:

1.620E+00 1.620E+03 6.327E-03 5.186E+00 5.992E+10 2.341E+02 1.919E+05

MegaShield 1.2 - Shield Input Data Case

Title:

Control Room, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CAACRE.MS1 Run Date: 07/27/2004 10:12:21 AM Total Run Time:41 seconds This case has no shields.

,'T rs )

Ao MegaShield 1.2 - Material Input Data Case

Title:

Control Room, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CMCRE.MS1 Buildup Region: Source Outer Run Date: 07/27/2004 10:12:21 AM Total Run Time:41 seconds Buildup Method: Average Region Composition Density Table All densities In gm/cc Material I Source Outer I Gap I

Ar 1220E-03 I 1.220E-03 Totals:

1.220E.03 1.220E.03

1I I

2.-'~

4 1111Cgkty His 3t*

'-.Se qd v C MegaShield 1.2 - Dose Results Case

Title:

Control Room, Alt. source term, Control Rod Ejection File Name: C:\\DA-EE--1\\CAACRE.MS1 Run Date:

07/27/2004 10:12:21 AM Total Run Time:41 seconds Standard Grouping Detector #11:

X = 12.20 ft Y = 5.70 ft Z = 0.00 ft Total Dose Equivalent Rate forAP Exposure in mRem/hr, w/o Buildi :5.OOOE+01 with Buildup: 5.089E+01 Flux Fluence Exposure Energy Disintegrations (photons/sq cm/sec)

(MeV/sq cm/sec)

(mR/hr)

(MeV)

(photons/sec) w/o Buildup 1 with Buildup w/o Buildup 1 with Buildup w/o Buildup with Buildup 1.OOOE-01 1.328E+07 1.047E+01 1.143E+01 1.047E+00 1.143E+00

1.594E-03 1.741 E-03 1.5002-01 3.041 E+09 2.411 E+03 2.578E+03 3.617E+02 3.866E+02 5.924E-01 6.333E-01 2.000E-01 6.771E+09 5.389E+03 5.689E+03 1.078E+03

1. 138E+03 1.892E+00.

1.997E+00 3.000E-01 5.347E+09 4.277E+03 4.451E+03 1.283E+03 1.335E+03 2.420E+00 2.518E+00 4.000E-01 7.444E+09 5.975E+03 6.168E+03

.2.390E+03

.2.467E+03 4.628E+00 4.778E+00 5.000E-01 3.883E+09 3.125E+03 3.21 OE+03 1.562E+03 1.605E+03 3.044E+00 3.126E+00 6.000E-01 1.244E+09 1.003E+03 1.027E+03

.-6.019E+02

.6.162E+02 1.168E+00 1.195E+00 8.000E-01 3.256E+09 2.633E+03 2.684E+03 2.107E+03 2.147E+03 3.988E+00 4.064E+00 1.000E+00 2.326E+09 1.885E+03 1.916E+03 -;

1.885E+03 1.916E+03

.3.450E+00 -3.506E+00 1.500E+00 1.928E+09 1.568E+03 1.587E+03 2.353E+03 2.381 E+03 3.932E+00 3.979E+00 2.OOOE+00 1.070E+10 8.722E+03 8.806E+03 1.744E+04 1.761E+04 2.683E+01 2.708E+01 3.000E+00 7.152E+08 5.847E+02 5.888E+02 1.754E+03 I

1.766E+03 2.366E+00 2.3832+00 Toas 4.66e+1_ 0 3 o.75E0 3s~.87 nn1n E~

3es.28E0 3.3E0 5.431E40 5.5Z7E Totals:

4.666E+10 3.75BF=+04 3.BTIE+04 3.282E+04 3.337E+04 5.431F+01 5.527E+01