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License Amendment Request Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function
	ML14247A524
Person / Time
Site:	Peach Bottom
Issue date:	09/03/2014
From:	David Helker; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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ML14247A522	List: ML14247A524;
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10 CFR 50.90 September 3, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

License Amendment Request Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (Exelon) requests amendments to Appendix A, Technical Specifications (TS) of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively.

This submittal requests changes to the PBAPS, Units 2 and 3, TS and associated TS Bases to eliminate the Main Steam Line Radiation Monitor (MSLRM) from initiating: 1) a Reactor Protection System (RPS) automatic reactor scram; and 2) a Primary Containment Isolation System (PCIS) isolation including automatic closure of the Main Steam Line Isolation Valves (MSIVs), Main Steam Line (MSL) drain valves, MSL sample line valves, Residual Heat Removal (RHR) system sample line valves, and Reactor Recirculation loop sample line valves.

Specifically, the proposed TS changes remove requirements for the MSLRM trip function from Table 3.3.1.1-1, "Reactor Protection System Instrumentation," and Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." The requirement for the MSLRM trip function for the Mechanical Vacuum Pump (MVP) will be retained in the Technical Requirements Manual (TRM) in Section 3.13, "Mechanical Vacuum Pump."

The justification for eliminating the MSLRM trip and isolation functions from initiating an automatic reactor scram and automatic closure of the MSIVs is based on the evaluation provided in General Electric's (GE's) Licensing Topical Report (LTR) NED0-31400A, "Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Line Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," dated October 1992.

This LTR was reviewed and approved by the NRC as documented in a letter dated May 15, 1991, in which the NRG indicated that this topical report would be acceptable for referencing by licensees requesting TS changes concerning the elimination of the MSL system high radiation trip functions.

The elimination of the MSLRM high radiation trip and isolation function from initiating an automatic closure of the MSL drain valves, MSL sample lines, RHR system sample lines, and Reactor Recirculation loop sample line valves was not specifically discussed in the LTR (i.e.,

NED0-31400A) analysis, and therefore, additional information is provided in this submittal to further justify these specific proposed TS changes.

U.S. Nuclear Regulatory Commission Elimination of Main Stream Line Radiation Monitor Trip and Isolation Function September 3, 2014 Page2 provides the evaluation of the proposed changes. Attachment 2 provides the marked-up TS pages for the proposed changes. Attachment 3 provides the mark-ups of the supporting TS Bases for information purposes. Attachments 4 and 5 include copies of the supporting calculations (i.e., PM-1057, Revision 5 and PM-1168, Revision O, respectively).

Exelon has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92.

Exelon requests approval of the proposed amendments by September 3, 2015. This schedule is being requested in order to support outage activities for Unit 3 in September 2015. Upon NRG approval, Exelon is planning to implement the amendment for Unit 3 during the 2015 outage and as soon as practicable for Unit 2, but no later than the 2016 Unit 2 refueling outage.

The proposed changes have been reviewed and approved by the station's Plant Operations Review Committee and by the Nuclear Safety Review Board.

Exelon is also notifying the applicable States of this application to amend the TS by transmitting a copy of this letter and supporting attachments to the designated State officials.

There are no regulatory commitments contained within this submittal.

If you have any questions or require additional information, please contact Richard Gropp at (610) 765-5557.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of September 2014.

Respectfully, 9.# 1r~

David P. Helker Manager, Licensing Exelon Generation Company, LLC Attachments: 1. Evaluation of Proposed Changes

2. Proposed Technical Specifications (Proposed Pages)

3. Proposed Technical Specifications Bases (For Information Only)

4. PBAPS Calculation PM-1057, "EAB, LPZ, and CR Doses due to Control Rod Drop Accident (CRDA)," Revision 5

5. PBAPS Calculation PM-1168, "Post-CRDA Release From RCS Sample Line,"

Revision O cc: Regional Administrator - NRG Region I w/ Attachments NRG Senior Resident Inspector - Peach Bottom Atomic Power Station NRG Project Manager, NRA - Peach Bottom Atomic Power Station II S. T. Gray, State of Maryland R.R. Janati, Commonwealth of Pennsylvania

ATTACHMENT 1 License Amendment Request Peach Bottom Atomic Power Station, Units 2 and 3 Docket Nos. 50-277 and 50-278 EVALUATION OF PROPOSED CHANGES Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip and Isolation Functions 1.0

SUMMARY

DESCRIPTION

2.0 BACKGROUND

3.0 DETAILED DESCRIPTION

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

5.1 Applicable Regulatory Requirements/Criteria 5.2 Precedent 5.3 No Significant Hazards Consideration 5.4 Conclusion

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 1of22 1.0

SUMMARY

DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (Exelon) requests an amendment to Appendix A, Technical Specifications (TS) of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, respectively.

The proposed changes eliminate the Main Steam Line Radiation Monitor (MSLRM) from initiating: 1) a Reactor Protection System (RPS) automatic reactor scram; and 2) a Primary Containment Isolation System (PCIS) isolation including automatic closure of the Main Steam Line Isolation Valves (MSIVs), Main Steam Line (MSL) drain valves, MSL sample line valves, Residual Heat Removal (AHR) system sample line valves, and Reactor Recirculation loop sample line valves. Specifically, the proposed TS changes remove requirements for the MSLRM trip function from Table 3.3.1.1-1, "Reactor Protection System Instrumentation," and Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation."

The requirements for the MSLRM trip function for the Mechanical Vacuum Pump (MVP) will be retained in Section 3.13, "Mechanical Vacuum Pump," of the Technical Requirements Manual (TAM) and supporting TAM Bases.

The justification for eliminating the MSLRM trip and isolation functions from initiating an automatic reactor scram and automatic closure of the MSIVs is based on the evaluation provided in General Electric's (GE's) Licensing Topical Report (LTR) NED0-31400A, "Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Line Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," dated October 1992 (Reference 1). This LTR was reviewed and approved by the NRC as documented in a letter dated May 15, 1991 (Reference 2), in which the NRC indicated that this topical report would be acceptable for referencing by licensees requesting TS changes concerning the elimination of the MSL system high radiation trip functions.

The elimination of the MSLRM high radiation isolation function from initiating an automatic closure of the MSL drain valves, MSL sample line valves, AHR system sample line valves, and Reactor Recirculation loop sample line valves was not specifically addressed in the LTR (i.e.,

NED0-31400A) analysis, and therefore, additional information is provided in this submittal to further justify these specific proposed TS changes.

Eliminating these reactor trip and isolation functions of the MSLs improve the availability of the Main Condenser for removal of decay heat and aids in eliminating inadvertent reactor trips.

In addition, the requirement for maintaining the MSLRM trip function is not included in the Improved Standard TS (i.e., NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric Plants, BWR/4, "April 2012) (Reference 3).

The evaluation of the proposed changes provided in this attachment includes a detailed discussion and description of the proposed TS changes, a safety assessment of the proposed

License Amendment Request Attachment 1 Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 2 of 22 TS changes, information supporting a finding of No Significant Hazards Consideration, and information supporting an Environmental Assessment. Attachment 2 provides the marked-up TS pages for the proposed changes. Attachment 3 provides mark-ups of the supporting TS Bases for information purposes. Attachments 4 and 5 include copies of the supporting calculations (i.e., PM-1057, Revision 5 and PM-1168, Revision O, respectively).

2.0 BACKGROUND

Boiling Water Reactors (BWRs) are equipped with radiation monitors which are located on the MSLs downstream of the outboard MSIVs. The MSLRMs provide an early indication of gross fuel failures. The MSLRM will generate a trip and isolation signal on conditions of high radiation in the MSL that are indicative of a Design Basis Accident (OBA) Control Rod Drop Accident

(CADA). The isolation signal will cause a trip and isolation of the MVP, which is used during plant startup and shutdown to maintain a vacuum condition in the Main Condenser, and will close the MSL drains and sample valves. In addition, the reactor coolant sample valves in the main Recirculation System receive a signal to close along with RHR system sample line valves.

Operating data presented in NED0-31400A (Reference 1) indicates that the MSLRMs have initiated eight reactor shutdowns from 1980 through October 1992, but none of the shutdowns were the result of fuel degradation. The shutdowns were the result of instrument failures, chemistry excursions, radiation monitor maintenance errors, and other causes. A number of BWRs within the industry have already submitted licensing actions and received NRC approval to eliminate MSLRM trip and isolation functions from initiating an automatic reactor scram and automatic closure of the MSIVs.

To reduce the potential for unnecessary reactor shutdowns and PCIS isolations caused by spurious actuation of the MSLRM trips, and to increase plant operational flexibility, the BWROG proposed to eliminate the RPS automatic reactor shutdown function and MSIV closure function initiated by the MSLRMs, and provided a supporting safety analysis in LTR NED0-31400A. By letter May 15, 1991 (Reference 2), the NRC documented its review and acceptance of the BWROG LTR NED0-31400A (Reference 1) and determined this topical report is acceptable for referencing in license applications to the extent specified and under the limitations delineated in the report and the NRC's supporting safety evaluation.

Because not all BWRs have the MVP trip and sample valve isolations on the MSLRM high radiation signal, the BWROG LTR did not address these specific isolations. In addition, the LTR did not include an analysis for the isolation of the MSL drains, MSL sample line valves, RHR system sample line valves, and Reactor Recirculation loop sample line valves.

3.0 DETAILED DESCRIPTION The proposed TS changes involve eliminating the MSLRM high radiation trip and isolation function from initiating: 1) an RPS automatic reactor scram; and 2) a PCIS isolation including automatic closure of the MSIVs, MSL drain valves, MSL sample line valves, RHR system sample line valves, and Reactor Recirculation loop sample line valves. The requirements for

License Amendment Request Attachment 1 Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 3 of 22 the MSLRM trip function for the MVP will be retained in Section 3.13, "Mechanical Vacuum Pump," of the TRM along with the supporting Bases.

The MSLRM is designed to monitor radiation levels in the MSLs, since high radiation emanating for the MSLs could indicate gross failure of fission products from the fuel. Upon detection of high radiation, an alarm signal is initiated and the MSLRM transmits signals to the RPS and PCIS. Upon receipt of a high-high radiation signal, the RPS initiates an automatic reactor scram and the PCIS initiates an automatic closure of all MSIVs, MSL drain valves, and MSL and Reactor Water (RW) sample line drain valves (i.e., RHR system and Reactor Recirculation loop sample lines) in order to limit fuel damage and contain the release of fission products.

The MSLRM high radiation trip settings are selected high enough above full reactor power background radiation levels to prevent spurious isolation and to increase the plant operational flexibility, yet low enough to promptly detect a gross release of fission products from the fuel.

Typically, the MSLRM alarms when the radiation level exceeds 1.5 times the full-power background level. At =5. 15 times the full-power background level, trip circuits automatically shut down the reactor and close the MSIVs along with the other containment isolations described (i.e., MSL drain valves and MSL and RW sample line drain valves).

The proposed TS changes will remove requirements for the MSLRM trip and isolation function from Table 3.3.1.1-1, "Reactor Protection System Instrumentation," and Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," listed below. The associated TS Bases for the applicable TS will also be revised accordingly.

Table 3.3.1.1-1 Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACT/OND.1 REQUIREMENTS VALUE

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License Amendment Request Attachment 1 Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 4 of 22 Table 3.3.6. 1-1 Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTIOND.1 REQUIREMENTS VALUE

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The justification for eliminating the MSLRM high radiation trip and isolation function from initiating an automatic reactor scram and automatic closure of the MSIVs is based on BWROG LTR NED0-31400A (Reference 1), and the applicability of this report to PBAPS, Units 2 and 3.

The topical report provides the safety assessment for eliminating the MSLRM high radiation trip function from initiating an automatic reactor scram and automatic closure of the MSIVs and demonstrates that the reactor vessel isolation function and scram function provided by the MSLRMs are not required to ensure compliance with the applicable radiation dose requirements. By letter dated May 15, 1991 (Reference 2), the NRC approved the topical report and indicated that it would be acceptable for licensees to reference this report when submitting TS changes concerning the elimination of the MSLRM high radiation trip functions provided that the guidance and limitations specified in NED0-31400A and associated NRC Safety Evaluation Report (SER) are followed.

The MSLRM system high radiation alarm function in the Main Control Room (MCR) will be retained. Additionally, the trip function for isolating the MVP will be maintained in Section 3.13 of the TRM along with the supporting Bases. Therefore, appropriate controls are in place to ensure that any radioactive material released from a fuel failure will be contained in the Main Condenser and processed through the Offgas System.

The Offgas System continuously removes non-condensable gases from the Main Condenser by the Steam Jet Air Ejectors (SJAEs) during plant operation, The offgas extracted from the Main Condenser consists of activation gases, fission product gases, radiolytic hydrogen and oxygen, and condenser air in-leakage. The Offgas System is designed to reduce offgas radioactivity levels to permissible levels for release under all plant operations. The Offgas System provides an adequate holdup volume and time, which limits significant quantities of gaseous and particulate radioactive material so that resulting radiation exposures do not exceed applicable regulatory radiation dose limits. Continuous monitoring of system parameters is provided for all potential pathways of airborne radioactive releases, with annunciation at levels lower than release limits.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 5 of 22 The proposed TS changes associated with eliminating the MSLRM high radiation isolation function from initiating an automatic closure of the MSL drain valves, MSL sample line valves, and RW sample line valves (i.e., AHR system sample and Reactor Recirculation loop sample lines) were not evaluated in NED0-31400A. Exelon is proposing to eliminate the MSLRM high radiation automatic closure function for these valves at PBAPS, Units 2 and 3, on the basis that the MSL drain lines ultimately drain to the Main Condenser, whereby non-condensable gases are extracted, processed, and released to the environment through an isolated Main Condenser or through the Offgas System. Since the discharge from these valves enters the Main Condenser and is processed through an Offgas System the analysis provided in NED0-31400A is applicable. With respect to the MSL sample lines and RW sample line drain valves (i.e., AHR system and Reactor Recirculation loop sample lines), these sample lines are routed to sample sinks where inlet valves are normally closed. In addition, sample line valves may be periodically opened to facilitate chemistry sampling.

NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4, "contain criteria and guidance for the improved TS for GE BWR/4 plants. The proposed changes are consistent with the guidance provided in NUREG-1433, Revision 4.

Section 4.0, "Technical Analysis," of this submittal provides further justification in support of the proposed TS changes.

4.0 TECHNICAL ANALYSIS

The safety objective of the MSLRM system is to detect the release of fission products from a gross fuel failure and, upon indication of such failure, to initiate appropriate action to limit fuel damage and control fission product releases.

The current design basis for the MSLRM system is described as follows:

1. The MSLRM system is designed to give prompt indication of a release of fission products from a gross fuel failure.

2. The MSLRM system is capable of detecting a release of fission products from a gross fuel failure under any anticipated operating condition of MSLs.

3. Upon detection of a release of fission products from a gross fuel failure, the MSLRM system initiates a scram.

4. Upon detection of a release of fission products from a gross fuel failure, the MSLRM system initiates action to contain the fission products released from the fuel.

Four gamma-sensitive instrumentation channels monitor the gross gamma radiation from the MSLs. The detectors are physically located near the MSLs just downstream of the MSIVs. The detectors are geometrically arranged so that the system is capable of detecting significant increases in radiation level from any number of MSLs in operation. Their location along the

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 6 of 22 MSLs allows the earliest practical detection of a gross fuel failure. Two of the channels are powered from one RPS bus, and the other two channels are powered from the other RPS bus.

When a significant increase in the MSL radiation level is detected, trip signals are transmitted to the RPS, the PCIS, and to the MVP. Upon receipt of the high radiation trip signals, the RPS initiates a scram, the PCIS initiates closure of all MSIVs, the MVP would trip, if running, and the MVP suction valve would close.

The radiation trip setpoint is selected such that a high radiation trip results from the fission products released in the design basis CADA. The setting selected is sufficiently high enough above the rated full-power background radiation level in the vicinity of the MSLs that spurious trips are avoided at rated power. The setting is low enough that the monitor can respond to the fission products released during the design basis rod drop accident.

The four instrumentation channels are arranged in a one-out-of-two-twice logic to provide the required redundancy and prevent inadvertent scram and isolation as a result of instrumentation malfunctions. The output trip signals of each monitoring channel are combined in such a way that at least two channels must signal high radiation to initiate scram and MSL isolation. Thus, failure of any one monitoring channel does not result in inadvertent actuation.

Each monitoring channel consists of a gamma-sensitive ion chamber and a Logarithmic Radiation Monitor (LAM). Each LAM has two trip circuits. One trip circuit comprises the upscale trip setting that is used to initiate scram and isolation. The other trip circuit is a downscale trip that actuates an instrument trouble alarm in the MCA. The output from each LAM is displayed in the MCA.

The trip circuits for each monitoring channel operate normally energized, so that power interruptions to monitoring components result in a trip signal. The environmental capabilities of the components of each monitoring channel are selected in consideration of the locations in which the components are to be placed.

The number and location of the detectors meet the safety design bases described above under Items 1 and 2. The closure of the MSIVs and tripping of the MVP ensures containment of radioactive materials. This satisfies safety design bases described above in Items 3 and 4. The MSLRM system is capable of initiating safety action at the level of fuel damage resulting from the design basis CADA.

Elimination of the MSLRM system high radiation trip functions from initiating automatic closure of the MSL line drain valves, MSL sample line valves and RW sample line valves (i.e., AHR system and Reactor Recirculation loop sample lines) were not evaluated in NED0-31400A.

The flow from the MSL drain valves ultimately travels to the Main Condenser just as the flow from the MSIVs. Therefore, any radioactive material passing through the MSL drain valves to the Main Condenser and through the Offgas System is treated identically to any radioactive material that would pass through the MSIVs. Since NED0-31400A evaluated removing the

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 7 of 22 MSLRM system high radiation trip function from closing the MSIVs, this same analysis can be applied for closure of the MSL drain valves. During initial phases of plant startup (i.e., reactor coolant temperature < 200 °F), the MSL drain lines are isolated. Thus, these lines would not represent a release path if a CADA were to occur during this period at a low power level.

During later periods of the plant startup when reactor coolant temperatures exceed 212 °F, the MSL drain lines are opened, as needed, to maintain heatup within the TS limits. However, the MSIVs are also open during this period (i.e., the MSLs are open to the Main Condenser). It is assumed that 100% of CADA activity is postulated to be released to the Main Condenser in 1 second, and therefore, the transportation of the post-CADA activity from reactor coolant to the Main Condenser either via MSLs or MSL drain lines becomes inconsequential. The release through both the MSLs and MSL drain lines terminate at the same location (i.e., Main Condenser) before the release to the environment via the isolated Main Condenser or through the Offgas System.

Retaining the MVP Isolation in the TRM:

The MVP is used during the early part of plant startup to evacuate the Main Condenser until enough steam flow is achieved such that the SJAEs can be put into service to maintain Main Condenser vacuum. The MVP is also used during shutdown to maintain a vacuum condition in the Main Condenser. The MVP takes suction from the Main Condenser and discharges the non-condensable gases to a discharge pipe which provides a volume and holdup period for short-lived radionuclides. If a CADA were to occur during MVP operation, any resulting fission product release from the reactor coolant would travel through the open MSIVs to the Main Condenser where the MVP would exhaust any fission products to the plant's Main Offgas Stack.

This would result in an elevated release having a 0-2 hour X)Q value of 3.31 E-06 m/sec3 , which is substantially lower than the MCA X)Q value of 1.18E-03 m/sec3 for a Main Condenser release through the Reactor Building stack. Section 2.0 of Calculation PM-1057 (Attachment 4) discusses compensating conservatisms considered for the MVP release path. The effect of the compensating conservatisms for the MVP release path described in the supporting calculation is such that the resulting doses will be considerably smaller than rounding error.

Requirements for the MVP are currently described in TAM Section 3.13 and include Applicability, Compensatory Actions, Test Requirements, and Bases related to the MVP. Since the trip function requirements for the MVP are maintained in the TAM and the MSLRM system high radiation alarm function is being retained in the MCA, appropriate measures are in place to ensure that any radioactive material released from a gross fuel failure will be contained in the Main Condenser and processed through the Offgas System.

The requirement for maintaining the MSLRM trip function is not included in the Improved Standard TS (i.e., NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric Plants, BWR/4," April 2012) (Reference 3). In addition, there is no specific requirement in NUREG-1433, Revision 4 for including MVP instrumentation and isolation.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 8 of 22 10 CFR 50.36(c)(2)(ii), Criterion 3 stipulates the following:

A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."

Under CRDA conditions discussed in the submittal, isolation of the MVP is not a "primary success path"to mitigate the design basis accident. Specifically, the supporting dose analyses contained in Calculations PM-1057, Revision 5 and PM-1168, Revision O (Attachments 4 and 5, respectively) demonstrate that satisfying Criterion 3 of 10 CFR 50.36(c)(2)(ii) is no longer applicable, as both onsite and offsite dose consequences remain within regulatory limits, assuming no automatic MSLRM or MVP isolation function.

Dose Analysis:

The discussion below provides additional plant-specific analysis in support of the proposed changes. It shows that the fission product release involved in the CRDA and the resulting doses are still relatively small. Based on implementing the proposed changes, it can be concluded that for situations involving fission product releases from gross failures, the MSLRM system remains capable of providing an alarm function.

The supporting analyses for this License Amendment Request (i.e., Calculations PM-1057, Revision 5 - Attachment 4 and PM-1168, Revision 0 - Attachment 5) determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and MGR doses due to a Control Rod Drop Accident (CRDA) using:

1) Alternative Source Term (AST) methodology.

2) The Total Effective Dose Equivalent (TEDE) dose criteria of 10 CFR 50.67.

3) The Regulatory Guide (RG) 1.183, Appendix C and NED0-31400A.

4) The Extended Power Uprate {EPU) core inventory assuming the MSLRM no longer provides a signal for automatic closure of the MSIVs.

Analysis Assumptions:

1. The number of Failed Fuel Rods is assumed to be 1,200 rods for bounding case of 1Ox1 O bundle for GNF2 fuel. An average power peaking factor of 1. 7 per pin was assumed. 10%

of the core inventory of noble gases and iodine, and 12% of the core inventory of alkali metals, are released from the breached fuel gap.

2. Five percent (5.0%) of the breached fuel is conservatively assumed to melt during the CRDA. 100% of noble gases and 50% of the iodines contained in the melted fuel fraction are assumed to be released to the reactor coolant.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 9 of 22

3. The activity released from the fuel from either the gap or from fuel pellets is assumed to be instantaneously mixed with the reactor coolant within the pressure vessel. 100% of all noble gases, 10% of the iodines, and 1% of alkali metal nuclides are transported to the Turbine/Condenser.

4. Of the activity that reaches the turbine and condenser, 100% of the noble gases, 10% of the iodine, and 1% of the alkali metal nuclides are available for release to the environment.

5. Upon detection of high radiation levels during a CRDA by the MSLRM, no credit is taken for MSIV closure, nor SJAE shutdown. Credit is taken for MVP cessation.

6. It is assumed that the purging of the Reactor Water (RW) chemistry sample line continues for 60 minutes until the sample valves are closed by a MGR operator. These sample line valves are classified as Primary Containment Isolation Valves (PCIVs). The post-CRDA release through the RW sample line path contributes additional doses, which are added to corresponding total post-CRDA doses at EAB, LPZ, and CR locations.

7. The following potential release paths were reviewed and analyzed to determine the most limiting combination of the credible release paths as a result of the MSIVs remaining open during the CRDA:

a) An isolated Main Condenser is assumed to exhaust the post-CRDA activity through the reactor building stack as a ground level release at a rate of 1% per day. No credit is taken for dilution or holdup within the turbine building. Radioactive decay during holdup in the turbine is not assumed (i.e., the activity is instantaneously transported to the condenser). Radioactive decay during holdup in the condenser is assumed.

b) For a release without the automatic MSIV trip, the methods of analysis are the same as that used for the first case except for those that pertain to the release path.

For this case, the evaluation assumes that the MSIVs do not close and that steam flow continues for approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before this path is isolated. If the event occurs at low power and the steam jet air ejector does not operate, then the offsite dose is equivalent to that of the first case because the total activity is assumed to be transferred to the condenser instantaneously. If sufficient power is available for SJAE operation, then some of the available activity in the Main Condenser is transported to the Offgas System and thus provides a different release path to the environment. The charcoal beds in the Offgas System ensure that the iodine is retained in the charcoal beds and not released to the environment. The noble gases are held for significant decay times (refer to Table 1) before release from the stacks and to the environment.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 10 of 22 c) During the low power operating conditions there are forced flow paths from the Turbine/Main Condenser. For instance, the CADA can occur during MVP operation, which can exhaust an unprocessed release from the condenser at a significantly larger rate. Since the MSLRM trip function of the MVP is retained, this release path would be promptly terminated with the resulting doses considerably less than rounding error.

d) A release path not automatically isolated during this event is via the Turbine Gland Seal Condenser. For the turbine gland seal release, the reactor steam containing the CADA source is assumed to be directly released to the environment without any holdup, dilution, and partitioning of the radioiodine and particulates in the gland seal condenser.

e) Another release path not automatically isolated during this event is the consideration of a concurrent RW chemistry sample being taken when the CADA occurs. For this case, it is assumed that an MCR operator closes the PCIVs by remote-manual means within one hour (refer to Calculation PM-1168, Revision O - Attachment 5.

As discussed in the preceding discussion, the four credible release paths that exist during a CADA are through the isolated Main Condenser, SJAE, gland seal condenser, and RW sample line path. The SJAE release path exists when there is enough steam pressure available to sustain its operation. Only the SJAE or isolated Main Condenser release path exists at a given time. The operation of the SJAE maintains the Main Condenser at a vacuum, and thereby eliminates the potential for a release through the Main Condenser. The CADA occurring at a low power level secures the operation of the SJAE, which pressurizes the Main Condenser and establishes a post-CADA release path. The Turbine Gland Seal Condenser is operational as long as there is pressurized steam available during the CADA event.

Since the MSIV is postulated to remain open for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor decay heat continues to produce steam and thereby establishes the Turbine Gland Seal Condenser release path irrespective of Main Condenser or SJAE operation.

Consequently, in addition to the assumed 1-hour chemistry RW sample release path, the two possible combinations of release paths that may exist at any time during a CADA event are:

a) The isolated Main Condenser, gland seal condenser, and RW sample release paths.

b) The SJAE, gland seal condenser, and RW sample release paths.

8. All leakage from the main steam turbine condenser leaks to the atmosphere from the Turbine Building/Reactor Building Ventilation Exhaust Stack at a rate of 1% per day, for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 11 of 22

9. The accident release duration is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months except for the RW sample line release, which is for one hour.

Offsite Dose Consequences:

The offsite dose assumptions are the same as those in UFSAR Sections 14.9.2.1.16 through 14.9.2.1.18 for the CADA analysis (described below).

The offsite dose is determined as a Total Effective Dose Equivalent (TEDE), which is the sum of the Committed Effective Dose Equivalent (CEDE) from inhalation and the Deep Dose Equivalent (DOE) from external exposure from all radionuclides that are significant with regard to dose consequences and the released radioactivity.

The maximum EAB TEDE for any two-hour period following the start of the radioactivity release is determined and used in determining compliance with the dose acceptance criteria in 10 CFR 50.67.

TEDE is determined for the most limiting receptor at the outer boundary of the LPZ and is used in determining compliance with the dose criteria in 10 CFR 50.67.

Control Room Dose Consequences:

The radioactive material releases and radiation levels used in the MCR dose analysis are determined using the same source term, transport, and release assumptions used for determining the EAB and the LPZ TEDE values. The Main Control Room Emergency Ventilation (MCREV) parameters are shown in Table 1 below (Reference UFSAR Table 14.9.12). The MCR external cloud is negligible because less than 2% of the core fuel is damaged, and 60 fuel rods are melted. Also there is no release into containment, so there is no containment shine dose and the MCR emergency filtration is not modeled, so there is no MCR filter shine dose. Therefore, the MCR operator doses from the external cloud, containment shine, and MCR filter shine doses are not analyzed for the CADA.

Table 1 Parameters and Assumptions Used In Control Rod Drop Accident Radiological Consequence Analysis Parameters Value Reactor Power level 4,030 MWt Radial Peaking Factor 1.7 Number Failed Fuel Rods (Bounding case for 10x10 bundle tvoe) 1200 Melted Fuel Rods 5.0% of Failed Fuel Rods Fission Product Release Fractions:

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 12 of 22 Parameters Value Failed Fuel Rods:

Noble Gas 10%

Iodine 10%

Alkali Metals 12%

Melted Fuel Rods:

Noble Gas 100%

Iodine 50%

Remaining Fission Products RG 1.183 Table 1, Early-In-Vessel Fraction Fission Product Fraction Transfer To Condenser:

Noble Gas 100%

Iodine 10%

Remaining Fission Products 1%

Fission Product Fraction Available for Condenser Release:

Noble Gas 100%

Iodine 10%

Remaininq Fission Products 1%

Condenser Release Rate 1 volume%/dav Gland Seal Condenser (Extraction Steam) Flow Rate 0.15% of Main Steam Flow Rate (18,920 lbs/hr)

Offgas System Charcoal Delay Beds Hold-Up Time:

Krypton 34 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months Xenon 401 hours0.00464 days 0.111 hours 6.630291e-4 weeks 1.525805e-4 months Duration of Release 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Control Room Parameters:

Control Room Volume 1.76E+5 ft 3 MCREV Operation Not Credited Control Room Normal Intake Flow Rate 20,600 cfm Assumed Unfiltered lnleakaqe Rate 500 cfm

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f "'""* 'ti" '* ~"" "-' N "" > :

CR 1/ Qs o - 2 hrs 1.18E-3 sec/m 3 2 - 8 hrs 9.08E-4 sec/m 3 8-24 hrs 4.14E-4 sec/m 3 EAB 1/Qs O - 2 hrs 9.11 E-4 sec/m 3 LPZ x/Os O - 2 hrs 1.38E-4 sec/m 3 2 - 8 hrs 5.81E-5 sec/m 3 8 - 24 hrs 3. 77E-5 sec/m 3 Dose Conversion Factors FGR 11 & 12

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 13 of 22 Coincident Chemistry Sample Line Open Analysis:

A calculation (i.e., PM-1168, Revision O - Attachment 5) was performed to determine the EAB, LPZ, and MGR doses due to the Post- CADA release from the RW sample line. This calculation uses the AST methodology, the TEDE dose criteria of 10 CFR 50.67, guidance in RG 1.183, Appendix C and NED0-31400A, and the Extended Power Uprate (EPU) core inventory. This calculation assumes that the MSLRM no longer provides a signal for automatic closure of the MSL drain valves and MSL and RW water sample line valves (i.e., RHR system and Reactor Recirculation loop sample lines), which provides for potential release to the environment through Reactor Building (RB) ventilation via sample sink hood exhaust.

With respect to deleting the MSLRM high radiation trip function to close the RW sample line valves on a MSLRM system high radiation signal, the following bounding*Rw sampling scenario is postulated based on the PBAPS Chemistry procedure for sampling of reactor water. The post-CADA contact dose rate of the RW sample (i.e., RHR system and Reactor Recirculation loop sample lines) will immediately exceed the radiation zone allowable dose rate limit causing the area radiation monitor located near the sample sink to alarm alerting any plant personnel (e.g., chemist) to evacuate the area. Consequently, no credit is taken for the plant personnel (e.g., chemist) securing the sampling process. Instead, it is assumed that the purging of the RW sample line continues for one hour until the sample valves are closed by an MGR operator.

It is assumed that the worst-case status for a sample line from a dose perspective is being "open" coincident with the CADA.

The sample lines are routed to a sample sink where inlet valves on the sample lines are normally closed. The sample lines provide a means for drawing the necessary coolant samples to confirm plant water chemistry is within required limits. The sample sinks are located in the RB and are under equipment ventilation hoods, and vented air is filtered prior to release to the environment. The charcoal filtration is not credited. Any small system leakage would be into the Secondary Containment.

In order to assess the radiological impact of a scenario where a CADA occurred coincidentally with an open sample line, it was conservatively assumed that the largest sample line is "open" for one hour prior to being isolated by remote-manual action taken by licensed MGR operators.

This flow path would be isolated by the use of safety-related PCIVs. Because of the removal of the scram and automatic closure of the MSIVs, there would be ample time to promptly close the PCIVs. The likelihood of RW sample valves (i.e., RHR system and Reactor Recirculation loop sample lines) being open at the occurrence of a CADA is minimal. However, procedural controls will be in place to direct licensed operators to close the PCIVs. Additionally, the bounding sample line sample valves are typically only opened when the Reactor Water Cleanup System is out-of-service.

The comparison of resulting doses with the licensing basis CADA doses indicates that the post-CRDA EAB, LPZ, and CR doses due to a reactor water sample line release are a fraction (less than 20 percent) of the CADA doses for the most conservative case of continuous purging of RW sample line for one hour. The combined dose including the contribution from the sample lines is significantly below allowable regulatory dose limits (refer to Table 3).

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 14 of 22 The analysis indicates that the post-CRDA contact dose rate of the RW sample line in the sampling area is expected to immediately exceed the radiation zone allowable dose rate limit, and the resulting radiation monitor alarm would alert the personnel to evacuate the area immediately. Additionally, any plant personnel in the sampling area would also be immediately alerted of increasing dose rates by their personal dosimetry.

Dose Acceptance Criteria:

The following NRC regulatory requirement and guidance documents are applicable to CRDA analysis:

Regulatory Guide 1.183, Table 6

10 CFR 50.67

Standard Review Plan Section 15.0.1 Dose Acceptance Criteria are shown in Table 2:

Table 2 Regulatory Dose Limits Dose T e Control Room rem EAB and LPZ rem TEDE Dose 5 6.3 Atmospheric Dispersion Factors (x;Qs):

The xfQs are based on Regulatory Guide 1.194 methodology as implemented by ARCON96 for onsite locations (i.e., MCR) and on Regulatory Guide 1.145 methodology as implemented by PAVAN for offsite locations (EAB and LPZ). The MCR, EAB, and LPZ xfQs are shown in the supporting Calculation PM-1057, Revision 5 (Attachment 4).

Radiological Dose Consequences:

The post-CRDA MCR, EAB, and LPZ dose consequences are shown in Table 3. The Table 3 doses from a postulated CRDA event reflect scenarios both with and without a RW chemistry sample line open.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 15 of 22 Table 3 Postulated CRDA Dose Summary Open Sample Line Post-CRDA TEDE Dose (Rem)

Post-.CRDA Activity Receptor Location Release Path Control Room EAB LPZ Design Basis CRDA 1.77 2.04 0.35 without RW Sample Release RW Sample Release 0.290 0.286 0.043 Combined Design Basis CRDA with RW 2.06 2.33 0.39 Sample Release Allowable TEDE Limit 5.00 6.30 6.30 NRC May 15, 1991, LTR Safety Evaluation Report Conditions:

Finally, in the letter dated May 15, 1991 (Reference 2), the NRG stated that removal of the MSLRM system high radiation trip function from initiating an automatic reactor scram and closure of the MSIVs is acceptable; however, licensees referencing NED0-31400A in support of their TS change requests must meet the following conditions. Therefore, each condition is restated below followed by our response.

Condition 1 The applicant demonstrates that the assumptions with regard to input values (including power per assembly, Chi/Q, and decay times) that are made in the generic analysis bound those for the plant.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 16 of 22

Response

Although Condition 1 input values are not fully bounded, as-built information and the following assumptions were used which demonstrate acceptable dose results:

1. The number of Failed Fuel Rods is assumed to be 1,200 rods for bounding case of 1Ox10 GNF2 fuel type. An average power peaking factor of 1.7 per pin was assumed. 10% of the core noble gases and iodine, and 12% of the core alkali metals, are released from the fuel gap.

2. Five percent (5.0%) of the breached fuel is conservatively assumed to melt during the CADA. 100% of noble gases and 50% of the iodines contained in the melted fuel fraction are assumed to be released to the reactor coolant.

3. The activity released from the breached fuel gap and melted fuel is assumed to be instantaneously mixed with the reactor coolant within the pressure vessel. 100% of all noble gases, 10% of the iodines, and 1% of remaining nuclides are transported to the Turbine/Main Condenser.

4. Upon detection of high radiation levels during a CADA by the MSLRM, no credit is taken for MSIV closure, nor SJAE shutdown. Credit is taken for MVP cessation.

5. The Offgas System charcoal delay beds provide a retention time of 401 hours0.00464 days 0.111 hours 6.630291e-4 weeks 1.525805e-4 months for xenon holdup and 34 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months for krypton holdup.

The analysis provided in NED0-31400A assumes that the CADA results in the failure of 850 fuel rods with a mass fraction of fuel in the damaged rods of 0. 77%. For the portion of the fuel which was assumed to reach the melting point, the release fractions were 100% of the noble gases and 50% of the iodines.

The CADA with no credit taken for MSIV closure is modeled with an EAB atmospheric dispersion factor (XJ'Q) of 9.11 E-4 sec/m 3

This model provides higher atmospheric dispersion than the analysis provided in NED0-31400A for the scenario without MSIV closure, which models an EAB XJ'Q of 3E-4 sec/m 3

Condition 2 The applicant includes sufficient evidence (implemented or proposed operating procedures, or equivalent commitments) to provide reasonable assurance that increased significant levels of radioactivity in the main steam lines will be controlled expeditiously to limit both occupational doses and environmental releases.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 17 of 22

Response

Appropriate actions will be implemented at PBAPS to ensure that significant increases in MSL radiation levels are adequately controlled to limit occupational exposures and environmental releases. In the event of a MSLRM system high radiation alarm, MSLRM and Offgas System radiation level trending data from radiation monitor recorders will be reviewed, and if necessary, reactor coolant samples will be obtained and analyzed. If high radiation levels are confirmed, as measured by the Offgas system radiation monitors, reactor power will be reduced to maintain offgas release rates within TS requirements. If these release rates cannot be maintained within required TS limits, an orderly plant shutdown will be initiated. Plant procedures will be in place to implement the appropriate mitigative measures in response to a MSLRM high radiation alarm signal.

Condition 3 The applicant standardizes the MSLRM and offgas radiation monitor alarm setpoint at 1.5 times the normal Nitrogen-16 background dose rate at the monitor locations, and commits to promptly sample the reactor coolant to determine possible contamination levels in the plant reactor coolant and the need for additional corrective actions, if the MSLRM or offgas radiation monitors or both exceed their alarm setpoints.

Response

The MSLRM alarm setpoint is currently set at 1.5 times the expected full reactor power background radiation level. Therefore, the MSLRM alarm setpoint does not need to be changed. As previously indicated in our response to Item 2 above, samples will be taken, as necessary, to ascertain reactor coolant chemistry conditions and appropriate actions will be taken. Plant operators in the MCA will isolate the affected sample line PCIVs within one hour if plant conditions warrant.

5.0 REGULATORY ANALYSIS

5.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.67 The proposed TS changes are consistent with the current regulations and thus, an exemption pursuant to 10 CFR 50.12 is not required. Conformance to the current regulations will be maintained, in particular, 10 CFR 50.67, Alternative source term," with the elimination of the MSLRM from the plant design and TS.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 18 of 22 From Footnote 1 of 10 CFR 50.67:

The fission product release assumed for these calculations should be based upon a major accident, hypothesized for purposes of design analyses or postulated from considerations of possible accidental events, that would result in potential hazards not exceeded by those from any accident considered credible.

This submittal demonstrates that the dose consequences are in conformance with 1o CFR 50.67, assuming the MSLRM is no longer available to mitigate the consequences of a CADA.

10 CFR 50.36 This submittal demonstrates that the MSLRM and its associated trip and isolation functions involving initiating an automatic reactor scram and automatic closure of the MSIVs, MSL drain valves, MSL sample line valves, RW sample line valves (i.e., AHR system and Reactor Recirculation loop sample lines) are no longer necessary to satisfy certain 10 CFR 50.36 criteria. Specifically, the dose analysis demonstrates that Criterion 3 (i.e., 10 CFR 50.36(c)(2)(ii)(C)) is no longer applicable, as both onsite and offsite dose consequences remain within regulatory limits, assuming no automatic MSLRM isolation function.

The requirements for the MSLRM trip function for the MVP will be retained in TAM Section 3.13, "Mechanical Vacuum Pump," along with the supporting Bases. Therefore, Exelon considers that appropriate measures and requirements are in place to ensure that any radioactive material released from a gross fuel failure will be contained in the Main Condenser and processed through the Offgas System.

NUREG-1433. Revision 4 In addition, the proposed changes are consistent with guidance contained in the Improved Standard TS (i.e., NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric Plants, BWR/4, "April 2012).

5.2 Precedent A number of plants in the industry have submitted license amendment requests and received NRC approval to eliminate the MSLRM trip function from initiating an automatic reactor scram and automatic closure of the MSIVs based on the NRG-approved LTR NED0-31400A. Some of the plants include:

Limerick Generating Station - February 1995

Quad Cities Nuclear Power Station - October 2000

Duane Arnold Energy Center - March 1992

Vermont Yankee - September 2002

Cooper Nuclear Station - March 1993

Hope Creek Generating Station - August 1992

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 19 of 22 5.3 No Significant Hazards Consideration Exelon has concluded that the proposed changes to the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, Technical Specifications (TS), to eliminate the Main Steam Line Radiation Monitor (MSLRM) from initiating: 1) a Reactor Protection System (RPS) automatic reactor scram; and 2) automatic closure of the Main Steam Line Isolation Valves (MSIVs), Main Steam Line (MSL) drain valves, MSL sample line drain valves, Residual Heat Removal (AHA) system sample line valves, and Reactor Recirculation loop sample line valves do not involve a Significant Hazards Consideration. Additionally, existing requirements for operation of the Mechanical Vacuum Pump (MVP) will be retained in the Technical Requirements Manual (TAM). In support of this determination, an evaluation of each of the three standards, set forth in 10 CFR 50.92, "Issuance of amendment," is provided below.

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed changes eliminate the MSLRM trip and isolation function from initiating an automatic reactor scram and automatic closure of the MSIVs. The justification for eliminating the MSLRM trip and isolation functions is based on the NRG-approved evaluation provided in General Electric's (GE's) Licensing Topical Report (LTR) NED0-31400A, "Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Line Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," dated October 1992. The proposed changes also include the elimination of the MSLRM isolation function from closing the MSL drain valves, MSL sample line valves, AHR system sample line valves, and Reactor Recirculation loop sample line valves. The identified sample lines are small in comparison to the size of MSLs, and therefore, the effects of not isolating these lines for at least one hour is considered small and is supported by the dose analyses. The MSLRM system is not an initiator of any accident previously evaluated. Retaining requirements for the MVP in the TAM will ensure that appropriate measures and requirements are in place such that any release of radioactive material released from a gross fuel failure will be contained in the Main Condenser and processed through the Offgas System.

The proposed changes do not introduce new equipment or new equipment operating modes.

The proposed changes do not increase system or component pressures, temperatures, or flowrates for systems designed to prevent accidents or mitigate the consequences of an accident. There are no changes or modifications to the MVP. The MVP will continue to function as designed in all required modes of operation. Since these conditions do not change, the likelihood of a failure or malfunction of a Structure, System, or Component (SSC) is not increased. As a result, the probability of any accident previously evaluated is not significantly increased. The consequences of an accident previously evaluated (i.e., the Control Rod Drop

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 20 of 22 Accident (CADA)), have been evaluated consistent with the PBAPS licensing basis, which is based on Alternative Source Term (10 CFR 50.67). As demonstrated by the supporting dose analyses, the consequences of the accident are within the regulatory acceptance criterion. As a result, the consequences of any accident previously evaluated are not significantly increased.

Based on the above, Exelon concludes that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

No new or different accidents result from the proposed changes. The proposed changes do not involve a change in the method of operation of plant SSC. The proposed changes do not increase system or component pressures, temperatures, or flowrates. There is no new system component being installed, no construction of a new facility, and no performance of a new test or maintenance function. The MVP will continue to function as designed in all required modes of operation. Since these conditions do not change, the proposed changes will not create the possibility of a new or different kind of accident. Retaining requirements for the MVP in the TAM will ensure that appropriate measures and requirements are in place such that any release of radioactive material released from a gross fuel failure will be contained in the Main Condenser and processed through the Offgas System. The elimination of the MSLRM trip and isolation functions as described is only credited in the CADA analysis and no other event in the safety analysis. The proposed changes are consistent with the revised safety analysis assumptions for a CADA as described in this license amendment request.

Based on the above discussion, Exelon concludes that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed changes eliminate the MSLRM trip and isolation functions from initiating an automatic reactor scram ahd automatic closure of the MSIVs along with closing of the MSL drain valves, MSL sample line valves, AHR system sample line valves, and Reactor Recirculation loop sample line valves and are justified based on the NRG-approved LTR NED0-31400A and supporting dose analysis. Retaining requirements for the MVP in the TAM will ensure that appropriate measures and requirements are in place such that any release of radioactive material from a gross fuel failure will be contained in the Main Condenser and processed through the Offgas System.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 21of22 The proposed changes do not increase system or component pressures, temperatures, or flowrates for systems designed to prevent accidents or mitigate the consequences of an accident. Analyses performed consistent with the PBAPS licensing basis, demonstrate that the removal of the trip and isolation functions as described will not cause a significant reduction in the margin of safety, as the resulting offsite dose consequences are being maintained within regulatory limits. The proposed changes do not exceed or alter a design basis or a safety limit for a parameter to be described or established in the Updated Final Safety Analysis Report (UFSAR) or the Renewed Facility Operating License (FOL).

As a result, Exelon concludes that the proposed changes do not involve a significant reduction in a margin of safety.

5.4 Conclusion Based on the preceding 10 CFR 50.92 evaluation, Exelon concludes that the proposed changes present a "no significant hazards consideration" under the standards set forth in 10 CFR 50.92(c) and are therefore justified. There are no changes being proposed in this license amendment request such that commitments to applicable regulatory requirements and guidance documents described above would come into question. The evaluations documented above confirm that PBAPS will continue to comply with all applicable regulatory requirements.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

The proposed changes involve eliminating the MSLRM trip functions from initiating an automatic reactor scram and automatic closure of the MSIVs based on the evaluation provided in LTR NED0-31400A, which was approved by the NRC. In addition, the proposed changes request the elimination of the MSLRM high radiation trip and isolation function from initiating an automatic closure of the MSL drain valves, MSL sample lines, RHR system sample lines, and Reactor Recirculation loop sample line valves. The proposed changes do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

License Amendment Request Eliminate Main Steam Line Radiation Monitor Trip and Isolation Function Docket Nos. 50-277 and 50-278 Evaluation of Proposed Changes Page 22 of 22

7.0 REFERENCES

1) General Electric Report NED0-31400A, "Safety Evaluation for Eliminating the Boiling Water Reactor Main Steam Line Isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor," dated October 1992.

2) Letter from A. C. Thadani (U.S. Nuclear Regulatory Commission) to G. J. Beck (BWROG),

Acceptance for Referencing Topical Report NED0-31400,"dated May 15, 1991.

3) NUREG-1433, Revision 4, "Standard Technical Specifications, General Electric Plants, BWR/4, "April 2012)

Attachment 2 Peach Bottom Atomic Power Station, Units 2 and 3 NRC Docket Nos. 50-277 and 50-278 Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip Function Proposed Technical Specifications Unit 2 Unit 3 3.3-5 3.3-5 3.3-6a 3.3-6a 3.3-8 3.3-8 3.3-48 3.3-48 3.3-51 3.3-51 3.3-51a 3.3-51a 3.3-52 3.3-52

Unit 2 TS Pages

RPS Instrumentation 3.3.l.l SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.l.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Survei *11 ance Frequency Control Program.

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SR 3.3.1.1.11 - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - -

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Cont ro 1 Program.

(continued)

PBAPS UN IT 2 3.3-5 Amendment No. 278

RPS Instrumentation 3.3.1.1 SlJRVEI L.LANCE REOU IPEMENTS (continued)

SURVEILLANCE FREQUENCY

,----------------------------------------------~I SR 3.3.1.1.16 Ga)/i era t.e*.*****.~aefrradtatfa.rr In a95~fdanEe

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I I SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Survei 11 ance Frequency Control Program. SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within In accordance limits. with the Surveillance Frequency Control Program. SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM In accordance Simulated Thermal Power is ~29.5% and with the recirculation drive flow is <60%. Surveillance Frequency Control Program. PBAPS UN IT 2 3.3-6a Amendment No. 278

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3) Reactor Protection System !nstrumentation APPLICABLE CONDITIONS MODES OR REQU I REil REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDIT IONS SYSTEM ACTION D. l REQUIREMENTS VALUE

3. Reactor Pressure -High 1,2 2 G SR 3.3.1.1.l s 1085.0 psig SR 3.3.1.l.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

4. Reactor Vessel Water l, 2 2 G SR 3.3.1.1.1 <= 1.0 inches Level-Low (Level 3) SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

5. Main Steam Isolation 8 F SR 3.3.1.1.9 s 10% closed Valve -Closure SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

6. Drywel l Pressure - High 1,2 2 G SR 3.3.1.1.l s 2.0 psig SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.l.17 SR 3.3.1.1.18

7. Scram Discharge Volume 1, 2 2 G SR 3.3.1.1.9 ::; 50.0 gallons Water Level -High SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 5 ca) 2 H SR 3.3.1.1.9 ::; 50.0 gallons SR 3.3.1.1.15 SR 3.3.1.1.17

8. Turbine Stop <= 29.5% RTP 4 E SR 3.3.1.1.9 s 10% closed Valve -Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

9. Turbine Control Valve <= 29.5% RTP 2 E SR 3.3.1.1.9 <= 500.0 psig Fast Closure. Trip Oil SR 3.3.1.1.13 Pressure -Low SR 3.:3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

10. Turbine Condenser-Low 2 F SR 3.3.1.1.1 <= 23.0 inches Vacuum SR 3.3.1.1.9 Hg vacuum SR 3.3.1.1.15 SR 3. 3.1.1.17 SR 3.3.1.1.18 Ir----------------------------------~----~--------1

11. ***.....*. _,., .. ***.'ii ~ 4 4 :**:*******

I I

12. Reactor Mode Switch -

Shutdown Position 1,2 G SR SR

3. 3.1.1.14 3.3.1.1.17 NA 5<a) H SR 3.3.1.1.14 NA SR 3.3.1.1.17 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. PBAPS UNIT 2 3.3-8 Amendment No. 247

Primary Containment Isolation Instrumentation

3. 3. 6. 1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1. ACTIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDIT ION REQUIRED ACTION COMPLETION TIME A. One or more required A .1 Pl ace channel in 12 hours for channels inoperable. trip. Functi ans 1;'i'i:li'!1 2.a, 2.b, 8.a, and 8.b 24 hours for Functions other than Functions

                                                                                                                   #'.;!Et1"~ 2.a, 2.b, 8.a, and 8.b B. One or more Fun ct i ans                         B.1             Restore isolation                        1 hour with isolation                                                   capability.

capability not maintained. C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or Table 3.3.6.1-1 for B not met. the channel. (continued) PBAPS UNIT 2 3.3-48 Amendment No. 259

Primary Containment Isolation Instrumentation

3. 3. 6. 1 SURVEILLANCE REQUIREMENTS

    - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - - -

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program. SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program ,,...............__..........................-................................................._____...............___.........._________, __.__................._~~~~~~~ I I I I I I .,.,,,,,,,.,.>*:********,.:..*,.:..*. * ., I

  ---------------------~---------~--~

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued) PBAPS UN IT 2 3.3-51 Amendment No. 278

Primary Containment Isolation Instrumentation

3. 3. 6. 1 SlJf<V EI LLANCE REQU IREME.NTS (continued)

SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. rn accordance with the Surv(c'i 1 lance Frequency Control Program. 1----------------------------------- ----------- , SR 3.3.6.1.6 Cai~ii ~'t<.(&~ o~¢§ f~dia*t.~~ In ~Gco.rdante** I detecter.O.e.1 eted. ..i i 1 tFithe t..;,,.:.:: .:\*i**' **<l** : ..: *_;* **_::':***/.'~:~',i:'*,.;**.:,::-:;' I 7JtlPT!} :J ~Ace I Freq~7ncy I con~rpt Pro§x'am*i I I

 -------------------------------------------~-----

SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Survei l la nee Frequency Control Program. PBAPS UN IT 2 3.3-5la Amendment No. 278

Primary Containment Isolation Instrumentation

3. 3. 6. 1 rable 3.3.6.1-1 (page 1 of 3)

Primary Containment Isolation Instrumentation APPLICABLE CONDI TIO NS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPEC!F!ED PER TRIP REOU !RED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C. l REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water l, 2 '3 2 D SR 3.3.6.1.l <! -160.0 Leve 1 - Low Low Low SR 3.3.6.1.2 inches (Level 1) SR 3.3.6.1.5 SR 3.3.6.1.7

b. Main Steam Line 2 E SR 3.3.6.1.3 <! 850.0 psig Pressure - Low SR 3.3.6.1.7

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 s; 123.3 psid Flow-Hiqh MSL SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

.--------------~-----~--------------------------.

d. Maill\S'~~a.f!! :,~t.Fi~/?*;if;i!:~~*i Ra eta ti 9J:ip1:ni¢t4li

~-----------------------------------------------

e. Turbine Building Main 1,2' 3 6 D SR 3.3.6.1.l ,,; 200.0"F Steam Tunnel SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.7

f. Reactor Building Main l, 2' 3 2 D SR 3.3.6.1.1 ,,; 230.0"F Steam runnel SR 3.3.6.1.2 Temperature-High SR 3.3.6.1.5 SR 3.3.6.1. 7

2. Pr"imary Containment Isolation

a. Reactor Vessel Water l, 2' 3 2 G SR 3.3.6.1.1 <! 1.0 inches Leve 1 - Low (Leve 1 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

b. Drywell Pressure-High 1,2' 3 2 G SR 3.3.6.1.l s; 2.0 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

c. Main Stack Monitor 1,2,3 F SR 3.3.6.1.l $ 2 x 10-2 Radiation-High SR 3.3.6.1.2 µCi/cc SR 3.3.6.1.4 SR 3.3.6.1. 7

d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 s; 16.0 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation-High SR 3.3.6.1.7

e. Refueling Floor 1,2' 3 2 G SR 3.3.6.1.l ,,; 16.0 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation - High SR 3.3.6.1.7 (continued}

PBAPS UNIT 2 3.3-52 Amendment No. 250

Unit 3 TS Pages

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. ,~--~-~----------------------------- ~------~---------------------------- SR 3.3.1.1.11 - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - -

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. (continued) PBAPS UN IT 3 3.3-5 Amendment No. 281

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY r---------------------------------- ------------, SR 3.3.1.1.16 SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within In accordance limits. with the Surveillance Frequency Control Program. SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM In accordance Simulated Thermal Power is ~29.5% and with the recirculation drive flow is <60%. Surveillance Frequency Control Program. PBAPS UNIT 3 3.3-6a Amendment No. 281

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3) Reactor Protection System Instrumentation APPLICABLE CONDIT IONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SU RV EI LLANCE ALLOWABLE FUNC T !ON CONDITIONS SYSTEM ACTION D.1 REOU I llEMENTS VALUE

3. Reactor Pressure - High 1,2 2 G SR 3.3.1.1.1 s 1085.0 pslg SR 3.3.1.l.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

4. Reactor Vessel Water 1, 2 2 G SR 3.3.1.1.l ~ 1.0 inches Level - Low (Level 3) SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

5. Main Steam Isolation 8 F SR 3.3.1.l.9 s 10% closed Valve -Closure SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

6. Drywell Pressure-High 1,2 2 G SR 3.3.1.1.1 s 2.0 psig SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

7. Scram Discharge Volume 1, 2 2 G SR 3.3.1.1.9 s 50.0 gallons Water Level -High SR 3.3.l.l.15 SR 3.3.1.l.17 SR 3.3.1.1.18 5(a) 2 H SR 3.3.l.l.9 s 50.0 gallons SR 3.3.1.1.15 SR 3.3.1.1.17

8. Turbine Stop :!! 29.5% RTP 4 E SR 3.3.1.1.9 s 10% closed Valve-Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18

9. Turbine Control Valve ~ 29.5% RTP 2 SR 3.3.1.1.9 ~ 500.0 psig Fast Closure, Trip Dil SR 3.3.1.1.13 Pressure - Low SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3. 3 .1.1.18

10. Turbine Condenser-Low 2 F SR 3.3.1.1.1 ~ 23.0 inches Vacuum SR 3.3.1.1.9 Hg vacuum SR 3.3.1.1.15 SR 3.3.1.1.17

- -17. -:3.,,:-; :-:- -_ - -:-,::~ - - - ~- - - - -~- - - - - ~- - - -~ .J..l.i.i_ia. - - ~t;~x~~,~)~ - - - -:

I =~~WI! I I I

12. Reactor Mode Switch - 1,2 G SR 3.3.1.1.14 NA Shutdown Position SR 3.3.1.1.17 5(al H SR 3.3.1.1.14 NA SR 3.3.1. l.17 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. PBAPS UN IT 3 3.3-8 Amendment No. 250

Primary Containment Isolation rnstrumentation 3.3.6.l 3.3 INSTRUMENTATION 3.3.6.l Primary Containment Isolation Instrumentation l_CO 3.3.6.l The primary containment isolation instrumentation for each r:* u n ct i on i n fa b I c~ 3 . 3 . 6 . l - l s 11 a 1 I be 0 PE RAB LE . APPLICABILITY: According to Table 3.3.6.1-1. ACTIONS - ......... - - - -* - -.. - - - . . - - - - - . . - - - ...... - - - - - . . - . . NOTES - - -

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME r - - - - - - - - - - - - - -. I A. One or more required A.I Place channel in 12 hours for I channels inoperable. trip. Functions 2.a, 2.b, 8.a, and 8.b 24 hours for Functions other than Functions

2. a, 2. b, I 8.a, and 8.b I I I 1_ "" - - - - - - - - - - - - I B. One or more Functions B.l Restore isolation 1 hour with isolation capability.

capability not maintained. C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or Table 3.3.6.1-1 for B not met. the channe 1 . (continued) PBAPS UN IT 3 3.3-48 Amendment No. 262

Primary Containment Isolation Instrumentation

3. 3. 6. 1 SURVEILLANCE REQUIREMENTS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program. SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. ~----------------------------------~ Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program. SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program. (continued) PBAPS UNIT 3 3.3-51 Amendment No. 281

Primary Containment Isolation Instrumentation

3. 3. 6. 1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program. r-----------------------------------------------1 catto~.*a'te'.****~.aew.*r~(;li.aJ,.fo~*>* SR 3.3.6.1.6 Iil .~.~;~Qr*.q~.~*o.e'> detes~~k:'.. b~T~it~~j~ .* . . . . * ***~ ~~***tna*\

                                                                          ~.#'~~;=:~~.~~:~~;~~::.:

co&~*~WJ: Pto g'.~'afli:~:i

~-----------~

SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program. PBAPS UNIT 3 3.3-5la Amendment No. 281

Primary Containment Isolation Instrumentation

3. 3. 6 .1 Table 3.3.6.l*l (page l of 31 Primary Containment Isolation Instrumentation*

APPLICABLE CONOITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C. l REQUIREMENTS VALUE

 !. Main Steam Line Isolation

a. Reactor Ve s se 1 Water 1'2 '3 D SR 3.3.6.1.l ~ -160.0 Leve 1 *-Low Low Low SR 3.3.6.1.2 inches (Level l) SR 3.3.6.1.5 SR 3.3.6.1. 7

b. Main Steam Line 2 SR 3.3.6.1.3 ~ 850.0 psig Pressure - Low SR 3.3.6.1. 7

c. Main Steam Line 1, 2 '3 2 per D SR 3.3.6.1.l s: 123.3 psid Flow-High MSL SR 3.3.6.1.2 SR 3.3.6.1.5 r - - - - - ... - - - - - - - - - - - - - - - - - - - - - - - _ ~-3..3..Q..J..7- _______ ,

d. .,,...,...,.,,.

                                         ,: ?i::Ct I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .,;;:<::,;,;,,;.* ... ~:.:; - - - - - - - -

I

e. Main Steam Tunnel l, 2' 3 8 D SR 3.3.6.1.l :> 200.0"F Temperature -High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1. 7

2. Primary Containment Isolation

a. Reactor Vessel water 1,2. 3 2 G SR 3.3.6.1.1 ;;? 1. 0 inches Level - Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6. l. 7

b. Drywe 11 Pressure -High 1, 2 '3 2 G SR 3.3.6.1.1 :> 2 .0 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

c. Main Stack Monitor 1,2,3 F SR 3.3.6.1.1 $ 2 x 10*2 Radiation-High SR 3.3.6.1.2 µCi/cc SR 3.3.6.1.4 SR 3.3.6.1.7

d. Reactor Building 1. 2 ,3 2 G SR 3.3.6.1.l :> 16.0 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation-High SR 3.3.6.1.7

e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 :> 16.0 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation-High SR 3.3.6.1.7

{continued) PBAPS UNIT 3 3.3-52 Amendment No. 214

Attachment 3 Peach Bottom Atomic Power Station, Units 2 and 3 NRC Docket Nos. 50-277 and 50-278 Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip Function Proposed Technical Specifications Bases (For Information Only) Unit 2 Unit 3 B 3.3-1 B 3.3-1 B 3.3-20 B 3.3-20 B 3.3-21 8 3.3-21 B 3.3-141 B 3.3-142 B 3.3-148 B 3.3-149 B 3.3-149 B. 3.3-150 B 3.3-166 B 3.2-167

Unit 2 TS Bases Pages

RPS Instrumentation B 3.3.1.1 B 3.3 INSTRUMENTATION B 3.3.1.1 Reactor Protection System (RPS) Instrumentation BASES BACKGROUND The RPS initiates a reactor scram when one or more monitored parameters exceed their specified limits, to preserve the integrity of the fuel cladding and the Reactor Coolant System (RCS) and minimize the energy that must be absorbed following a loss of coolant accident (LOCA). This can be accomplished either automatically or manually. The protection and monitoring functions of the RPS have been designed to ensure safe operation of the reactor. This is achieved by specifying limiting safety system settings CLSSS) in terms of parameters directly monitored by the RPS, as well as LCOs on other reactor system parameters and equipment performance. The LSSS are defined in this Specification as the Allowable Values, which, in conjunction with the LCOs, establish the threshold for protective system action to prevent exceeding acceptable limits, including Safety Limits (Sls) during Design Basis Accidents (DBAs). The RPS, as shown in the UFSAR Section 7.2, (Ref. 1), includes sensors, relays, bypass circuits, and switches that are necessary to cause initiation of a reactor scram. Functional diversity is provided by monitoring a wide range of dependent and independent parameters. The input parameters to the scram logic are from instrumentation that monitors reactor vessel water level, reactor vessel pressure, neutron flux, main steam line isolation valve position, turbine control valve (TCV) fast closure trip oil 1 __ _pf~~~ '!r_e_,_ !~t:_b_i_n~ _ ~i:_o_p_ ~~ l ~e_ _<I~~~ _p_o2!!1._o_n_._ 9~,tw_e]1 _________ _

              ,      pressure, scram discharge volume (SDV) water level,                                                             1

1 con de ns e r va cu um , ffi~;W~~!f'$;~~:~#t'...~::'.f:'~'~,~;'.,i¥:~~%:':'~~f~'~p,' ~'. a s we 11 a s :

reactor mode switch in shutdown position, manual scram :

L - - -slgnaTs-,--ar;a-R"P"S-t:esf" swifch-es-:- -nre-re-are--a1-rea-s1-f our- ------ redundant sensor input signals from each of these parameters (with the exception of the manual scram signal and the reactor mode switch in shutdown scram signal). Most channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs an RPS trip signal to the trip logic. c PBAPS UN IT 2 B 3.3-1 Revision No. 0

RPS Instrumentation B 3.3.l.l BASES Af)PLICAl3LE 10. Turbine Condenser-Low Vacuum (continued) SAFETY ANALYSES, LCO, and rurbine Conden'.;er-Low Vacuum signals are initiated from APPLICABILITY four vacuum pressure transmitters that provide inputs to associated trip systems. There are two trip systems and two channels per trip system. Each trip system is arranged in a one-out of-two logic and both trip systems must be tripped in order to scram the reactor. The Turbine Condenser-Low Vacuum Allowable Value is specified to ensure that a scram occurs prior to the integrity of the main condenser being breached, thereby limiting the damage to the normal heat sink of the reactor. Four channels of the Turbine Condenser-Low Vacuum Function with two channels in each trip system, are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this function on a valid signal. This Function is only required in MODE 1 where considerable energy exists which could challenge the integrity of the main condenser if vacuum is low. In MODE 2, the Turbine Condenser-Low Vacuum Function is not required because at low power levels the transients are less severe. r----------------------------------------------------------, I I

u. *

Main stearfbine High RadratiooOeleted I

I Main . steam.~ine~"li9oRadiatAon Functto.~ ensures prompt reaE]tOr s.hutdmm blporr aetecti on 9-P high radi aJi on in th~ v.ieintty* . otthe.mat11.stea11( lines: *.llig.h radiation .in the.' viei.n;lty oJ the ma1.n.*stea$ liQE:!'S .eould, . i.ndi c~te a gross ,fu(Jl* fatlure)n.the core.****.The .scram Js'tnitiated to.}i.mtt tfie f i ssi,OQ . *. pp oduet* .relea~e**.*frqffl t hf;. *fue)*..*.* * .. This Fblnctforri § not* speeifi calJ;,e, crefjitE!d i 8 ar:t)1 *. agcideot analysJs but 1s eetng retained* fpr oy(Jra} l redundaney *and 91 versity of the JWS as *. required tay. thEr NRG.approve.ct licensing Qi:lSi{;* Ma in s.team*. bine . .* ~fg.frRa~i ati 9n signals ar~ Tnttrated

frqm **

four radf~tton Ftiontters .*..* ~ach FHoni tor*senses, M gh. gamma radiation i.n t.he vi cintty of the main. steam line; **.The ~ai tl Steam. L]ne.;..High.RadiattowAllowabJe Value ts selectep>htgh . eneugJi above packgpound: raei atJon

1eve ls to avoict spurious scpam.s, y.et.lo*..;i enough tq; prompt1 y . detect .. a gross rE!) oase qf I I

fission products.*.from the fuel. I

             -----------------------------------------------------------                        con inue I

PBAPS UN IT 2 B 3.3-20 Revision No. 0

RPS Instrumentation B 3.3.1.l BASES ~~~~~~~-+~~~~~~~~~~~~~~~~~~~~~~~~~~~~~* I I APPLICABLE 1r**cji < *MaWrP1*s:te*aiR;"'Ef'i1'e'Y.HW911':"'R'a'~W~'t'le'e;'::.:J~~*oif#'fh'~~ij'~ : SAFETY ANALYSES, I I LCO, and I APPLICABILITY I I I I I I I I I

                         ..                                                                                        I

_~~~~~-----------------------------------------------J

12. Reactor Mode Switch-Shutdown Position The Reactor Mode Switch-Shutdown Position Function provides signals, via the manual scram logic channels, directly to the scram pilot solenoid power circuits. These manual scram logic channels are redundant to the automatic protective instrumentation channels and provide manual reactor trip capability. This Function was not specifically credited in the accident analysis, but it is retained for the overall redundancy and diversity of the RPS as required by the NRC approved licensing basis.

The reactor mode switch is a keylock four-position, four-bank switch. The reactor mode switch is capable of scramming the reactor if the mode switch is placed in the shutdown position. Scram signals from the mode switch are input into each of the two RPS manual scram logic channels. There is no Allowable Value for this Function, since the channels are mechanically actuated based solely on reactor mode switch position. Two channels of Reactor Mode Switch-Shutdown Position Function, with one channel in each manual scram trip system, are available and required to be OPERABLE. The Reactor Mode Switch-Shutdown Position Function is required to be OPERABLE in MODES 1 and 2, and MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, since these are the MODES and other specified conditions when control rods are withdrawn. PBAPS UN IT 2 B 3.3-21 Revision No. O

Primary Containment Isolation Instrumentation B 3.3.6.l B 3.3 INSTRUMENTATION B 3.3.6.l Primary Containment Isolation Instrumentation BASES BACKGROUND The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents CDBAsl. Primary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a OBA. The isolation instrumentation includes the sensors, relays, and switches that are necessary to cause initiation of primary containment and reactor coolant pressure boundary CRCPB) isolation. Most channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs a primary containment isolation signal to the isolation logic. Functional diversity is provided by monitoring a wide range of independent parameters. The r - - - _i_n2!!! _~a_r20~t~r_s_ ,!~ _t_h_e_ j 2<2.l_a_t.] .9~ _l_o_gj s2 _~r_e_ i ~ ~ _r_e_as!<2.t:. _ - - - - - - 1 vessel water level, Cb) reactor pressure, (c) main steam 1 line CMSU flow measurement, Cdl FRain steaFR Tf11e : 1 radlatieA(d~le.i;ed), (e) main steam line pressure, :

____ if 2_e!_rJ.!'I~ l l _P_r_e2 2~r:_e_,_ i 2 ~ _h_i3b _e.r:_e_s_: ,:;t !:~ _c_o222Y].t_ _i!1j ~~t_i_o.!1 ______ ~

CHPCI) and reactor core isolation cooling CRCIC) steam line flow, (h) HPCI and RCIC steam line pressure, (i) reactor water cleanup CRWCU) flow, (j) Standby Liquid Control (SLC) System initiation, Ck) area ambient temperatures, (l) reactor building ventilation and refueling floor ventilation exhaust radiation, and Cm) main stack radiation. Redundant sensor input signals from each parameter are provided for initiation of isolation. Primary containment isolation instrumentation has inputs to the trip logic of the isolation functions listed below. continue PBAPS UN IT 2 B 3.3-141 Revision No. 0

Primary Containment Isolation Instrumentation l3 3.3.6.l BASES APPLICAf3LE 1. c. Main S~!LLLne Fl ow-::ll.i9Jl SAFETY ANALYSES, LCO, and Main Steam Line Flow-High is provided to detect a break of APf)LICABILITY the MSL and to initiate closure of the MSIVs. If the steam (cont*inued) were allowed to continue flowing out of the break, the reactor would depressurize and the core could uncover. If the RPV water level decreases too far, fuel damage could occur. Therefore, the isolation is initiated on high flow to prevent or minimize core damage. The Main Steam Line Flow-High Function is directly assumed in the analysis of the main steam line break CMSLB) (Ref. 3). The isolation action, along with the scram function of the Reactor Protection System (RPS), ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46 and offsite doses do not exceed the 10 CFR 50.67 limits. The MSL flow signals are initiated from 16 transmitters that are connected to the four MSLs. The transmitters are arranged such that, even though physically separated from each other, all four connected to one MSL would be able to detect the high flow. Four channels of Main Steam Line Flow-High Function for each MSL (two channels per trip system) are available and are required to be OPERABLE so that no single instrument failure will preclude detecting a break in any individual MSL. The Allowable Value is chosen to ensure that offsite dose limits are not exceeded due to the break. PBAPS UNIT 2 B 3.3-148 Revision No. 75

Primary Containment Isolation Instrumentation 13 3.3.6.1 l3ASES r--------------------------------------------------------~ APf>LICABLE £,.j;b:::::::+/-1%HP:fufeaerbihe Hf.)§ aaai atfofl**** (E:bnti*fl-0~ : SAFETY ANALYSES, l_CO, a ncl T.h.e****** ~**~*1H . *.~tea rn******. b) r1.e.i Hl.\Jh ~a4fat+oH ~4 qbals§re <fritt i ated. APflUCAf3IUTY '~'.r-OHl .f0H.Y'9 ilft!Ffl.~ ~.efl sttf.V~ >tA.§~fµ~ents .f~Uf .Cha.p~els *. **.*.~.*.Pe

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                    +-A+:S.-rrnfref~sqJ*~***tes*** Ms*tV$.; .Ms~******.*.*.tr~ari:i*s,.*.*.*.*Mst*******.sa*rH~le*****t**~***hes**   1 ane.       ree.i    rculat*foFr>l11op>sampJe.~******~riJ<va.t 1, ________________________________________________________ J                   1r$s;.                               :

l.e Turbine Building Main Steam Tunnel Temperature-High I The Turbine Building Main Steam Tunnel Temperature Function is provided to detect a break in a main steam line and provides diversity to the high flow instrumentation. Turbine Building Main Steam Tunnel Temperature signals are initiated from resistance temperature detectors CRTDs) located along the main steam line between the Reactor Building and the turbine. Twelve channels of Turbine Building Main Steam Tunnel Temperature-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function. The Allowable Value is chosen to detect a leak equivalent to between 1% and 10% rated steam flow. This Function isolates MSIVs, MSL drains, MSL sample lines and recirculation loop sample line valves. l.f. Reactor Building Main Steam Tunnel Temperature-High The Reactor Building Main Steam Tunnel Temperature Function is provided to detect a break in a main steam line and provides diversity to the high flow instrumentation. Reactor Building Main Steam Tunnel Temperature signals are initiated from resistance temperature detectors CRTDs) located in the Main Steam Line Tunnel ventilation exhaust duct. Four channels of Reactor Building Main Steam Tunnel Temperature-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function. continued PBAPS UN IT 2 B 3.3-149 Revision No. 48

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. For Function l.e, 1.f, 3.e, and 4.e channels, verification that trip settings are less than or equal to the specified Allowable Value during the CHANNEL FUNCTIONAL TEST is not required since the installed indication instrumentation does not provide accurate indication of the trip setting. This is considered acceptable since the magnitude of drift assumed in the setpoint calculation is based on a 24 month calibration interval. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

- - - - - - -~- -.;:-c- - - --,- - - - - - - - - - - - - -:--=-------:

I I I A CHANNEL CALIBRATION is a complete check of the instrument I loop and the se~sor. This test verifies the channel : responds to the measured parameter within the necessary 1 range and accuracy. CHANNEL CALIBRATION leaves the channel 1 adjusted to account for instrument drifts between I successive calibrations, consistent with the I the curr t set int methodol I I I I a'!~~!,'i1'lli'ii~!l~~$~i;;§:;;i'i~$i~::r1~1:~,=:1~1~:;*:~.;11(J'.'.'!~'!';;1*1.1;ft:l*iai~ : tA~'i~~~row:*'~\J1f*1t~a:;xdem 0 1n,faeiF1sf**e*t?a~li*lMa***ih4'ijij'fi~* 1 operalthcr* tl~Htir;a*g~,*atlQA* d*a~f!ils;u*~i'.': ir;:e* 1;feiiteimi;H Y: i rr0ii ~*fitSib ** I I , . **e titiq;e Padi@':lttaR . s1;-eehif*

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PBAPS UN IT 2 B 3.3-166 Revision No. 86

Unit 3 TS Bases Pages

RPS Instrumentation B 3.3.1.1 B 3.3 INSTRUMENTATION B 3.3.1.1 Reactor Protection System (RPS) Instrumentation BASES BACKGROUND The RPS initiates a reactor scram when one or more monitored parameters exceed their specified limits, to preserve the integrity of the fuel cladding and the Reactor Coolant System (RCS) and minimize the energy that must be absorbed following a loss of coolant accident (LOCA). This can be accomplished either automatically or manually. The protection and monitoring functions of the RPS have been designed to ensure safe operation of the reactor. This is achieved by specifying limiting safety system settings (LSSS) in terms of parameters directly monitored by the RPS, as well as LCOs on other reactor system parameters and equipment performance. The LSSS are defined in this Specification as the Allowable Values, which, in conjunction with the LCOs, establish the threshold for protective system action to prevent exceeding acceptable limits, including Safety Limits (Sls) during Design Basis Accidents CDBAs). The RPS, as shown in the UFSAR Section 7.2, (Ref. 1), includes sensors, relays, bypass circuits, and switches that are necessary to cause initiation of a reactor scram. Functional diversity is provided by monitoring a wide range of dependent and independent parameters. The input parameters to the scram logic are from instrumentation that monitors reactor vessel water level, reactor vessel pressure, neutron flux, main steam line isolation valve r- _ 22~ ~ t i_o_n.! _ !!!r:b_i!J~ _ '2_q_n_t.r~ ! _v_a_} :!~ _LT_C_VJ _ f~ s_t_ ~l ~~ L+/-_r_e_ ! ~~p- _o~} ___ _

              ,    pressure, turbine stop valve CTSV) position, drywell                                                         :

pressure, scram discharge volume CSDV) water level, 1 condenser vacuum, ~'$'.}ftit'.:?~'.~:@;,a#{::';;lj\:ffe::'.',:i#'a'!ifff'~:,~:~,]ff~\f~~ as we 11 as :

              ,     reactor mode switch i~ shutdo~~ pci~itio~:,~anual scram                                                     :
              - - -5; giiaTs,- aiid'ltP"S-tes-t- swifclfes:- ""Tifere-a"fe- at-re-a-s1-f6u_r_ - - - - - -

redundant sensor input signals from each of these parameters (with the exception of the manual scram signal and the reactor mode switch in shutdown scram signal). Most channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs an RPS trip signal to the trip logic. PBAPS UN IT 3 B 3.3-1 Revision No. O

f~PS Instrumentation [3 3.3.l.l BASES APPLICABLE 10. Turbine Condenser-Low Vacuum (continued) SAFETY ANALYSES, L.CO, and rurbine Condenser-Low Vacuum signals are initiated from APPLICABILITY four vacuum pressure transmitters that provide inputs to associated trip systems. There are two trip systems and two channels per trip system. Each trip system is arranged in a one-out of-two logic and both trip systems must be tripped in order to scram the reactor. The Turbine Condenser-Low Vacuum Allowable Value is specified to ensure that a scram occurs prior to the integrity of the main condenser being breached, thereby limiting the damage to the normal heat sink of the reactor. Four channels of the Turbine Condenser-Low Vacuum Function with two channels in each trip system, are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this function on a valid signal. This Function is only required in MODE 1 where considerable energy exists which could challenge the integrity of the main condenser if vacuum is low. In MODE 2, the Turbine Condenser-Low Vacuum Function is not required because at low power levels the transients are less severe. 1---------------------------------------------------------------1 l I

                                                                                   *1 I                                                                         I continue PBAPS UNIT 3                       B 3.3-20                        Revision No. 0

RPS Instrumentation B 3.3.l.l BASES

                  ------------------------------------------------------~

APP LI CABLE 11= Ma,Bt:-£;teafH Lino High Badi atton (cbntirluedi SAFETY ANALYSES, L.CO, and I ~*r** ch.a.~Ae 1*. s df .Ma.i w.**** St.eam . ****ti*. nfI .....ll.i**.gH******* . Rad4att1Jn******Fur.oti§9 APPUCABIL.ITY vii th twe cha.nnelsJn. e.ach*** . *.*.trtp**.*.sys.tem.;. a*re r~qu.ip~d J~ pe OPERABLf. to ensure tha~*ri.Etsin~Je i Qptryffi.~nt f.aJI~ge.'.:ttlli* p ree:I ua*e: ilscraFR . . fro1H . Jt:iisf.Yncti. p.p***oq .a '~?}J9 i.s.i9n.al* .lhi $ V-u+rctton is.*.* rfqui***r.~ct**tn ~9ges.. J .9nd* 2 .~h.~J'9. con~fd.9.[~b.]:.e energy . exJst. s. such thatsteamis being 11roduc9.d at*.~****.*.rate> wt:! i cJi.co!'.:l) d rel ease . . C\3f1S j dera bl e JJ.ssA \Eln .prod.ucJs frof!l .t hf?. I~ I I I

12. Reactor Mode Switc~-Shutdown Position The Reactor Mode Switch-Shutdown Position Function provides signals, via the manual scram logic channels, directly to the scram pilot solenoid power circuits. These manual scram logic channels are redundant to the automatic protective instrumentation channels and provide manual reactor trip capability. This Function was not specifically credited in the accident analysis, but it is retained for the overall redundancy and diversity of the RPS as required by the NRC approved licensing basis.

The reactor mode switch is a keylock four-position, four-bank switch. The reactor mode switch is capable of scramming the reactor if the mode switch is placed in the shutdown position. Scram signals from the mode switch are input into each of the two RPS manual scram logic channels. There is no Allowable Value for this Function, since the channels are mechanically actuated based solely on reactor mode switch position. Two channels of Reactor Mode Switch-Shutdown Position Function, with one channel in each manual scram trip system, are available and required to be OPERABLE. The Reactor Mode Switch-Shutdown Position Function is required to be OPERABLE in MODES 1 and 2, and MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, since these are the MODES and other specified conditions when control rods are withdrawn. ontinued PBAPS UN IT 3 B 3.3-21 Revision No. 0

Primary Containment Isolation Instrumentation B 3.3.6.l B 3.3 INSTRUMENTATION B 3.3.6.1 Primary Containment Isolation Instrumentation BASES BACKGROUND The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs). Primary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a OBA. The isolation instrumentation includes the sensors, relays, and switches that are necessary to cause initiation of primary containment and reactor coolant pressure boundary CRCPB) isolation. Most channels include electronic equipment (e.g., trip units) that compares measured input signals with pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs a primary containment isolation signal to the isolation logic. Functional diversity is provided by monitoring a wide range of independent parameters. The 1__ J .DP u.t.. ..Pllra!Jle.~I. L t.Q. _t.ti~- is..Q.Jll.tiQll. J..o,.gi C.!i JU~- Ui.L I~a c.t..qy_______ _ 1 vessel water level, (b) reactor pr~ssure, (c) main steam : l ~~~t'~~'.~'~,'~~!9~~'.~fJ~~!~]~s~~~m~~; ~ ~~~a~lf~:~::t;~:;;;:~~:.1 1

                *    (f) drywell pressure, (g) high pressure coolant injection                                              1
                ~- -\HP-C11- ari<f-reacfo_r_ core-isoi affo-n-cooTin9-\R'Ocl-sfe-am-Tirie- - - - --

fl ow, (h) HPCI and RCIC steam line pressure, (i) reactor water cleanup (RWCU) flow, (j) Standby Liquid Control (SLC) System initiation, (k) area ambient temperatures, (l) reactor building ventilation and refueling floor ventilation exhaust radiation, and (m) main stack radiation. Redundant sensor input signals from each parameter are provided for initiation of isolation. Primary containment isolation instrumentation has inputs to the trip logic of the isolation functions listed below. con in e PBAPS UN IT 3 B 3.3-142 Revision No. 3

llr'irnary Containment Isoliltion Instrumentation fl 3.3.6.l l3ASES APPUCABLE L ..£. McJi n SJ.killlL...J i oe r:1 ow-Hi qt1 SAFETY ANALYSES, LCO, and Main Steam Line Flow-High is provided to detect a break of APPLICABILITY the MSL and to initiate closure of the MSIVs. If the steam (continued) were allowed to continue flowing out of the break, the reactor would depressurize and the core could uncover. If the RPV water level decreases too far, fuel damage could occur. Therefore, the isolation is initiated on high flow to prevent or minimize core damage. The Main Steam Line Flow-High Function is directly assumed in the analysis of the main steam line break CMSLB) (Ref. 3). The isolation action, along with the scram function of the Reactor Protection System CRPS), ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46 and offsite doses do not exceed the 10 CFR 50.67 limits. The MSL flow signals are initiated from 16 transmitters that are connected to the four MSLs. The transmitters are arranged such that, even though physically separated from each other, all four connected to one MSL would be able to detect the high flow. Four channels of Main Steam Line Flow-High Function for each MSL (two channels per trip system) are available and are required to be OPERABLE so that no single instrument failure will preclude detecting a break in any individual MSL. The Allowable Value is chosen to ensure that offsite dose limits are not exceeded due to the break. This Function isolates MSIVs, MSL drains, MSL sample lines and recirculation loop sample line valves .

              .----------------------------------------------------------,                   I I

I PBAPS UN IT 3 B 3.3-149 Revision No. 76

Prirnar*y Containrnf~nt I:;olation Instrumentation B 3.3.6.1 BASES r----:-----------------~---------------~---------------1 APPUCAf3LE : ::k-r:Eb-=:Mafn Steam b*ine H~9i9 Badta1j'icm (CEmtinueEl) : SAFETY ANALYSES,* 1 u:o, and : +he Ma~n Steam.lfne~Hfgh Radiafion stgna~s.are initiateq : APPUCABIUTY : f:t::oft) foul" gamma-,.sensitive iA~tru1Mnts *. Feur ehannels' are : 1 avaJlabl e and are .requtredto be OPERABb!t to ensure. that no'

sinile instrument faflur~ ean preelude.the ~solatian funct~oA, The Allo1tJable Value is chosen to* ensure .that of:fsi te. dose*

                  ++mi ts are no.t exc.eeded~

Thi Ei. r:~ne~.~ on isolates MS IVs, MSL drafAs, MSb siHApTe lines and recirculatior11oop samf)te line valves, ,

                *-------------------------------------------------------~

l.e. Main Steam Tunnel Temperature-High The Main Steam Tunnel Temperature Function is provided to detect a break in a main steam line and provides diversity to the high flow instrumentation. Main Steam Tunnel Temperature signals are initiated from resistance temperature detectors CRTDsl located along the main steam line between the drywell wall and the turbine. Sixteen channels of Main Steam Tunnel Temperature-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function. The Allowable Value is chosen to detect a leak equivalent to between 1% and 10% rated steam flow. This Function isolates MSIVs, MSL drains, MSL sample lines and recirculation loop sample line valves. This Function in Unit 3 combines Unit 2 Functions l.e. and l.f. Primary Containment Isolation 2.a. Reactor Vessel Water Level-Low (Level 32 Low RPV water level indicates that the capability to cool the fuel may be threatened. The valves whose penetrations communicate with the primary containment are isolated to limit the release of fission products. The isolation of the primary containment on Level 3 supports actions to ensure that offsite dose limits of 10 CFR 50.67 are not exceeded. rcontinue PBAPS UN IT 3 B 3.3-150 Revision No. 76

Primary Containment Isolation Instrumentation B 3.3.6.l BASES SU RV EI U_ANCE SR 3.3.6.1.2 l~EQIJ I REMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel wi 11 perforrn the intended function. Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology. fhe Surveillance Frequency is controlled under the Surveillance Frequency Control Program. r-----------------------------------------------------------,

                '    SR  :3.J'.6<L.3. SR J.3L6.1;A, and SR   J.3.6.1..5. and*.,*.     :

SR 3.3.6~1r6 : A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the f the current set int methodol I

                '-----------------------------------------------------------~

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. cont*i nue PBAPS UN IT 3 B 3.3-167 Revision No. 87

Attachment 4 Peach Bottom Atomic Power Station, Units 2 and 3 NRC Docket Nos. 50-277 and 50-278 Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Trip Function PBAPS Calculation PM-1057, "EAB, LPZ, and CR Doses due to Control Rod Drop Accident (CRDA}," Revision 5

CC-AA-309-1001 Revision 8 AITACHMENT 1

A nalIYSi S Cover Sh eet Des urn Design Analysis J Last Page No. 6 102 Analysis No.: 1 PM-1057 Revision: 2 5 Major~ MlnorD

Title:

3 EAB, LP7., and CR , Doses due to Control Rod Drop Accident (CRDA) (Task T0901) EC/ECR No.: 4 l~-nD4Cl4 Revi~ion: 5 {") Station(s): 7 Peach Bottom Component(s): 14 Unit No.: 8 NIA 2 and3 Discipline: 9 Mech Descrip. Code/Keyword: 10 EPU;AST Safety/QA Class: 11 SR System Code: 12 912 Structure: 13 NIA CO:STROLLED DOCUMENT REFERENCES 15 Document No.: Fromfro Document No.: From/To UFSAA Section 14.9.2.4 & Tables 14.9.6 PM-lOSS From To "14.9.7 PEAM-EPU-63 From PM-1168 From PM-0982 From PEAM-EPU-67 From 16 Is this Design Analysis Safeguards Information? YesD ..Ho181 Ifyes, see SY-AA-101-106 17 Ifyes, Docs this Design Analysis contain Unvcrili:.:d Assumptions? YesO No181 ATI/AR#: This Design Analysis SUPERCEDF.S: 111 ' NIA in its entirety.

'Description of Revision (list changed pag~s "'h~n *II pages of original analysis-Were not changed):       19 Revision 5 evaluates the r.uliological impacr of deletfon of the MSIV closure function of main steam line radiation monitor (MSLRM) on the Control Rod Drop Accident (CRDA).

I Preparer: 20 Gopal J, Patel (NUCORE)

                                                                             *~                 ~

0711412014 Print Name Si I Date Method of Review: 21 Detailed Review 181 Alternate Calculat)Ohs_{a ) TestingO Reviewer: 22 Mark I. Drucker (NUCORE) N~/ ,,;..-,. - 0711412014

              .                 Print Name                               Sif, Name                                          Date Review Notes: 13                Independent re\*iew 181          Peer review 0 (For External Aulyses Only)

External Approver: 24 Print Name Sign Name Date 25 Exelon Reviewer: Print Name Sil!ll Name Date Independent 3n1 Party Review Rcqd~ Exelon Approver: 17 ::X-e.; cA . Yes!XJ I '2Q...Y"V NoO\ rwe P>y : Arn'j Hl.lbC.r ~ ~ ~ 7{1i/1+ cP /"--'\ 7/:21/1¥ Print Name Sia n Name? Date ' (/

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 2of102 REVISION HISTORY Revision Description 0 Initial issue 1 Revised Section 2. 7, Section 6.2, and Attachment B to use CR normal intake flowrate of 20,600 cfm plus 1600 cfm for inleakage; Section 2.5.3 to elaborate on Sealing Steam System release treatment; Section 4.1 and Section 6.2, corrected Control Room dispersion coefficients; Section 5, added references 13 & 14 drawings to support CR normal intake flowrates and sealing steam assumptions; Section 7 to show corrected CR dose. 2 Rev 2 to incorporates year 2008 NRC Requests for Additional Information for Regulatory Guide 1.23 Revision 1 compliance and use of conservatively high meteorological tower IA based X/Q values. 3 This revision evaluates the effects of extended power uprate and to reduce CR unfiltered inleakage from 1600 to 500 cfm. This revision is a complete re-write. This revision is performed using the guidance in Regulatory Guide 1.183, with updated parameters regarding GNF2 fuel for EPU. 4 Revision 4 to incorporate the gap fractions of 10% for iodine and noble gases per Note 11 of Table 3 of Regulatory Guide 1.183. 5 This revision evaluates the radiological impact of deletion of the MSIV closure function of main steam line radiation monitor (MSLRM) on the Control Rod Drop Accident (CRDA).

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 3of102 SHEET REVISION INDEX SHEET REV SHEET REV I 5 35 5 2 5 3 5 4 5 Attachment 13.1 5 5 5 Attachment 13.2 5 6 5 Attachment 13.3 5 7 5 Attachment 13.4 5 8 5 Attachment 13.5 5 9 5 Attachment 13.6 5 10 5 11 5 12 5 13 5 14 5 15 5 16 5 17 5 18 5 19 5 20 5 21 5 22 5 23 5 24 5 25 5 26 5 27 5 28 5 29 5 30 5 31 5 32 5 33 5 34 5

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 4 of 102 TABLE OF CONTENTS Section Sheet No. Cover Sheet 1 Revision History 2 Page Revision Index 3 Table of Contents 4 1.0 Purpose 5 2.0 Methodology 5 3.0 Acceptance Criteria 10 4.0 Assumptions 11 5.0 Design Inputs 15 6.0 Computer Codes & Regulatory Compliance 19 7 .0 Calculations 20 8.0 Results Summary & Conclusions 22 9.0 References 23 10.0 Tables 25 11.0 Figures 31 12.0 Affected Documents 35 13.0 Attachments 35 13.1 RADTRAD Output File: PCRDACON05.o0 36 13.2 RADTRAD Output File: PCRDAGLD05.o0 52 13.3 RADTRAD Nuclide Inventory File: PBCRDA3_def.txt 68 13.4 RADTRAD Nuclide Inventory File: PBCRDA_GLD_def.txt 78 13.5 RADTRAD Release Fraction and Timing File: pbcrda_rft.txt 88 13.6 RADTRAD Dose Conversion Factor File: pbcrda_fgl 1&12.txt 89 l st Pass Attributes - General Overview 100 251 Pass Attributes - Technical Review 101 3rd Pass Attributes - Administrative 102

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 5of102

1.0 PURPOSE

The purpose of this calculation is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room (CR) doses due to a Control Rod Drop Accident (CRDA) using the Alternative Source Term (AST) methodology, the TEDE dose criteria of 10 CFR 50.67 (Ref. 9.4), Guidance in RG 1.183, Appendix C and NED0-3 l 400A, and the extended power uprate (EPU) core inventory assuming the main steam line radiation monitors (MSLRM) no longer provide a signal for automatic closure of the main steam isolation valves (MSIV). Peach Bottom Atomic Power Station (PBAPS) has implemented a "Banked Position Withdrawal Sequence (BPWS)" CRDA withdrawal sequence that maintains the rod worths to such low values that peak fuel enthalpies do not threaten the design or fuel cladding failure threshold, thereby eliminating the need for a CRDA analysis (Ref. 9.16, Section 3.12.2). Therefore, the CRDA is analyzed for information only using the bounding current licensing basis damaged and melted fuel information with the uprated core inventory. Revision 5: This revision evaluates the radiological impact of deletion of the MSIV closure function of main steam line radiation monitor (MSLRM) on the Control Rod Drop Accident (CRDA).

2.0 METHODOLOGY

Post-CRDA Release Paths At the request of the BWR Owners Group, General Electric prepared NED0-31400A (Ref. 9.12) to provide an analysis to prove that the elimination of the MSIV closure and scram function of the MSLRM, in conjunction with use of the augmented offgas system (AOG), results in offsite doses that are less than allowable guidelines, even when using very conservative source terms. The analysis in NED0-31400A and this analysis for the PBAPS address the CRDA because it is a Design Basis Accident taking credit for MSIV closure on high radiation in the steam lines. This calculation will utilize the NED0-31400A report to analyze the two release scenarios evaluated there, but applied to the PBAPS. Also, the calculation will address other plant specific release paths namely the Gland Sealing Steam System and mechanical vacuum pump release at low power level that were not included in NED0-31400A. The NEDO used the most bounding parameters from all participating plants (including PBAPS) to analyze the effects of removing the MSIV isolation function of the MSLRM. Participating BWR licensees, including the PBAPS (Ref. 9.12, Safety Evaluation Section 3.0, and Table 1) may reference NED0-31400A in support of their licensing applications provided that the applicant demonstrates that the assumptions with regard to input values (including power per assembly, xJQ, and decay times) that are made in the generic analysis bound those for the plant. The following potential post-CRDA release paths were reviewed to determine the most limiting combination of the credible release paths as a result the MSIVs remain open during a CRDA: As indicated in NED0-31400A, two alternative scenarios (1 & 2) are considered for the CRDA.

1. An isolated Main Condenser (MC) is assumed to exhaust the post-CRDA activity as a ground level release at a rate of 1 % per day (Ref. 9.1, Appendix C, Section 3.4 and Ref. 9.12, Safety Evaluation Section 2.1). No credit is taken for dilution or holdup within the turbine building.

Radioactive decay during holdup in the turbine is not assumed (i.e., the activity is instantaneously transported to the condenser). Radioactive decay during holdup in the condenser

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 6of102 (associated with a release rate of 1% per day rather than an instantaneous release to the environment) is assumed (Ref. 9.1, Appendix C, Section 3.4).

2. For the second case, which involved a release without the automatic MSIV trip, the methods of analysis are the same as that used for the first case except for those that pertain to the release path. For this case, the calculations assumed that the MSIVs do not close and that steam flow continues for some time, approximately 24 hours, before this path is isolated. If the event occurs at low power and the steam jet air ejector (SJAE) does not operate, the offsite dose is equivalent to that of the first case because the total activity is assumed to be transferred to the condenser instantaneously. If sufficient power is available for the SJAE operation, some of the available activity is pumped into the augmented offgas system (AOS) and, thus, provides a different release path to the environment. The charcoal beds in the augmented offgas system, however, ensure that the iodine is retained. The noble gases are held for significant decay times before release from the stacks. The amount of the decay time depends on the system design.

The following two additional PBAPS design-specific release paths (3 & 4) that are not included in NED0-31400A are addressed as follows:

3. During the low power operating conditions there are forced flow paths from the Turbine/Condenser. For instance, the CRDA can occur during mechanical vacuum pump (MVP) operation, which can exhaust an unprocessed release from the condenser at a significantly larger rate. Since the MSLRM trip function of MVP is retained, this release path is subsequently ruled out in this section of this calculation because:

1. The MVP operates to establish the main condenser vacuum when core thermal power level is expected to be less than 5%, which provides a CRDA source term reduction factor of 20 for the 100% core thermal level source term used for the post-CRDA main condenser release.

2. The post-CRDA activity is instantly released to the condenser and further diluted in a condenser volume of approximately 235,000 ft 3 . The dilution in the condenser volume is conservatively not credited in the main condenser release.

3. The MVP exhausts the condenser air at a rate of approximately 2,000 cfm to the offgas stack (elevated release) having 0-2 hour -x}Q value of 3.3 lE-06 m/sec 3 (Ref. 9.5, Table 5-1), which is substantially lower than the MCR x!Q value of l.18E-03 m/sec 3 for a main condenser release through the reactor building stack which is treated as a ground level release, until the MSLRM trip occurs to isolate the MVP exhaust pathway.

4. The MVP operates for a considerably shorter duration (due to its trip and isolation) than the 24-hour main condenser release during the power ascension.

The effect of these compensating conservatisms for the MVP release path is such that the resulting doses will be considerably smaller than rounding error.

4. The only other release path not automatically isolated on this event is via the Turbine Gland Seal Condenser (GSC). For the turbine gland seal release, the reactor steam containing the CRDA source is assumed to pass through the turbine seals and condense in the gland seal condenser. In the analysis, no credit is taken for partitioning of radioiodine between the air and condensed steam, i.e., all iodines and noble gases in the steam are released to the environment.

As per the discussion in the above section, the three (3) credible release paths that exist during a

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 7of102 CRDA are through the isolated main condenser, SJAE, and gland seal condenser. The SJAE release path exists when there is enough steam pressure available to sustain its operation. Only either the SJEA or isolated MC release path exists at a time. The operation of the SJEA maintains the MC sub-atmospheric, and thereby eliminates the potential for a release through the isolated MC. The CRDA occurring at a low power level secures the operation of the SJEA, which pressurizes the MC and establishes a post-CRDA release path. The GSC is operational as long as there is pressurized steam available during the CRDA event. Since the MSIV is postulated to remain open for 24 hours, the reactor decay heat continues to produce a good amount of steam and thereby establishes the GSC release path irrespective of MC or SJEA operation. Consequently, the two possible combinations of release paths that may exist at any time during a CRDA event are:

1. The isolated main condenser and gland seal condenser release paths.

2. The SJEA and seal condenser release paths.

The resulting post-CRDA doses are combined accordingly for these combination of releases in Section 8.1. In both the scenarios 2 & 4, the post-CRDA gap activity in the reactor coolant (Table 2, Column D) is assumed to release without being further reduced in the condenser volume like in the case of isolated condenser release (Table 2, Column F). 2.1 CRDA Source Term Consistent with Reference 9 .1, Appendix C, Section 1, the release from the breached fuel is based on the estimate of the number of fuel rods breached and the assumption that 10% of the core inventory of the noble gases and iodines is in the fuel gap. The release attributed to fuel melting is based on the fraction of the fuel that reaches or exceeds the initiation temperature for fuel melting and on the assumption that 100% of the noble gases and 50% of the iodines contained in that fraction are released to the reactor coolant. Consistent with Reference 9.1 Tables 3 and 5, the CRDA gap release consists of halogens (iodine and bromine), noble gases (krypton and xenon), and alkali metals (cesium and rubidium). Non-iodine halogen isotopes (e.g., Bromine) are not modeled due to their short half lives and because RG 1.183 (Ref. 9.1, Appendix C, Sections 3.3 and 3.4) only addresses iodine and noble gas transport from the damaged fuel through the turbine and to the condenser, not bromine releases. This calculation models the release in two parts. The first part is due to the activity released from the fuel gap in the damaged fuel rods. The isotopic activities for the different groups of radionuclides in the damaged fuel rods are calculated in Table 1 using the uprated core inventory, peaking factor, and number of fuel rods damaged during the CRDA. 2.2 Activity Release This calculation uses the gap activity inventory fractions of 10% for iodines and noble gases and 12% for the alkali metals consistent with RG 1.183 Table 3 and Note 11. The melted fuel fraction of 25% is applied to the alkali metals per RG 1.183 Table 1. Per Reference 9.18, Section 4.2.1.3.2, in a severe reactivity initiated accident such as a BWR control rod drop, the large and rapid deposition of energy in the fuel can result in fuel melting, fragmentation, and violent dispersal of fuel droplets or fragments into the primary coolant. The prevention of widespread fragmentation and dispersal of fuel and the avoidance of pressure pulse generation within the reactor vessel, a radially averaged enthalpy limit of 280 cal/g should be observed. Per RG 1.183, Appendix C, Section 1, 100% of the noble gases and 50% of the iodine contained in the fuel melting fraction are released to the reactor coolant (RC).

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 8of102 Similarly, 25% of the alkali metals is postulated to release to the RC due to fuel melting, which is the same as the core alkali metals inventory fraction released into containment during a LOCA (RG 1.183, Table 1). The peak post-CRDA core isotopic activities in 1200 damaged fuel rods are calculated in Table 1 using the core isotopic activities, core thermal power level, peaking factor, number of damaged fuel rods, and total number of fuel rods in the core. The composite gap fractions for iodine, noble gas, and alkali metals are calculated in Section 7 .1 using the gap and melted fuel release fractions. These release fractions are applied to the post-CRDA peak isotopic activities in the damaged fuel rods calculated in Table I to obtain the isotopic gap activities in the damage fuel rods available to release into the reactor coolant (RC). The post-CRDA isotopic activities in the RC and isolated condenser are calculated in Table 2, Columns "D" & "F", respectively, using the appropriate release fractions. The RC activities are used with the SJAE and gland seal condenser release paths and the condenser activities are used with the isolated condenser release path. The RADTRAD Nuclide Inventory Files (NIFs) PBCRDA_GLD_def.txt (Table 2, Column "D") and PBCRDA3_def.txt (Table 2, Column "F") are created to be used with the post-CRDA releases. 2.3 RADTRAD Release Models This analysis uses Version 3.03 of the RADTRAD computer code to calculate the potential radiological consequences of the CRDA. The RADTRAD code was developed by Sandia National Laboratories, the NRC's technical contractor, for the staff to use in establishing fission product transport and removal models and in estimating radiological doses at selected receptors at nuclear power plants. The RADTRAD3.03 code is documented in NUREG/CR-6604 (Ref. 9.2) and maintained as Exelon Software ID Number EX0004754 (Ref. 9.11). The consequences of a CRDA are analyzed using the plant specific as-built design and licensing bases inputs, which are compatible to the AST and TEDE dose criteria. The post-CRDA activity from the turbine and condenser is postulated to directly release to the environment at the ground level release as shown in Figure 1. The x/Qs for these release paths are obtained listed in Design Input sections 5.3.3.7 (CR) and 5.3.4 (offsite locations). The Control Room Emergency Ventilation (CREV) system is not credited in the analysis. The CR is assumed to operate in a normal mode of operation with a maximum HY AC inflow rate of 20,600 cfm (Design Input section 5.3.3.2) plus an additional unfiltered inleakage of 500 cfm for the entire duration of the accident. The resulting doses at the EAB, LPZ, and CR locations are compared with the dose acceptance criteria in Section 8.0. The RADTRAD V3.03 (References 9.2 & 9.11) nuclide inventory files (NIFs) PBCRDA_GLD_def.txt

     & PBCRDA3_def.txt are developed using the actual activity in curies released to the environment from the RC and condenser; therefore, the thermal power level is set to unity in the RADTRAD input. The release fraction and timing file (pbcrda_rft.txt) is used to postulate an instantaneous post-CRDA release.

The RADTRAD V3.03 dose conversion factor (DCF) File (pbcrda_fgll&l2.txt) is based on DCFs obtained from References 9.7 & 9.8. Both the NIF and DCF files are modified to include additional significant radionuclides. 2.3.1 Isolated Condenser Release: As discussed in Section 2.0 above, the post-CRDA activity is homogeneously mixed in the RCS (Table

2) and transported to the main steam condenser (MSC) before the reactor is assumed to be scrammed in 10 minutes, with an assumed release rate of 276 cfm (Section 7.3). The post-CRDA activity in the MSC is available to release to the environment via the main steam condenser at a rate of 1 volume percent per day for 24 hours as shown in Figure 1. The activity is postulated to leak from the MSC via the Turbine

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 9of102 Building to the environment as an unfiltered ground release, with worst case xJQs derived in Reference 9.5. The MSC release path is modeled in RADTRAD input file PSF PCRDACONOS.psf using the NIP File pbcrda3_def.txt, RFf File pbcrda_rft.txt, and DCF File pbcrda_fgl 1&12.txt. TheMSCreleasepathis shown in Figure 1. The resulting doses from the MSC release path are listed in Section 8.0 and combined with other release paths to determine the most limiting release combination. Reactor Coolant to Main Steam Condenser Per Section 7.3, with the Reactor Coolant volume set to the nominal value of l ft3, a flow rate of 276 cfm is modeled to transfer 99% of the reactor coolant activity to the Main Condenser within l second (Figure 1). Main Steam Condenser Release Release from the Main Steam Condenser is assumed to be l % of MSC volume per day at ground level without credit for dilution or holdup in the Turbine Building as shown in Figure 1. 2.3.2 Augmented Offgas System Release: A second scenario is for a CRDA assumed to occur during SJAE operation. In this Scenario, activity is released to a system of Charcoal Delay Beds, where iodine and particulate are effectively removed and only a delayed release of noble gas nuclides occurs. Although this release pathway (like the gland seal release) would be through the Station Chimney, for conservatism this release pathway is treated as a ground level release with its higher xJQs. This pathway is assessed using a spreadsheet crediting elimination of Iodine & particulate releases and a delay of noble gas releases by the augmented off-gas system charcoal delay beds. The activated charcoal adsorber beds are used to delay the discharge of noble gases. The activated charcoal adsorber beds provide a retention time of 401 hours for xenon holdup and 34 hours for krypton holdup (Reference 9.6, Section 7.5.0). The noble gas activity is decayed in the charcoal adsorber beds using the following equation: A= A 0 x exp (-A.x t) where: A = nuclide activity after decay period (Ci) Ao= initial nuclide activity (Ci) exp = exponential constant A.= decay constant (hours- 1) t =time of delay (hours) The decayed noble gas activities are multiplied by the noble gas immersion dose conversion factors (DCF), applicable dispersion factor (xJQ), and (for the control room dose location) geometry factor. Of note is that the TEDE dose is the sum of the immersion DDE dose plus the inhalation CEDE dose. The noble gas isotopes that are released do not contribute to the inhalation dose. Therefore, the noble gas TEDE dose is equivalent to the noble gas DDE dose, and it is appropriate to apply the CR Geometry Factor to the noble gas TEDE dose. The SJAE release path is shown in Figure 2. The resulting doses due to the SJAE release pathway are calculated at each respective dose location following a CRDA (see Tables 3 through 6). The resulting doses from the SJAE release path are listed in Section 8.0 and combined with other release paths to determine the most limiting release combination.

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 10of102 2.3.3 Gland Seal Condenser Release For the Turbine Gland Seal Condenser release path, the fraction of activity released from reactor coolant that is transferred to the gland seal condenser (extraction steam) is 0.15% (per Section 7.4). This release path is not automatically isolated by the MSLRM, therefore, the dose contribution from this release path will be added to the isolated MSC and augmented offgas system paths. The reactor steam containing the CRDA source is assumed to pass through the turbine seals and into the gland seal condenser without any partitioning of the radioiodine and particulates. Although the releases would be through the Station Chimney, for conservatism they are assumed to be at ground level through the MSIV leakage path used in the current AST LOCA calculations. Per Sections 2.3.1 and 7 .3, the reactor coolant activity release rate to the Main Steam Condenser is modeled as 276 cfm. Therefore, the reactor coolant to environment release rate via the gland seal condenser is modeled as 0.414 cfm (= 0.0015 x 276 cfm) and the balance of 275.59 cfm (= 276 cfm - 0.414 cfm) is postulated to release to the MSC as shown in Figure 2. The GSC release path is modeled in RADTRAD input file PSF PCRDACON05.psf using the NIF File pbcrda_gld_def. txt, RFT File pbcrda_rft.txt, and DCF File pbcrda_fg 11 & 12.txt. The GSC release path is shown in Figure 3. The resulting doses from the GSC release path are listed in Section 8.0 and combined with other release paths to determine the most limiting release combination. 2.3.4 Additional Releases Through Drain & Sample Lines The main steam line radiation monitors (MSLRM) no longer provide a signal for automatic closure of the main steam line drain valves and main steam and reactor water (RW) sample line valves, which establishes an unprocessed release to the environment. The dose consequences of post-CRDA reactor water sample line release is calculated in Reference 9.24, Section 8.1. These dose consequences are additional doses occurring during a CRDA as a result of the modification proposed with the MSLRM and added to the doses occurring from other post-CRDA release paths in Section 8.1. 3.0 ACCEPTANCE CRITERIA The following NRC regulatory requirement and guidance documents are applicable to this PBAPS CRDA analysis:

RG 1.183 (Ref. 9.1, Table 6)
10CFR50.67 (Ref. 9.4)
Standard Review Plan section 15.0.1(Ref.9.14)

Dose Acceptance Criteria are: Regulatory Dose Limits Dose Type Control Room EAB and LPZ (rem TEDE) (rem TEDE) TEDE Dose 5 6.3

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 11 of 102

4.0 ASSUMPTIONS

Assumptions for Evaluating the Radiological Consequences of a Control Rod Drop Accident (CRDA) The assumptions in these sections are acceptable for evaluating the radiological consequences of a CRDA. These assumptions supplement the guidance provided in Regulatory Guide 1.183, Appendix C (Ref. 9.1). These assumptions are incorporated as design inputs in Sections 5.0 for the CRDA analysis. There are no unvalidated assumptions used in this calculation. Source Term Assumptions 4.1 Per Reference 9.20, Section 3.7, in the event of a CRDA 1200 fuel rods are breached. It is conservatively assumed that 5.00 percent of these breached rods experience fuel melt; the assumed 5.00% melt exceeds the 0.77% melt modeled in the previous analysis of record per UFSAR Section 14.9.2.4 (Reference 9.21). Per Reference 9.3 Section 3.2.1 Item #2 there are 764 fuel assemblies contained in the reactor core, and per Reference 9.19, Section 10.2 there are 85.6 fuel rods in each reactor assembly. 4.2 Per Reference 9.1, Appendix C, Section l, the release from the breached fuel to the coolant is based on Regulatory Position 3 and the estimate of the number of fuel rods breached. 4.3 Per Reference 9.1, Appendix C, Section 3.1, the activity released from either the gap or from fuel pellets is assumed to be instantaneously mixed in the reactor coolant within the pressure vessel. 4.4 Per Reference 9.1, Appendix C, Section 3.2, credit is not assumed for partitioning in the pressure vessel or for removal by the steam separators. 4.5 Per Reference 9.1, Appendix C, Section 3.3, of the activity released from the reactor coolant within the pressure vessel, 100% of the noble gases, 10% of the iodine, and 1% of the remaining radionuclides are assumed to reach the turbine and condensers, which is incorporated as a design input in Section 5.3.1.8. 4.6 Per Reference 9.1, Appendix C, Section 3.4, of the activity that reaches the turbine and condenser, 100% of the noble gases, 10% of the iodine, and 1% of the particulate radionuclides are available for release to the environment, which is incorporated as a design input in Section 5.3.1.9. The turbine and condenser leak to the atmosphere as a ground-level release at a rate of 1% per day for a period of 24 hours, at which time the leakage is assumed to terminate (incorporated as design inputs in Sections 5.3.2.1 through 5.3.2.3). To facilitate RADTRAD modeling, the condenser is modeled with an arbitrary volume of 1 cubic feet upon which the 1% per day leak rate is applied. Any value of the condenser volume can be used, which will result in the same Ci/sec release rate. No credit is taken for dilution or holdup within the turbine building, which is incorporated as a design input in Section 5.3.2.6. Radioactive decay during holdup in the turbine is not assumed (i.e., the activity is instantaneously transported to the condenser). Radioactive decay during holdup in the condenser (associated with a release rate of 1% per day rather than an instantaneous release to the environment) is assumed. Per Reference 9.1, Appendix C, Note 2, the forced flow paths of augmented offgas system (Section 2.3.2) and gland seal condenser (Section 2.3.3) are analyzed. 4.7 Per Reference 9.1, Appendix C, Section 3.6, the iodine species released from the reactor coolant within the pressure vessel is assumed to be 95% Csl as an aerosol, 4.85% elemental, and 0.15% organic, which is incorporated as a design input in Section 5.3.2.4. The release from the turbine and condenser is assumed to be 97% elemental and 3% organic, which is incorporated as a design input in Section 5.3.2.5. Offsite Dose Consequences: Regulatory Guide 1.183 (Ref. 9.1, Section 4.1) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located at the exclusion area boundary (EAB) and at the outer boundary of

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 12of102 the low population zone (LPZ). The following sections address the applicability of this guidance to the PBAPS CRDA analysis. These assumptions are incorporated as design inputs in Sections 5.3.1 through 5.3.4. The following guidance is used in determining the TEDE for a maximum exposed individual at EAB and LPZ locations: 4.8 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.1) that the dose calculation determines the TEDE, which is the sum of the committed effective dose equivalent (CEDE) from inhalation and the deep dose equivalent (DDE) from external exposure; and these two components of the TEDE consider all radionuclides, including progeny from the decay of parent radionuclides that are significant with regard to dose consequences and the released radioactivity. These isotopes are incorporated as a design input in Section 5.3.1.2. 4.9 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.2), that the exposure-to-CEDE factors for inhalation of radioactive material are derived from the data provided in ICRP Publication 30, "Limits for Intakes of Radionuclides by Workers". This calculation models the CEDE dose conversion factors (DCFs) in the column headed "effective" yield doses in Table 2.1 of Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion" (Ref. 9.7). 4.10 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.4), that Table 111.1 of Federal Guidance Report 12, "External Exposure to Radionuclides in Air, Water, and Soil" (Ref. 8), provides external EDE conversion factors acceptable to the NRC staff. The factors in the column headed "effective," yield doses corresponding to the EDE. 4.11 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.3), that for the first 8 hours, the breathing rate of persons offsite should be assumed to be 3.5 x 10*4 cubic meters per second. From 8 to 24 hours following the accident, the breathing rate is assumed to be 1.8 x 10*4 cubic meters per second. After that and until the end of the accident, the rate is assumed to be 2.3 x 10*4 cubic meters per second. The breathing rate of an individual at the EAB is assumed to be 3.5 x 10*4 cubic meters per second for the duration of the event. These offsite breathing rate assumptions are incorporated as design inputs in Sections 5.3.4.3 and 5.3.4.4. 4.12 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.5), that the TEDE is determined for the most limiting person at the EAB. The maximum EAB TEDE for any two-hour period following the start of the radioactivity release is determined and used in determining compliance with the dose criteria in 10 CFR 50.67 (Ref. 9.4). For the CRDA the postulated EAB doses should not exceed the criteria established in RG 1.183 Section 4.4 and Table 6. This assumption is incorporated as a design input in Section 5.3.4.5. EAB Dose Acceptance Criterion: 6.3 Rem TEDE The RADTRAD3.03 Code (Ref. 9.2) used in this analysis determines the maximum two-hour TEDE by calculating the postulated dose for a series of small time increments and performing a "sliding" sum over the increments for successive two-hour periods. The time increments appropriately reflect the progression of the accident to capture the peak dose interval between the start of the event and the end of radioactivity release. It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.5), that the maximum 2-hour EAB x!Q occurs for the entire duration of the release to the environment to ensure that the limiting case is identified. The 2-hour EAB XIQ is incorporated as a design input in Section 5.3.4.1. 4.13 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.6), that the TEDE is determined for the most limiting receptor at the outer boundary of the low population zone (LPZ) and is used in determining compliance with the dose criteria in 10 CFR 50.67 (Ref. 9.4). For the CRDA the postulated LPZ doses should not exceed the criteria established in RG 1.183 Section 4.4 and Table 6. This assumption is incorporated as a design input in Section 5.3.4.6.

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 13of102 LPZ Dose Acceptance Criterion: 6.3 Rem TEDE 4.14 No correction is made for depletion of the effluent plume by deposition on the ground (Ref 9.1, Section 4.1.7). Control Room Dose Consequences The following guidance is used in determining the TEDE for maximum exposed individuals located in the control room: 4.15 Regulatory Guide 1.183 (Ref. 9 .1, Section 4.2) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located in the control room (CR). The following sections address the applicability of this guidance to the PBAPS CRDA analysis. 4.16 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.1), that the CR TEDE analysis should consider the following sources of radiation that will cause exposure to control room personnel:

Contamination of the control room atmosphere by the intake or infiltration of the radioactive material contained in the post-accident radioactive plume released from the facility (via CR air intake),
Contamination of the control room atmosphere by the intake or infiltration of airborne radioactive material from areas and structures adjacent to the control room envelope (via CR unfiltered inleakage ),
Radiation shine from the external radioactive plume released from the facility (external airborne cloud),
Radiation shine from radioactive material in the reactor containment (containment shine dose),
Radiation shine from radioactive material in systems and components inside or external to the control room envelope, e.g., radioactive material buildup in recirculation filters (CR filter shine dose).

Air introduced via the CR air intake is addressed in Design Input 5.3.3.2. Air introduced via CR unfiltered inleakage is addressed in Design Input 5.3.3.4. Radiation shine from the external airborne cloud is negligible because less than 2% (1,200/65,398 x 100% = 1.8%) of total fuel rods are damaged and 60 (0.05 x 1,200 = 60) rods are melted. The CRDA does not release radioactive material in the reactor containment, so there is no containment shine dose. The safety-related CR emergency ventilation system is not credited for dose mitigation, so there is no CR filter shine dose. 4.17 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.2), that the radioactive material releases and radiation levels used in the control room dose analysis are determined using the same source term, in-plant transport, and release assumptions used for determining the EAB and the LPZ TEDE values. These parameters do not result in non-conservative results for the control room. 4.18 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.6), that the CR dose receptor is the hypothetical maximum exposed individual who is present in the control room for 100% of the time during the first 24 hours after the event, 60% of the time between 1 and 4 days, and 40% of the time from 4 days to 30 days. For the duration of the event, the breathing rate of this individual should be assumed to be 3.5 x 10-4 cubic meters per second. These assumptions are incorporated as design inputs in Sections 5.3.3.5 and 5.3.3.6. 4.19 It is assumed consistent with RG l.183 (Ref. 9.1, Section 4.4 and Table 6), that the postulated CR dose should not exceed the 5 Rem TEDE criterion established in 10 CFR 50.67 (Ref. 9.4). This assumption is incorporated as a design input in Section 5.3.3.8. CR Dose Acceptance Criteria: 5 Rem TEDE

CALCULATION NO. PM-1057 REV. No. S PAGE NO. 14of102 4.20 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.4), that engineered safety features (ESF) that mitigate airborne radioactive material within the control room may be credited. Such features include control room recirculation filtration. For this analysis, CR filtration is not credited.

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 15 of 102 5.0 DESIGN INPUTS: 5.1 General Considerations 5.1.1 Applicability of Prior Licensing Basis The PBAPS current licensing basis (CLB) for the CRDA event is AST methodology per Amendments 269 and 273 (Ref. 9.9) based on Regulatory Guide 1.183 guidance. This revision of the CRDA analysis uses the CLB AST guidance in Regulatory Guide 1.183, Appendix C (Ref. 9.1). 5.1.2 Credit for Engineered Safety Features Credit is taken only for accident mitigation features that are classified as safety-related, are required to be operable by technical specifications, are powered by emergency power sources, and are either automatically actuated or, in limited cases, have actuation requirements explicitly addressed in emergency operating procedures. The safety-related CR emergency ventilation system is not credited for dose mitigation. 5.1.3 Assignment of Numeric Input Values The numeric values that are chosen as inputs to the analyses required by 10 CFR 50.67 (Ref. 9.4) are compatible to AST and TEDE dose criteria and selected with the objective of producing conservative radiological consequences. As a conservative alternative, the limiting value applicable to each portion of the analysis is used in the evaluation of that portion. 5.1.4 Meteorology Considerations The control room atmospheric dispersion factors (X/Qs) for the turbine building release point were previously developed and approved by the NRC (Ref. 9.5, Table 5-1) using the NRC sponsored computer code ARCON96. The EAB and LPZ x/Qs (Ref. 9.5, Table 5-1) were previously developed and approved by the NRC using the PBAPS plant specific meteorology and appropriate regulatory guidance. The off-site x!Qs were accepted by the staff in previous licensing proceedings (Ref. 9.9). 5.2 Accident-Specific Design Inputs/Assumptions The design inputs/assumptions utilized in the EAB, LPZ, and CR habitability analyses are listed in the following sections. The design inputs are compatible with the AST and TEDE dose criteria. Assumptions are consistent with those identified in Appendix C of RG 1.183 (Ref. 9.1). The design inputs and assumptions in the following sections represent the as-built design of the plant.

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 16of102 Design Input Parameter Value Assigned Reference 5.3 CRDA Parameters 5.3.1 Source Term 5.3 .1.1 Rated power level 3,293 MW 1 (Original) 9.3, Section 1.1 Item #4, 3,951 MWt (LPU) and Section 3.2.1 Item #1 4,030 MWt used in analysis (Includes 2% uncertainty) 5.3.1.2 Isotopic Core Inventory In Ci/MWt at 4,030 MWt 9.3, Appendix B Isotope Activity Isotope Activity Isotope Activity KR-83M 3.848E+03 I-134 6.179E+04 RB-86 6.473E+Ol KR-85 3.658E+02 I-135 5.198E+04 RB-88 2.408E+04 KR-85M 8.555E+03 XE-131M 3.024E+02 CS-134 6.832E+03 KR-87 l .686E+04 XE-133 5.488E+04 CS-136 1.933E+03 KR-88 2.379E+04 XE-133M l.714E+03 CS-137 4.ll8E+03 I-131 2.704E+04 XE-135 2.140E+04 CS-138 5.270E+04 I-132 3.901E+04 XE-135M l.081E+04 I-133 5.564E+04 XE-138 4.815E+04 5.3.1.3 Radionuclide Composition Group Elements 9.1, Section 3.4, Table 5 Noble gases Xe, Kr Halogens I, Br Alkali metals Cs, Rb 5.3.1.4 Number of fuel rods in fuel 85.6 9.19, Section 10.2 assembly 5.3.1.5 Damaged fuel rods: Breached Fuel Rods 1200 9.20, Section 3.7 Melted Fuel Rods 5.0% of the breached fuel rods Conservative bounding value melted 5.3.1.6 Number of fuel assemblies in 764 9.3, Section 3.2.1 Item #2 core 5.3.1.7 Fission products released from breached fuel gap Noble Gas 10% 9.1, Appendix C, Section 1 Iodine 10% 9 .1, Appendix C, Section 1 Alkali Metals 12% 9.1, Table 3 5.3.1.8 Fission product transfer from 9.1, Appendix C, Section 3.3 reactor coolant to turbine I condenser Noble Gas 100% Iodine 10% Alkali Metals 1% 5.3.1.9 Fission products available for 9.1, Appendix C, Section 3.4 release to the environment from turbine/ condenser Noble Gas 100% Iodine 10% Alkali Metals 1%

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 17of102 Design Input Parameter Value Assigned Reference 5.3.1.10 Radial peaking factor 1.70 9.15, Section 4.5.19.1.D 5.3.1.11 Fission products released from Assumed based on RG 1.183, melted fuel rods Appendix C, Section 1 Iodine 50% Noble Gas 100% 5.3.1.12 Fission products released from 25% Assumed based on Ref. 9.1, alkali metals Table 1 5.3.1.13 Charcoal holdup time for 34 hours 9.6, Section 7.5.0 Krypton 5.3.1.14 Charcoal holdup time for 401 hours Xenon 5.3.1.15 Total seal steam flow rate to (= 9,460 #/hr x 2 = 18,920 #/hr) 9.23 both steam packing exhausters 5.3.1.16 Uprated steam mass flow rate 16.562 x 1OD #/hr 9.22, Section 3.2.1, Item 4 5.3.2 Activity Transport to Isolated Main Steam Condenser (see Figure 1) 5.3.2.1 Condenser leak rate 1% per day 9.1, Appendix C, Section 3.4 5.3.2.2 Duration of turbine/condenser 24 hours 9.1, Table 7 and Appendix C, leak rate Section 3.4 5.3.2.3 Turbine/Condenser leak to the Ground level release 9.1, Appendix C, Section 3.4 atmosphere 5.3.2.4 Chemical form of Iodine in reactor coolant released within the pressure vessel Aerosol 95% 9.1, Appendix C, Section 3.6 Elemental 4.85% Organic 0.15% 5.3.2.5 Chemical form of iodine available for release from turbine and main condenser Elemental 97% 9.1, Appendix C, Section 3.6 Organic 3% 5.3.2.6 Dilution or holdup within the Not credited 9.1, Appendix C, Section 3.4 turbine building 5.3.2.7 Condenser free volume l fe Assumed, Section 2.3. l 5.3.2.8 Reactor coolant volume 1 ftj Assumed, Section 2.3. l 5.3.3 Control Room Parameters (see Figure 4) 5.3.3. l CR volume 176,ooo fe 9.17, Attachment 2, page 4 5.3.3.2 CR maximum air inflow rate 20,600 cfm 9.13 during CRDA + 500 cfm inleakage Assumed in Item 5.3.3.4 21,100 cfm used in the analysis 5.3.3.3 CR charcoal iodine & HEPA 0% removal Not credited in this analysis particulate filter efficiencies 5.3.3.4 CR Unfiltered Inleakage 500 cfm Assumed 5.3.3.5 CR occupancy factors Time (Hr) % 9.1, Section 4.2.6 0-24 100 24-96 60 96-720 40 5.3.3.6 CR breathing rate 3.5E-04 m.1/sec 9.1, Section 4.2.6

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 18of102 Design Input Parameter Value Assigned Reference 5.3.3.7 CR atmospheric dispersion factors for Turbine Building ground level release (X/Qs) Time (Hr) X/Q (sec/mj) 0-2 l .18E-03 9.5, Table 5-1 2-8 9.08E-04 8-24 4.14E-04 24-96 2.90E-04 96-720 2.26E-04 5.3.3.8 CR Allowable Dose Limit 5 rem TEDE for the event 9.1, Table 7 and Ref. 9.4 duration 5.3.4 Site Boundary Release Model Parameters 5.3.4. l EAB atmospheric dispersion 9. l lE-04 sec/mj 9 .5, Table 5-1 factor for ground level release (X/Q) 5.3.4.2 LPZ Atmospheric dispersion factors for ground level release (X/Qs) Time (Hr) X/Q (sec/mj) 0-2 l.38E-04 9.5, Table 5-1 2-8 5.81E-05 8-24 3.77E-05 24-96 l.48E-05 96-720 4.15E-06 5.3.4.3 EAB breathing rate 3.5E-04 mj/sec 9.1, Section 4.1.6 5.3.4.4 LPZ breathing rates (mj/sec) Time (Hr) (mj/sec) 0-8 3.5E-04 9.1, Section 4.1.6 8-24 l.8E-04 24-720 2.3E-04 5.3.4.5 EAB allowable dose limit 6.3 rem TEDE for any 2-hour 9.1, Table 6 period 5.3.4.6 LPZ allowable dose limit 6.3 rem TEDE for the event 9.1, Table 6 duration

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 19of102 6.0 COMPUTER CODES & REGULATORY COMPLIANCE 6.1 Computer Codes All computer codes used in this calculation have been approved for use with appropriate Verification and Validation (V&V) documentation. Computer codes used in this analysis include:

RADTRAD 3.03 (Ref. 9.2): This is an NRC-sponsored code approved for use in determining control room and offsite doses from releases due to reactor accidents. This code was used by most of the AST license amendments that have been approved by the NRC. A rigorous high quality code qualification process was adopted to develop and procure the code by testing of the program elements, verification of input/output files, and examination of design specification.

Therefore, the RADTRAD3.03 computer code is considered to be qualified to comply with the quality assurance requirements of 10 CFR50, Appendix B and it can be safely used to perform the design basis accident analyses. This code was used by EXELON in various AST license amendments, which are approved by the NRC. Therefore, the code is considered validated to be used for the PBAPS AST analysis. The Exelon V&V of the RADTRAD3.03 code is documented as DTSQA Number EX0004754 and is classified as SQA Level AA per IT-AA-101 (Ref. 9.11). 6.2 Regulatory Compliance As discussed in Section 4.0, Assumptions, the analysis in this calculation complies with the line-by-line requirements in Regulatory Guide 1.183 including its Appendix C (Ref. 9.1).

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 20of102

7.0 CALCULATIONS

7 .1 Post-CRDA Composite Activity Release Fractions This calculation uses the gap activity inventory fractions in Note 11 of Table 3 of RG 1.183 and assumes the release of 50% of the iodine and 100% of the noble gases for fuel reaching melted conditions (per RG 1.183, Appendix C, Section 1). Since the fuel gap can also contain the alkali metals (per RG 1.183 Table 1), this calculation applies a gap activity inventory fraction of 12% consistent with RG 1.183 Table 3. Since Appendix C of RG 1.183 does not address the melt release fraction for alkali metals for a CRDA, this calculation will assume 25% of the alkali metals are released from the melted fuel consistent with RG 1.183 Table 1. Gap Release Melt Release Group Fraction Fraction Noble Gases 10% 100% Iodine 10% 50% Alkali Metals 12% 25% Iodine Release Fraction= (l-0.05)* 10% + 0.05*50% = 12.0% = 0.12 NG Release Fraction = (1-0.05)* 10% + 0.05* 100% = 14.5% = 0.145 Alkali Metals Release Fraction= (l-0.05)* 12% + 0.05*25% = 12.65% = 0.1265 These release fractions are used in Table 2. 7.2 CR Geometry Factor GF = V 0 *338 I 1173 (Reference 9 .1, Section 4.2. 7) Where V =CR volume= 176,000 ft 3 (Section 5.3.3.1) GF = (176000)0 .3 38 I 1173 =5.055E-02 7.3 Reactor Coolant to Main Condenser Release Rate A I Ao = exp[-(QN) x t] Where: Ao= Initial Activity in Reactor Coolant A = Final Activity in Reactor Coolant Q =Reactor Coolant to Main Condenser Flow Rate (ft3/minute) V =Reactor Coolant Volume (ft3) t =Removal Time (seconds) Assuming that 99% of the reactor coolant activity within a nominal reactor coolant volume of 1 ft 3 is released to the main condenser within 1 second: A I Ao= 0.01 Therefore, In (0.01) = - (Q/V) x t Q = - [In (0.01)] x (V/t)

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 21of102 Q = (4.605) x (1 ft 3 x 60 sec/min I 1 sec) Q = 276 cfm 7.4 Gland Seal Condenser Flow Rate Original core thermal power level= 3,293 MW1 (Section 5.3.1.1) Licensed power uprate (LPU)level = 4,030 MW1 (Section 5.3.1.1) Original total steam seal flow rate= 18,920 #/hr (Section 5.3.1.15) Uprated steam mass flow rate= 16.562 x 106 #/hr (Section 5.3.1.16) Uprated total steam seal flow rate

   = 18,920 #/hr x 4,030 MWi/3,293 MW 1 = 23,155 #/hr Fraction of uprated steam mass flow rate
   = 23,155 #/hr I 16.562 x 106 #/hr= 0.0014 (conservatively rounded up to 0.0015 or 0.15%)

Gland seal condenser release= 0.0015 x 276 cfm (Section 7.3) = 0.414 cfm

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 22of102 8.0 RESULTS

SUMMARY

& CONCLUSIONS:

8.1 Results Summary: The results of the CRDA analysis are summarized in the following table: Post- CRDA Post-CRDA TEDE Dose (Rem) Activity Release Receptor Location Path Control Room EAB LPZ 3.14E-01 Main Condenser Leakage 4.22E-01 8.58E-02 (occurs @ 0.0 hr) 1.73E+OO Gland Seal Condenser Leakage l.35E+OO 2.61E-OI (occurs @ 0.0 hr) 6.28E-02 SJAE Release 4.l lE-03 9.52E-03 (occurs @ 0.0 hr) 2.86E-Ol RW Sample Line Release (I) 2.90E-Ol 4.30E-02 (occurs @ 0.0 hr) TOTALS: Main & Gland Seal Condenser 2.06 2.33 0.39 Leakage & RW Sample Line Release Gland Seal Condenser Leakage and 1.65 2.08 0.31 SJAE & RW Sample Line Releases Allowable TEDE Limit 5.00E+OO 6.30E+OO 6.30E+OO RADTRAD Computer Run No. Main Condenser Leakage PCRDACON05 .oO PCRDACON05.o0 PCRDACON05.o0 Gland Seal Condenser Leakage PCRDAGLD05.o0 PCRDAGLD05.o0 PCRDAGLD05.o0 Spreadsheet Spreadsheet Spreadsheet SJAE Release (Table 6) (Table 5) (Table 5) (I) From Reference 9.24, Section 8.1 8.2

Conclusions:

The analysis results presented in Section 8.1 indicate that the EAB, LPZ, and CR doses due to a control rod drop accident are fractions of their allowable TEDE dose limits.

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 23of102

9.0 REFERENCES

1. U.S. NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000

2. S.L. Humphreys et al., NUREG/CR-6604 (including Supplements 1 and 2), "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation," (originally published December 1997; Supplement 1 dated June 8, 1999, and Supplement 2 dated October 2002).

3. PEAM-EPU-63; GEH Project Task Report OOOO-Ol 17-7472-R2 (DRF 0000-0105-2456 Revision 2) for Peach Bottom Atomic Power Station Units 2 and 3; Extended Power Uprate Task T0802, Revision 2, "Core Source Term", January 2011

4. 10 CFR 50.67, "Accident Source Term."

5. PBAPS Calculation PM-1055, Revision 1, "Calculation of Alternative Source Term (AST) Onsite and Offsite X/Q Values".

6. PBAPS Calculation PM-0982, Revisions 1 and lA, "Operation of Offgas System Charcoal Adsorber Bed at 128F and dew point of 70F."

7. Federal Guidance Report 11, EPA-520/1-88-020, Environmental Protection Agency.

8. Federal Guidance Report 12, EPA-402-R-93-081, Environmental Protection Agency.

9. Peach Bottom Atomic Power Station Amendment Nos. 269 and 273 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.

RE: Application Of Alternative Source Term Methodology; September 5, 2008 (ADAMS Accession Number ML082320406).

10. PBAPS Technical Specifications:

10. l LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

10.2 Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation."

11. Exelon DTSQA Number EX0004754, per Procedure IT-AA-101, Rev. 7.

12. GE NEDO 31400A, October 1992, "Safety Evaluation for Eliminating The Boiling Water Reactor Main Steam Isolation Valve Closure Function and Scram Function of The Main Steam Line Radiation Monitor."

13. PBAPS Drawing 6280-M-844, Sheet 2, "QAD Diagram Control Room HVAC", Revision 2.

14. NUREG-0800, Standard Review Plan, "Radiological Consequence Analyses Using Alternative Source Terms," SRP 15.0.1, Revision 0, July 2000.

15. Exelon Procedure NF-AB-110-2210, Revision 11; Core Loading Pattern Development.

16. GEH NEDC-33270P, Revision 2, June 2009, GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GEST AR II).

17. Bechtel Letter No. BLP 22066, 05/18/1982, "Design Review of Plant Shielding."

18. NEDE-24011-P-A-15-US, Class III, September 2005, Licensing Topical Report, General Electric Standard Application for Reactor Fuel (Supplement for United States).

19. GEH Report No. GEH-HEOWX20N-026, September 3, 2010,

Subject:

PBAPS GNF2 Fuel Transition: Fl 104 Fuel Transition Report - Final, Rl.

20. GNF Report No. NEDE-31152P, Revision 7, General Electric Fuel Bundle Designs.

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 24of102

21. PBAPS UFSAR Section 14.9.2.4, Revision 22, "Control Rod Drop Accident (CRDA)".

22. PEAM-EPU-67, GEH Project Task Report 0000-0119-0663-Rl (DRF 0000-0103-2563) for Peach Bottom Atomic Power Station Units 2 and 3; Extended Power Uprate Task T0807, "Coolant Radiation Sources", March 2011.

23. PBAPS Document Number M2-139-F, GE Flow Diagram No. 738E306, Revision 6, Diagram of Stearn Sealing Piping.

24. PBAPS Calculation PM-1168, Revision 0, "Post-CRDA Release From RCS Sample Line."

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 25of102 10.0 TABLES: Table 1 Post-CRDA Activity In Damaged Fuel Rods Core Core Radial Average Total Number of Total Peak Isotope Isotopic Thermal Peaking Number Number Damaged Core Activity Inventory Power Factor of Fuel of Fuel Fuel In Damaged (Ci/MWt) Level Rods Per Rods Rods Fuel Rods (MWt) Bundle In Core By CRDA (Ci) A B c D E=D*764 F G=(A *B*C*F)/E I-131 2.704E+04 4030 1.7 85.6 65398 1200 3.399E+06 I-132 3.901E+04 4030 1.7 85.6 65398 1200 4.904E+06 I-133 5.564E+04 4030 1.7 85.6 65398 1200 6.994E+06 I-134 6. 179E+04 4030 1.7 85.6 65398 1200 7.768E+06 I-135 5.198E+04 4030 1.7 85.6 65398 1200 6.534E+06 KR-83M 3.848E+03 4030 1.7 85 .6 65398 1200 4.837E+05 KR- 85 3.658E+02 4030 1.7 85.6 65398 1200 4.598E+04 KR- 85M 8.555E+03 4030 1.7 85.6 65398 1200 I.075E+06 KR- 87 l.686E+04 4030 1.7 85.6 65398 1200 2.l 19E+06 KR-88 2.379E+04 4030 1.7 85.6 65398 1200 2.991E+06 XE13JM 3.024E+02 4030 1.7 85.6 65398 1200 3.801E+04 XE-133 5.488E+04 4030 1.7 85.6 65398 1200 6.899E+06 XE-133M l.714E+03 4030 1.7 85.6 65398 1200 2.155E+05 XE-135 2.140E+04 4030 1.7 85.6 65398 1200 2.690E+06 XE-135M l.081E+04 4030 1.7 85.6 65398 1200 l.359E+06 XE-138 4.815E+04 4030 1.7 85.6 65398 1200 6.053E+06 RB-86 6.473E+Ol 4030 1.7 85.6 65398 1200 8.137E+03 RB-88 2.408E+04 4030 1.7 85.6 65398 1200 3.027E+06 CS-134 6.832E+03 4030 1.7 85 .6 65398 1200 8.588E+05 CS-136 l.933E+03 4030 1.7 85.6 65398 1200 2.430E+05 CS-137 4.118E+03 4030 1.7 85.6 65398 1200 5.177E+05 CS-138 5.270E+04 4030 1.7 85.6 65398 1200 6.625E+06 A From Reference 9.3 Appendix B B From Reference 9.3 Section 1.1 C From Reference 9.15, Section 4.5.19.1.D D From Reference 9.19, Section 10.2

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 26of102 Table 2 Total CRDA Activity Released To Environment Total Peak Gap Activity Fraction of Total Gap Fraction of Total Gap Isotope Core Activity Release Gap Activity Activity RC Activity Activity In Damaged Fraction Released To Released To Released Released To Fuel Rods From Damaged Reactor Reactor To Condenser & Fuel Rods Coolant Coolant Condenser Environment (Ci) (Ci) (Ci) (Ci) A B c D= A*B*C E F=D*E I-131 3.399E+06 0.1200 0.1 .4079E+05 0. 1 .4079E+04 I-132 4.904E+06 0.1200 0.1 .5885E+05 0.1 .5885E+04 I-133 6.994E+06 0.1200 0.1 .8393E+05 0. 1 .8393E+04 1-134 7.768E+06 0.1200 0.1 .9321E+05 0.1 .9321E+04 l-135 6.534E+06 0.1200 0. 1 .7841E+05 0. 1 .7841E+04 KR-83M 4.837E+05 0.1450 I .7014E+05 l .7014E+05 KR- 85 4.598E+04 0.1450 1 .6668E+04 1 .6668E+04 KR- 85M l.075E+06 0.1450 I . 1559E+06 I .1559E+06 KR- 87 2.l 19E+06 0.1450 1 .3073E+06 I .3073E+06 KR-88 2.991E+06 0.1450 1 .4336E+06 I .4336E+06 XE131M 3.801E+04 0.1450 l .5512E+04 l .5512E+04 XE-133 6.899E+06 0.1450 1 . IOOOE+07 1 . IOOOE+07 XE-133M 2.155E+05 0.1450 1 .3124E+05 1 .3124E+05 XE-135 2.690E+06 0.1450 1 .3901E+06 1 .3901E+06 XE-135M l .359E+06 0.1450 l .1970E+06 I .1970E+06 XE-138 6.053E+06 0.1450 1 .8777E+06 1 .8777E+06 RB-86 8.137E+03 0.1265 0.01 .1029E+02 0.01 . 1029E+OO RB-88 3.027E+06 0.1265 0.01 .3829E+04 0.01 .3829E+02 CS-134 8.588E+05 0.1265 0.01 . 1086E+04 0.01 .1086E+02 CS-136 2.430E+05 0.1265 0.01 .3074E+03 0.01 .3074E+Ol CS-137 5. I 77E+05 0.1265 O.Dl .6549E+03 0.01 .6549E+Ol CS-138 6.625E+06 0.1265 0.01 .8380E+04 0.01 .8380E+02 A From Table 1 B From Section 7 .1 C & E From Reference 9.1, Appendix C

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 27 of 102 Table 3 CRDA SJAE Release To Environment Total Gap Decay Holdup in Release to Release to Half-Life Half-Live Activity Released Constant Delay Bed Delay Bed Environment To Reactor Coolant Isotope (seconds) (Ci) (hours) (hours)" 1 (hours) (Ci) (Ci) A B C=A/3600 D=LN(2)/C E F=B G=F*EXP(-D*E) Kr-83m 6.588E+03 7.014E+04 l.830E+OO 3.788E-OI 34 7.014E+04 1.791 E-01 Kr-85 3.383E+08 6.668E+03 9.397E+04 7.376E 06 34 6.668E+03 6.666E+03 Kr-85m l.613E+04 l .559E+05 4.481E+OO l.547E-OI 34 1.559E+05 8.103E+02 Kr-87 4.578E+03 3.073E+05 l.272E+OO 5.451 E-01 34 3.073E+05 2.748E-03 Kr-88 l .022E+04 4.336E+05 2.839E+OO 2.442E-OI 34 4.336E+05 l .076E+02 Xe- 131m l .028E+06 5.512E+03 2.856E+02 2.427E-03 401 5.512E+03 2.083E+03 Xe-133 4.532E+05 l.OOOE+06 I .259E+02 5.506E-03 401 l.OOOE+06 l.IOOE+05 Xe-133m l.890E+05 3. 124E+04 5.250E+OI 1.320E-02 401 3. 124E+04 l.568E+02 Xe-135 3.272E+04 3.901E+05 9.089E+OO 7.626E-02 401 3.901E+05 2.041E-08 Xe-135m 9.174E+02 l .970E+05 2.548E-OI 2.720E+OO 401 l .970E+05 O.OOOE+OO Xe-138 8.502E+02 8.777E+05 2.362E-OI 2.935E+OO 401 8.777E+05 O.OOOE+OO A From RADTRAD Output File PCRDACON05.o0 B and F From Table 2, Column D E From Sections 5.3.1.13 and 5.3. 1.14

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 28of102 Table 4 Noble Gas Isotopic Dose Conversion Factor Isotopic Conversion Isotopic Submersion Dose Factor Submersion Dose Isotope Conversion Conversion Factor Factor (Sv-m3/ Bq s) (rem/Ci I Sv/Bq) (rem-m3/Ci-sec) A B C=AxB Kr-83m l .50E-18 3.70E+l2 5.550E-06 Kr-85 l.l 9E- l6 3.70E+l2 4.403E-04 Kr-85m 7.48E-15 3.70E+l2 2.768E-02 Kr-87 4. 12E-14 3.70E+l2 l.524E-Ol Kr-88 l.02E-13 3.70E+l2 3.774E-Ol Xe-13lm 3.89E-l 6 3.70E+l2 l .439E-03 Xe-133 I .56E-15 3.70E+l2 5.772E-03 Xe-133m l.37E-l5 3.70E+l2 5.069E-03 Xe-135 1.19E-14 3.70E+l2 4.403E-02 Xe-135m 2.04E-l4 3.70E+l2 7.548E-02 Xe-138 5.77E-l4 3.70E+l2 2. l 35E-01 A From FGR-12 (Reference 9.8, Table III.l)

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 29of102 Table 5 CRDA SJAE Release EAB & LPZ Dose Consequences Atmospheric Release to Dispersion EAB LPZ 3 Isotope Environment DCF Factor (s/m ) Dose Dose 3 (Ci) (rem-m /Ci-sec) EAB LPZ RemTEDE RemTEDE A B c D E=AxBxC F=AxBxD Kr-83m 1.791 E-0 I 5.550E-06 9.055E-10 l.372E-10 Kr-85 6.666E+03 4.403E-04 2.674E-03 4.050E-04 Kr-85m 8.103E+02 2.768E-02 2.043E-02 3.095E-03 Kr-87 2.748E-03 I.524E-OI 3.817E-07 5.782E-08 Kr-88 1.076E+02 3.774E-OI 3.700E-02 5.604E-03 Xe-13lm 2.083E+03 I .439E-03 9.l lE-04 l.38E-04 2.731E-03 4.136E-04 Xe-133 l.IOOE+05 5.772E-03 5.782E-Ol 8.759E-02 Xe-133m l.568E+02 5.069E-03 7.243E-04 l.097E-04 Xe-135 2.041E-08 4.403E-02 8.185E-13 l .240E-13 Xe-135m O.OOOE+OO 7.548E-02 O.OOOE+OO O.OOOE+OO Xe-138 O.OOOE+OO 2.135E-Ol O.OOOE+OO O.OOOE+OO Total Dose (Rem TEDE) 6.28E-02 9.52E-03 A From Table 3 B From Table 4 C From Section 5.3.4. l & D From Section 5.3.4.2

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 30of102 Table 6 CRDA SJAE Release CR Dose Consequences Release to CR Atmospheric CR Isotope Environment DCF Geometry Dispersion Dose (Ci) (rem-m*'/Ci-sec) Factor Factor RemTEDE 3 (sec/m ) A B c D E=AxBxCxD Kr-83m l.791E-01 5.550E-06 5.929E-l 1 Kr-85 6.666E+03 4.403E-04 l.751E-04 Kr-85m 8.103E+02 2.768E-02 1.338E-03 Kr-87 2.748E-03 1.524E-01 2.499E-08 Kr-88 l.076E+02 3.774E-01 2.422E-03 Xe-131m 2.083E+03 1.439E-03 5.055E-02 1. 180E-03 l.788E-04 Xe-133 l.100E+05 5.772E-03 3.786E-02 Xe-133m l.568E+02 5.069E-03 4.742E-05 Xe-135 2.041E-08 4.403E-02 5.359E-14 Xe-135m O.OOOE+OO 7.548E-02 O.OOOE+OO Xe-138 O.OOOE+OO 2. l 35E-01 O.OOOE+OO Total Dose (Rem TEDE) 4.llE-03 A From Table 3 B From Table 4 C From Section 7 .2 D From Section 5.3 .3.7

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 31of102 11.0 FIGURES: E N v I To CR, EAB, LPZ I

Reactor I Coolant v =t.o rt3 R 0 N 276 cfm < 10 min I M E N I 1 v% per day~ 24 hrs I - T Main Steam Condenser Main Steam v =t.o rt3 Condenser Release Figure 1: RADTRAD Nodalization For Post-CRDA Isolated Condenser Release

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 32of102 E N v I To CR, EAB, LPZ Main Steam Steam Jet Charcoal R I Condenser

                 ~
                 ~

Air Ejector (SJAE)

Adsorber Beds

0 -

N M E N T Figure 2: Post-CRDA Steam Jet Air Ejector Release

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 33of102 I 0.414 cfm < 24 hrs I .

j ~ Gland Seal E Condenser Release N v I To CR, EAB, LPZ

                                                                                  . I Reactor                                                  I Coolant v =1.0 rt3                                                R 0

N 275.59 cfm < 10 min I M E N T Main Steam Condenser v =1.0 rt3 Figure 3: RADTRAD Nodalization For Post-CRDA Gland Seal Condenser Release

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 34of102 E -- j N 0 - 720 hrs 21,100 cfm I v I Control R Room CRDA 0 I I-- N v = 176,000 ft3 M E N T -- 0 - 720 hrs 20,600 cfm

                        + 500 cfm Unfiltered inleakage Figure 4 - PBAPS Control Room RADTRAD Nodalization

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 35of102 12.0 AFFECTED DOCUMENTS: The following documents will be either superseded or revised: Document to be superseded Calculation PM-1057, Revision 4 Documents to be revised: UFSAR Section 14.9.2.4, "Control Rod Drop Accident (Roof Top Release)" UFSAR Table 14.9-6, "Design Basis Accident Radiological Doses Control Room." UFSAR Table 14.9-7, "Design Basis Accident Radiological Doses Exclusion Area Boundary & Low Population Zone." 13.0 ATTACHMENTS: 13.1 RADTRAD Output File: PCRDACON05.o0 13.2 RADTRAD Output File: PCRDAGLD05.o0 13.3 RADTRAD Nuclide Inventory File: PBCRDA3_def.txt 13.4 RADTRAD Nuclide Inventory File: PBCRDA_GLD_def.txt 13.5 RADTRAD Release Fraction and Timing File: pbcrda_rft.txt 13.6 RADTRAD Dose Conversion Factor File: pbcrda_fgl 1&12.txt

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 36of102 Attachment 13.1 RADTRAD Output File: PCRDACONOS.oO RADTRAD Version 3.03 (Spring 2001) run on 12/17/2013 at 15:08:55 File information Plant file G:\Radtrad 3.03\Input\PM-1057\PCRDACON05.psf Inventory file g:\radtrad 3.03\defaults\pbcrda3_def . txt Release file g:\radtrad 3.03\defaults\pbcrda_rft.txt Dose Conversion file g:\radtrad 3.03\defaults\pbcrda_fgll&l2.txt Radtrad 3.03 4/15/2001 PBAPS Post-CRDA EAB, LPZ, & CR Doses Using Guidance in RG 1.183, Appendix C Nuclide Inventory File: g:\radtrad 3.03\defaults\pbcrda3_def.txt Plant Power Level: l.OOOOE+OO Compartments: 4 Compartment 1: Reactor Coolant 3 l.OOOOE+OO 0 0 0 0 0 Compartment 2: Environment 2 O.OOOOE+OO 0 0 0 0 0 Compartment 3: Control Room

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 37 of 102 1 l.7600E+OS 0 0 0 0 0 Compartment 4: Condenser 3 l.OOOOE+OO 0 0 0 0 0 Pathways: 4 Pathway 1: Reactor Coolant to Condenser 1 4 2 Pathway 2: Environment to Control Room 2 3 2 Pathway 3: Control Room Exhaust to Environment 3 2 2 Pathway 4: Condenser to Environment 4 2 4 End of Plant Model File Scenario Description Name: Plant Model Filename: Source Term: 1 1 1.0000E+OO g:\radtrad 3.03\defaults\pbcrda_fgll&l2.txt g:\radtrad 3.03\defaults\pbcrda_rft.txt 0.0000E+OO 1 O.OOOOE+OO 9.7000E-Ol 3.0000E-02 l.OOOOE+OO Overlying Pool: 0 O.OOOOE+OO 0 0 0 0

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 38of102 Compartments: 4 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 1 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 0 0 0 Compartment 4: 0 1 0 0 0 0 0 0 0 Pathways: 4 Pathway 1: 0 0 0 0 0 1 2 O.OOOOE+OO 2.7600E+02 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO l.6670E-Ol 0.0000E+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 0 0 0 0

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 39of102 0 0 Pathway 2: 0 0 0 0 0 1 2 0.0000E+OO 2 .1100E+04 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 7.2000E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0 0 0 0 0 0 Pathway 3: 0 0 0 0 0 1 2 0.0000E+OO 2.1100E+04 l.OOOOE+02 l.OOOOE+02 l.OOOOE+02 7.2000E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0 0 0 0 0 0 Pathway 4: 0 0 0 0 0 0 0 0 0 0 1 2 0.0000E+OO l.OOOOE+OO 2.4000E+Ol O.OOOOE+OO 0 Dose Locations: 3 Location 1: Exclusion Area Boundary 2 1 2 0.0000E+OO 9.llOOE-04

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 40of102 7.2000E+02 O.OOOOE+OO 1 2 0.0000E+OO 3.SOOOE-04 7.2000E+02 O.OOOOE+OO 0 Location 2: Low Population Zone 2 1 6 0.0000E+OO l.3800E-04 2.0000E+OO S.8100E-OS 8.0000E+OO 3.7700E-OS 2.4000E+Ol 1.4800E-05 9.6000E+Ol 4.lSOOE-06 7.2000E+02 0.0000E+OO 1 4 O.OOOOE+OO 3.SOOOE-04 8.0000E+OO l.8000E-04 2.4000E+Ol 2.3000E-04 7.2000E+02 O.OOOOE+OO 0 Location 3: Control Room 3 0 1 2 0.0000E+OO 3.SOOOE-04 7.2000E+02 O.OOOOE+OO 1 4 O.OOOOE+OO l.OOOOE+OO 2.4000E+Ol 6.0000E-01 9.6000E+Ol 4.0000E-01 7.2000E+02 O.OOOOE+OO Effective Volume Location: 1 6 O.OOOOE+OO l.1800E-03 2.0000E+OO 9.0800E-04 8.0000E+OO 4.1400E-04 2.4000E+Ol 2.9000E-04 9.6000E+Ol 2.2600E-04 7.2000E+02 O.OOOOE+OO Simulation Parameters: 6 O.OOOOE+OO l.OOOOE-01 2.0000E+OO S.OOOOE-01 8.0000E+OO l.OOOOE+OO 2.4000E+Ol 2.0000E+OO 9.6000E+Ol 8.0000E+OO 7.2000E+02 0.0000E+OO Output Filename: G:\Radtrad 3.ol8 1

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 41of102 1 1 0 0 End of Scenario File

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 42of102 RADTRAD Version 3.03 (Spring 2001) run on 12/17/2013 at 15:08:55 Plant Description Number of Nuclides 60 Inventory Power= l.OOOOE+OO MWth Plant Power Level l.OOOOE+OO MWth Number of compartments 4 Compartment information Compartment number 1 (Source term fraction l.OOOOE+OO

Name: Reactor Coolant Compartment volume = l.OOOOE+OO (Cubic feet) Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Reactor Coolant to Condenser Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 3: Control Room Exhaust to Environment Inlet Pathway Number 4: Condenser to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume l.7600E+05 (Cubic feet) Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room Exhaust to Environment Compartment number 4 Name: Condenser Compartment volume l.OOOOE+OO (Cubic feet) Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 1: Reactor Coolant to Condenser Exit Pathway Number 4: Condenser to Environment Total number of pathways 4

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 43of102 RADTRAD Version 3.03 (Spring 2001) run on 12/17/2013 at 15:08:55 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0.0000 hrs 0.0000 hrs (gm) NOBLES 1.0000E+OO O.OOOOE+OO O.OOOOE+OO 2.271E+Ol IODINE l.OOOOE+OO 0.0000E+OO 0.0000E+OO 4.346E-02 CESIUM l.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 8.373E-02 TELLURIUM O.OOOOE+OO 0.0000E+OO 0.0000E+OO O.OOOE+OO STRONTIUM O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOE+OO BARIUM O.OOOOE+OO O.OOOOE+OO 0.0000E+OO O.OOOE+OO RUTHENIUM O.OOOOE+OO 0.0000E+OO O.OOOOE+OO O.OOOE+OO CERIUM 0.0000E+OO O.OOOOE+OO O.OOOOE+OO 0.000E+OO LANTHANUM O.OOOOE+OO 0.0000E+OO 0.0000E+OO O.OOOE+OO Inventory Power 1. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq) Kr-83m 1 7.014E+04 6.588E+03 1. 500E-18 O.OOOE+OO O.OOOE+OO Kr-85 1 6.668E+03 3.383E+08 1. 190E-16 O.OOOE+OO 0.000E+OO Kr-85m 1 l.559E+05 1.613E+04 7.480E-15 O.OOOE+OO O.OOOE+OO Kr-87 1 3.073E+05 4.578E+03 4.120E-14 O.OOOE+OO 0.000E+OO Kr-88 1 4.336E+05 l.022E+04 l.020E-13 0.000E+OO O.OOOE+OO Rb-86 3 l.029E-Ol l.612E+06 4.810E-15 l.330E-09 l.790E-09 Rb-88 3 3.829E+Ol 1.068E+03 3.360E-14 1.370E-12 2.260E-ll I-131 2 4.079E+03 6.947E+05 l.820E-14 2.920E-07 8.890E-09 I-132 2 5.885E+03 8.280E+03 l.120E-13 l.740E-09 1.030E-10 I-133 2 8.393E+03 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 9.321E+03 3.156E+03 1.300E-13 2.880E-10 3.550E-ll I-135 2 7.841E+03 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-13lm 1 5.512E+03 l.028E+06 3.890E-16 0.000E+OO 0.000E+OO Xe-133 1 l.OOOE+06 4.532E+05 l.560E-15 O.OOOE+OO 0.000E+OO Xe-133m 1 3.124E+04 l.890E+05 l.370E-15 O.OOOE+OO O.OOOE+OO Xe-135 1 3.901E+05 3.272E+04 l.190E-14 0.000E+OO O.OOOE+OO Xe-135m 1 l.970E+05 9.174E+02 2.040E-14 0.000E+OO O.OOOE+OO Xe-138 1 8. 777E+05 8.502E+02 5.770E-14 O.OOOE+OO 0.000E+OO Cs-134 3 l.086E+Ol 6.507E+07 7.570E-14 1.llOE-08 l.250E-08 Cs-136 3 3.074E+OO 1.132E+06 l.060E-13 1.730E-09 l.980E-09 Cs-137 3 6.549E+OO 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Cs-138 3 8.380E+Ol l.932E+03 l.210E-13 3.570E-12 2.740E-ll Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1. 00 none 0.00 none 0.00 Kr-88 Rb-88 1. 00 none 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 44of102 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0 . 85 none 0.00 Xe-133m Xe-133 1. 00 none 0.00 none 0.00 Xe-135 Cs-135 1. 00 none 0.00 none 0.00 Xe-135m Xe-135 1. 00 none 0.00 none 0.00 Xe-138 Cs-138 1. 00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Iodine fractions Aerosol O.OOOOE+OO Elemental 9.7000E-01 Organic 3.0000E-02 COMPARTMENT DATA Compartment number 1: Reactor Coolant Compartment number 2: Environment Compartment number 3: Control Room Compartment number 4: Condenser PATHWAY DATA Pathway number 1: Reactor Coolant to Condenser Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic O.OOOOE+OO 2.7600E+02 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 1.6670E-01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic O.OOOOE+OO 2.1100E+04 0.0000E+OO O.OOOOE+OO O.OOOOE+OO 7.2000E+02 0.0000E+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO Pathway number 3: Control Room Exhaust to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic O.OOOOE+OO 2.1100E+04 l.OOOOE+02 1.0000E+02 l.OOOOE+02 7.2000E+02 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO Pathway number 4: Condenser to Environment Convection Data Time (hr) Flow Rate (% I day) O.OOOOE+OO l.OOOOE+OO 2.4000E+Ol O.OOOOE+OO

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 45of102 LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

mA-3)

O.OOOOE+OO 9.llOOE-04 7.2000E+02 0.0000E+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1) 0.0000E+OO 3.5000E-04 7.2000E+02 O.OOOOE+OO Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s
mA-3)

O.OOOOE+OO l.3800E-04 2.0000E+OO 5.8100E-05 8.0000E+OO 3.7700E-05 2.4000E+Ol 1.4800E-05 9 . 6000E+Ol 4.1500E-06 7.2000E+02 O.OOOOE+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1)

O.OOOOE+OO 3.5000E-04 8.0000E+OO 1.BOOOE-04 2.4000E+Ol 2.3000E-04 7.2000E+02 0.0000E+OO Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/Q (s

mA-3)

O. OOOOE+OO l.1800E-03 2.0000E+OO 9.0800E-04 8.0000E+OO 4.1400E-04 2.4000E+Ol 2.9000E-04 9.6000E+Ol 2.2600E-04 7.2000E+02 O.OOOOE+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1)

O.OOOOE+OO 3.5000E-04 7.2000E+02 O.OOOOE+OO Location Occupancy Factor Data Time (hr) Occupancy Factor O.OOOOE+OO l.OOOOE+OO 2.4000E+Ol 6.0000E-01 9.6000E+Ol 4.0000E-01 7.2000E+02 O.OOOOE+OO USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+OO 1.0000E-01 2.0000E+OO 5.0000E-01 8.0000E+OO l.OOOOE+OO

CALCULATION NO. PM-1057 REV. No. S PAGE NO. 46of102 2.4000E+Ol 2.0000E+OO 9.6000E+Ol 8.0000E+OO 7.2000E+02 O.OOOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 47of102 RADTRAD Version 3.03 (Spring 2001) run on 12/17/2013 at 15:08:55 Dose Output Exclusion Area Boundary Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 2.9778E-04 l.4361E-03 3.4341E-04 Accumulated dose (rem) 2.9778E-04 1. 4361E-03 3.4341E-04 Low Population Zone Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 4.5109E-05 2.1754E-04 5.2020E-05 Accumulated dose (rem) 4.5109E-05 2.1754E-04 5.2020E-05 Control Room Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) l.9340E-07 l.8453E-05 7.7967E-07 Accumulated dose (rem) l.9340E-07 l.8453E-05 7.7967E-07 Exclusion Area Boundary Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 2.7847E-02 l.3447E-Ol 3.2284E-02 Accumulated dose (rem) 2.8145E-02 1. 3591E-01 3.2627E-02 Low Population Zone Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 4.2184E-03 2.0370E-02 4.8904E-03 Accumulated dose (rem) 4.2635E-03 2.0588E-02 4.9424E-03 Control Room Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 7.2648E-04 6.9450E-02 3.0579E-03 Accumulated dose (rem) 7.2667E-04 6.9468E-02 3.0586E-03 Exclusion Area Boundary Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2369E-Ol l.4867E+OO 2.8091E-Ol Accumulated dose (rem) 2.5184E-Ol l.6226E+OO 3 .1354E-Ol

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 48of102 Low Population Zone Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.3886E-02 2.2520E-01 4.2553E-02 Accumulated dose (rem) 3.8149E-02 2.4579E-01 4.7496E-02 Control Room Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) l.4176E-02 l.8790E+OO 8.6555E-02 Accumulated dose (rem) l.4903E-02 1.9485E+OO 8.9613E-02 Exclusion Area Boundary Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4301E-01 4. 5911E+OO 3.9909E-01 Accumulated dose (rem) 4.9485E-01 6.2137E+OO 7.1264E-01 Low Population Zone Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) l.5498E-02 2.9280E-01 2.5453E-02 Accumulated dose (rem) 5.3647E-02 5.3860E-01 7.2949E-02 Control Room Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) l.2412E-02 4.6108E+OO 1.6926E-01 Accumulated dose (rem) 2.7315E-02 6.5592E+OO 2.5888E-01 Exclusion Area Boundary Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3626E-01 l.0828E+Ol 4. 7716E-01 Accumulated dose (rem) 6.3111E-01 l.7041E+Ol 1.1898E+OO Low Population Zone Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.6388E-03 2.3044E-01 l.2894E-02 Accumulated dose (rem) 5.9286E-02 7.6904E-01 8.5843E-02 Control Room Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.2071E-03 4.9786E+OO 1. 6000E-01 Accumulated dose (rem) 3.0522E-02 l.1538E+Ol 4.1888E-01 Exclusion Area Boundary Doses: Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 6.3111E-Ol l.7041E+Ol 1.1898E+OO Low Population Zone Doses: Time (h) = 96.0000 Whole Body Thyroid TEDE

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 49of102 Delta dose (rem) O.OOOOE+OO O.OOOOE+OO 0.0000E+OO Accumulated dose (rem) 5.9286E-02 7.6904E-Ol 8.5843E-02 Control Room Doses: Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5936E-05 8.5163E-02 2.6654E-03 Accumulated dose (rem) 3.0548E-02 l.1623E+Ol 4.2154E-01 Exclusion Area Boundary Doses: Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 6. 3111E- 01 1. 7041E+Ol l.1898E+OO Low Population Zone Doses: Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 5.9286E-02 7.6904E-01 8.5843E-02 Control Room Doses: Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.6009-231 4.4688-227 1. 3 799-228 Accumulated dose (rem) 3.0548E-02 l.1623E+Ol 4.2154E-01 839 I-131 Summary Reactor Coolant Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 6.8414E+Ol 5.8739E-05 6.8937E-07 0.004 6.8420E+Ol 2.9583E-03 3.4468E-05 0.167 0.0000E+OO 2.8002E-01 l.9269E-03 0.500 0.0000E+OO 8.4564E-01 2. 6940E-03 0.800 0.0000E+OO 1.3541E+OO 2.7588E-03 1.100 O.OOOOE+OO l.8619E+OO 2.7633E-03

1. 400 0 . 0000E+OO 2.3692E+OO 2.7609E-03 1.700 0.0000E+OO 2.8758E+OO 2.7577E-03 2.000 O.OOOOE+OO 3.3818E+OO 2.7544E-03 2.300 O.OOOOE+OO 3.8872E+OO 2.1902E-03 2.600 0.0000E+OO 4.3920E+OO 2.1228E-03 2.900 O.OOOOE+OO 4. 8962E+OO 2 .1128E-03 3 . 200 0.0000E+OO 5.3998E+OO 2 . 1094E-03 3.500 O.OOOOE+OO 5.9028E+OO 2.1068E-03 3.800 O.OOOOE+OO 6.4052E+OO 2 . 1042E-03 4.100 O.OOOOE+OO 6.9070E+OO 2.1017E-03 4.400 O.OOOOE+OO 7.4081E+OO 2.0992E-03 4.700 O.OOOOE+OO 7.9087E+OO 2.0967E-03 5.000 O.OOOOE+OO 8.4087E+OO 2.0941E-03 5.300 O.OOOOE+OO 8.9080E+OO 2.0916E-03 5.600 O.OOOOE+OO 9.4068E+OO 2.0891E-03 5.900 0.0000E+OO 9.9050E+OO 2.0866E-03 6.200 0.0000E+OO l.0403E+Ol 2.0841E-03

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 50of102 6.500 O.OOOOE+OO l.0900E+Ol 2.0816E-03 6.800 O.OOOOE+OO l.1396E+Ol 2.0791E-03 7.100 0.0000E+OO l.1892E+Ol 2.0766E-03 7.400 O.OOOOE+OO l.2387E+Ol 2.0741E-03 7.700 O.OOOOE+OO l.2881E+Ol 2.0716E-03 8.000 O.OOOOE+OO l.3375E+Ol 2. 0691E-03 8.300 0.0000E+OO l.3869E+Ol l.0722E-03 8.600 O.OOOOE+OO l.4362E+Ol 9.5613E-04 8.900 0.0000E+OO l.4854E+Ol 9.4173E-04 9.200 O.OOOOE+OO l.5345E+Ol 9.3907E-04 9.500 0.0000E+OO l.5836E+Ol 9.3777E-04 9.800 O.OOOOE+OO l.6327E+Ol 9.3662E-04 10.100 O.OOOOE+OO l.6817E+Ol 9.3549E-04 10.400 O.OOOOE+OO l.7306E+Ol 9.3437E-04 24.000 O.OOOOE+OO 3.8851E+Ol 8.8479E-04

96. 000 O.OOOOE+OO 3.8851E+Ol 8.0082-229 720.000 O.OOOOE+OO 3.8851E+Ol 0.0000E+OO Condenser Time (hr) I-131 (Curies) 0.000 5.6106E+02 0.004 4.0105E+03 0.167 4.0763E+03 0.500 4.0708E+03 0.800 4.0659E+03 1.100 4. 0611E+03 1.400 4.0562E+03 1.700 4. 0513E+03 2.000 4.0464E+03 2.300 4.0416E+03 2.600 4.0367E+03 2.900 4.0319E+03 3.200 4.0270E+03 3.500 4.0222E+03 3.800 4.0173E+03 4.100 4.0125E+03 4.400 4.0077E+03 4.700 4.0029E+03 5.000 3.9981E+03 5.300 3.9933E+03 5.600 3.9885E+03 5.900 3.9837E+03 6.200 3.9789E+03 6.500 3. 9741E+03 6.800 3. 9693E+03 7.100 3.9645E+03 7.400 3.9598E+03 7.700 3.9550E+03 8.000 3.9503E+03 8.300 3.9455E+03 8.600 3.9408E+03 8.900 3.9360E+03 9.200 3. 9313E+03 9.500 3.9266E+03 9.800 3.9219E+03 10.100 3. 9171E+03 10.400 3.9124E+03 24.000 3.7048E+03

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 51of102 96.000 2.8605E+03 720.000 3.0406E+02 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.0000E+OO 0.0000E+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 0.004 l.4361E-03 3.4341E-04 2.1754E-04 5.2020E-05 1.8453E-05 7.7967E-07 0.167 l.3591E-01 3.2627E-02 2.0588E-02 4.9424E-03 6.9468E-02 3.0586E-03 0.500 4.0963E-01 9.7089E-02 6.2051E-02 l.4707E-02 3.8152E-01 l.7935E-02 0.800 6.5469E-01 l.5018E-01 9.9173E-02 2.2750E-02 6.9519E-01 3.3152E-02 1.100 8.9848E-01 1.9777E-01 l.3610E-01 2.9959E-02 l.0106E+OO 4.8097E-02 1.400 l.1410E+OO 2.4036E-01 l.7285E-01 3.6410E-02 1.3247E+OO 6.2478E-02 1.700 1.3824E+OO 2.7870E-01 2.0941E-01 4.2218E-02 l.6373E+OO 7.6295E-02 2.000 l.6226E+OO 3.1354E-01 2.4579E-01 4.7496E-02 l.9485E+OO 8.9613E-02 2.300 1.8616E+OO 3.4550E-01 2.6104E-01 4.9534E-02 2.2173E+OO 1.0081E-01 2.600 2.0995E+OO 3.7507E-01 2.7621E-01 5.1420E-02 2.4579E+OO l.1059E-01 2.900 2.3364E+OO 4.0263E-01 2.9132E-01 5.3178E-02 2.6944E+OO l.2000E-01 3.200 2.5722E+OO 4.2847E-01 3.0635E-01 5.4825E-02 2.9295E+OO l.2919E-01 3.500 2.8069E+OO 4.5281E-01 3.2132E-01 5.6378E-02 3.1634E+OO l.3819E-01 3.800 3.0406E+OO 4.7584E-01 3.3623E-01 5.7847E-02 3.3964E+OO l.4702E-01 4.100 3.2733E+OO 4.9771E-01 3.5107E-01 5.9241E-02 3.6283E+OO 1.5570E-01 4.400 3.5050E+OO 5.1853E-01 3.6584E-01 6.0569E-02 3.8593E+OO l.6424E-01 4.700 3.7357E+OO 5.3840E-01 3.8056E-01 6.1836E-02 4.0893E+OO 1.7266E-01 5.000 3.9655E+OO 5.5741E-01 3.9521E-01 6.3049E-02 4.3183E+OO l.8096E-01 5.300 4.1943E+OO 5.7563E-01 4.0981E-01 6.4211E-02 4.5464E+OO l.8915E-01 5.600 4.4222E+OO 5.9312E-01 4.2434E-01 6.5326E-02 4.7736E+OO 1.9724E-01 5.900 4.6492E+OO 6.0994E-01 4.3882E-01 6.6399E-02 4.9998E+OO 2.0523E-01 6.200 4.8753E+OO 6.2615E-01 4.5324E-01 6.7433E-02 5.2252E+OO 2.1313E-01 6.500 5.1005E+OO 6.4178E-01 4.6760E-01 6.8429E-02 5.4497E+OO 2.2094E-01 6.800 5.3249E+OO 6.5688E-01 4.8191E-01 6.9392E-02 5.6733E+OO 2.2867E-01 7.100 5.5484E+OO 6.7148E-01 4.9616E-01 7.0324E-02 5.8960E+OO 2.3633E-01 7.400 5.7710E+OO 6.8562E-01 5.1036E-01 7.1225E-02 6.1179E+OO 2.4391E-01 7.700 5.9928E+OO 6.9933E-01 5.2450E-01 7.2100E-02 6.3390E+OO 2.5143E-01 8.000 6.2137E+OO 7.1264E-01 5.3860E-01 7.2949E-02 6.5592E+OO 2.5888E-01 8.300 6.4339E+OO 7.2557E-01 5.4328E-01 7.3341E-02 6.7103E+OO 2.6396E-01 8.600 6.6532E+OO 7.3815E-01 5.4795E-01 7.3719E-02 6.8159E+OO 2.6750E-01 8.900 6.8717E+OO 7.5041E-01 5.5260E-01 7.4085E-02 6.9159E+OO 2.7084E-01 9.200 7.0895E+OO 7.6236E-01 5.5723E-01 7.4439E-02 7.0149E+OO 2.7413E-01 9.500 7.3064E+OO 7.7402E-01 5.6185E-01 7.4782E-02 7.1135E+OO 2.7739E-01 9.800 7.5226E+OO 7.8541E-01 5.6645E-01 7.5115E-02 7.2118E+OO 2.8064E-01 10.100 7.7381E+OO 7.9655E-01 5.7104E-01 7.5438E-02 7.3097E+OO 2.8386E-01 10.400 7.9528E+OO 8.0746E-01 5.7561E-01 7.5752E-02 7.4073E+OO 2.8705E-01 24.000 1.7041E+Ol 1.1898E+OO 7.6904E-01 8.5843E-02 l.1538E+Ol 4.1888E-01 96.000 l.7041E+Ol l.1898E+OO 7.6904E-01 8.5843E-02 l.1623E+Ol 4.2154E-01 720.000 l.7041E+Ol l.1898E+OO 7.6904E-01 8.5843E-02 1.1623E+Ol 4.2154E-01 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 2.5184E-Ol l.6226E+OO 3.1354E-01

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 52of102 Attachment 13.2 RADTRAD Output File: PCRDAGLDOS.oO RADTRAD Version 3.03 (Spring 2001) run on 12/26/2013 at 19:19:56 File information Plant file G:\Radtrad 3.03\Input\PM-1057\PCRDAGLD05.psf Inventory file G:\Radtrad 3.03\Defaults\PBCRDA_GLD_def.txt Release file G:\Radtrad 3.03\Defaults\PBCRDA_RFT.txt Dose Conversion file g:\radtrad 3.03\defaults\pbcrda_fgll&l2.txt Radtrad 3.03 4/15/2001 PBAPS Post-CRDA EAB, LPZ, & CR Doses Due To Gland Seal Condenser Release Using Guidance in RG 1.183, Appendix C Nuclide Inventory File: G:\Radtrad 3.03\Defaults\PBCRDA_GLD_def.txt Plant Power Level: 1.0000E+OO Compartments: 4 Compartment 1: Reactor Coolant 3 l.OOOOE+OO 0 0 0 0 0 Compartment 2: Environment 2 0.0000E+OO 0 0 0 0 0 Compartment 3: Control Room

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 53of102 1 l.7600E+05 0 0 0 0 0 Compartment 4: Condenser 3 l.OOOOE+OO 0 0 0 0 0 Pathways: 4 Pathway 1: Reactor Coolant to Condenser 1 4 2 Pathway 2: Environment to Control Room 2 3 2 Pathway 3: Control Room Exhaust to Environment 3 2 2 Pathway 4: Reactor Coolant to Environment 1 2 2 End of Plant Model File Scenario Description Name: Plant Model Filename: Source Term: 1 1 l.OOOOE+OO g:\radtrad 3.03\defaults\pbcrda_fgll&l2.txt G:\Radtrad 3.03\Defaults\PBCRDA_RFT . txt O.OOOOE+OO 1 O.OOOOE+OO 9.7000E-Ol 3.0000E-02 l.OOOOE+OO Overlying Pool: 0 0.0000E+OO 0 0 0 0

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 54of102 Compartments: 4 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 1 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 0 0 0 Compartment 4: 0 1 0 0 0 0 0 0 0 Pathways: 4 Pathway 1: 0 0 0 0 0 1 2 O.OOOOE+OO 2.7560E+02 0.0000E+OO O.OOOOE+OO O.OOOOE+OO l.6670E-Ol O.OOOOE+OO 0.0000E+OO O.OOOOE+OO O.OOOOE+OO 0 0 0 0

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 55of102 0 0 Pathway 2: 0 0 0 0 0 1 2 O.OOOOE+OO 2. 1100E+04 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 7.2000E+02 0.0000E+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO 0 0 0 0 0 0 Pathway 3: 0 0 0 0 0 1 2 O.OOOOE+OO 2 .1100E+04 l.OOOOE+02 l.OOOOE+02 l.OOOOE+02 7.2000E+02 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO 0 0 0 0 0 0 Pathway 4: 0 0 0 0 0 1 2 O.OOOOE+OO 4.1400E-Ol 0.0000E+OO O.OOOOE+OO O.OOOOE+OO 2.4000E+Ol O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 0 0 0 0 0 0 Dose Locations: 3 Location 1: Exclusion Area Boundary 2 1 2 O.OOOOE+OO 9. llOOE-04

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 56of102 7.2000E+02 O.OOOOE+OO 1 2 O.OOOOE+OO 3.SOOOE-04 7.2000E+02 O.OOOOE+OO 0 Location 2: Low Population Zone 2 1 6 O.OOOOE+OO l.3800E-04 2.0000E+OO S.8100E-05 8.0000E+OO 3 . 7700E-05 2.4000E+Ol l.4800E-OS 9.6000E+Ol 4.lSOOE-06 7.2000E+02 O.OOOOE+OO 1 4 0.0000E+OO 3.SOOOE-04 8.0000E+OO l.8000E-04 2.4000E+Ol 2.3000E-04 7.2000E+02 0 . 0000E+OO 0 Location 3: Control Room 3 0 1 2 O.OOOOE+OO 3.SOOOE-04 7.2000E+02 0.0000E+OO 1 4 O.OOOOE+OO l.OOOOE+OO 2.4000E+Ol 6 . 0000E-01 9.6000E+Ol 4.0000E-01 7.2000E+02 O.OOOOE+OO Effective Volume Location: 1 6 0.0000E+OO l.1800E-03 2.0000E+OO 9.0800E-04 8.0000E+OO 4.1400E-04 2.4000E+Ol 2.9000E-04 9.6000E+Ol 2.2600E-04 7.2000E+02 O.OOOOE+OO Simulation Parameters: 6 0 . 0000E+OO l.OOOOE-01 2.0000E+OO 5.0000E-01 8.0000E+OO l.OOOOE+OO 2.4000E+Ol 2.0000E+OO 9.6000E+Ol 8.0000E+OO 7.2000E+02 0.0000E+OO Output Filename: G: \Radtrad 3. oO 1

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 57of102 1 1 0 0 End of Scenario File

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 58of102 RADTRAD Version 3.03 (Spring 2001) run on 12/26/2013 at 19:19:56 Plant Description Number of Nuclides 60 Inventory Power= l.OOOOE+OO MWth Plant Power Level l.OOOOE+OO MWth Number of compartments 4 Compartment information Compartment number 1 (Source term fraction l.OOOOE+OO

Name: Reactor Coolant Compartment volume = l.OOOOE+OO (Cubic feet) Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Reactor Coolant to Condenser Exit Pathway Number 4: Reactor Coolant to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 3: Control Room Exhaust to Environment Inlet Pathway Number 4: Reactor Coolant to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume l.7600E+05 (Cubic feet) Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room Exhaust to Environment Compartment number 4 Name: Condenser Compartment volume l.OOOOE+OO (Cubic feet) Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 1: Reactor Coolant to Condenser Total number of pathways 4

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 59of102 RADTRAD Version 3.03 (Spring 2001) run on 12/26/2013 at 19:19:56 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0 . 0000 hrs 0.0000 hrs (gm) NOBLES l.OOOOE+OO O.OOOOE+OO 0.0000E+OO 2 . 271E+Ol IODINE l.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 4.346E-01 CESIUM l.OOOOE+OO 0 . 0000E+OO 0.0000E+OO 8 . 373E+OO TELLURIUM O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.000E+OO STRONTIUM O. OOOOE+OO 0.0000E+OO 0.0000E+OO O. OOOE+OO BARIUM O. OOOOE+OO O. OOOOE+OO O.OOOOE+OO 0 . 000E+OO RUTHENIUM O.OOOOE+OO O. OOOOE+OO O.OOOOE+OO O.OOOE+OO CERIUM 0.0000E+OO O.OOOOE+OO 0.0000E+OO O. OOOE+OO LANTHANUM O.OOOOE+OO 0.0000E+OO O.OOOOE+OO O.OOOE+OO Inventory Power 1. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) ( Sv-m3 /Bq-s) (Sv/Bq) (Sv/Bq) Kr-83m 1 7.014E+04 6.588E+03 l.500E-18 O.OOOE+OO 0.000E+OO Kr-85 1 6.668E+03 3.383E+08 l.190E-16 0.000E+OO O.OOOE+OO Kr-85m 1 l . 559E+05 1. 613E+04 7.480E-15 O. OOOE+OO O.OOOE+OO Kr-87 1 3.073E+05 4.578E+03 4.120E-14 O.OOOE+OO O.OOOE+OO Kr-88 1 4.336E+05 l.022E+04 1 . 020E-13 O.OOOE+OO O. OOOE+OO Rb-86 3 l.029E+Ol l.612E+06 4.810E-15 1. 330E-09 l.790E-09 Rb-88 3 3.829E+03 l.068E+03 3.360E-14 l.370E-12 2.260E-ll I-131 2 4.079E+04 6.947E+05 l.820E-14 2.920E-07 8.890E-09 I-132 2 5.885E+04 8.280E+03 l.120E-13 l.740E-09 l.030E-10 I-133 2 8.393E+04 7.488E+04 2.940E-14 4.860E-08 l.580E-09 I-134 2 9.321E+04 3.156E+03 l . 300E-13 2.880E-10 3 . 550E-ll I-135 2 7.841E+04 2.380E+04 8 . 294E-14 8.460E-09 3.320E-10 Xe-13lm 1 5.512E+03 l.028E+06 3.890E-16 0.000E+OO O.OOOE+OO Xe-133 1 l.OOOE+06 4.532E+05 1. 560E-15 O.OOOE+OO O.OOOE+OO Xe-133m 1 3.124E+04 l.890E+05 l.370E-15 O.OOOE+OO 0.000E+OO Xe-135 1 3.901E+05 3.272E+04 l . 190E-14 0.000E+OO O.OOOE+OO Xe-135m 1 l.970E+05 9.174E+02 2 . 040E-14 O.OOOE+OO O.OOOE+OO Xe-138 1 8.777E+05 8.502E+02 5.770E-14 O.OOOE+OO O. OOOE+OO Cs-134 3 l.086E+03 6.507E+07 7 . 570E-14 l.llOE-08 l.250E-08 Cs-136 3 3.074E+02 1. l32E+06 l . 060E-13 l.730E-09 l . 980E-09 Cs-137 3 6.549E+02 9.467E+08 2 . 725E-14 7.930E-09 8.630E-09 Cs-13 8 3 8.380E+03 l.932E+03 l.210E-13 3.570E-12 2.740E-ll Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1. 00 none 0.00 none 0.00 Kr-88 Rb-88 1. 00 none 0.00 none 0.00 I-131 Xe-13lm 0.01 none 0.00 none 0.00

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 60of102 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1. 00 none 0.00 none 0.00 Xe-135 Cs-135 1. 00 none 0.00 none 0.00 Xe-135m Xe-135 1. 00 none 0.00 none 0.00 Xe-138 Cs-138 1. 00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Iodine fractions Aerosol O.OOOOE+OO Elemental 9.7000E-01 Organic 3.0000E-02 COMPARTMENT DATA Compartment number 1: Reactor Coolant Compartment number 2: Environment Compartment number 3: Control Room Compartment number 4: Condenser PATHWAY DATA Pathway number 1: Reactor Coolant to Condenser Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic 0.0000E+OO 2.7560E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO l.6670E-01 0.0000E+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic O.OOOOE+OO 2.1100E+04 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 7.2000E+02 O.OOOOE+OO 0.0000E+OO 0.0000E+OO O.OOOOE+OO Pathway number 3: Control Room Exhaust to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic O.OOOOE+OO 2.1100E+04 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 O.OOOOE+OO 0.0000E+OO O.OOOOE+OO O.OOOOE+OO Pathway number 4: Reactor Coolant to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%) (cfm) Aerosol Elemental Organic

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 61of102 O.OOOOE+OO 4.1400E-01 0.0000E+OO O.OOOOE+OO 0.0000E+OO 2.4000E+Ol O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

mA-3)

O.OOOOE+OO 9.llOOE-04 7.2000E+02 O.OOOOE+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1)

O.OOOOE+OO 3.SOOOE-04 7.2000E+02 0.0000E+OO Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

mA-3)

O.OOOOE+OO 1.3800E-04 2.0000E+OO 5.8100E-05 8.0000E+OO 3.7700E-05 2.4000E+Ol l.4800E-05 9.6000E+Ol 4.lSOOE-06 7.2000E+02 0.0000E+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1)

O.OOOOE+OO 3.SOOOE-04 8.0000E+OO 1.8000E-04 2.4000E+Ol 2.3000E-04 7.2000E+02 O.OOOOE+OO Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/Q (s

mA-3)

O.OOOOE+OO l.1800E-03 2.0000E+OO 9.0800E-04 8.0000E+OO 4.1400E-04 2.4000E+Ol 2.9000E-04 9.6000E+Ol 2.2600E-04 7.2000E+02 O.OOOOE+OO Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-1)

O.OOOOE+OO 3.SOOOE-04 7.2000E+02 0.0000E+OO Location Occupancy Factor Data Time (hr) Occupancy Factor O.OOOOE+OO l.OOOOE+OO 2.4000E+Ol 6.0000E-01 9.6000E+Ol 4.0000E-01 7.2000E+02 0.0000E+OO USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+OO 1.0000E-01

CALCULATION NO. PM-1057 REV. No. S PAGE NO. 62of102 2.0000E+OO 5.0000E-01 8.0000E+OO l.OOOOE+OO 2.4000E+Ol 2.0000E+OO 9.6000E+Ol 8.0000E+OO 7.2000E+02 O.OOOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 63of102 RADTRAD Version 3.03 (Spring 2001) run on 12/26/2013 at 19:19:56 Dose Output Exclusion Area Boundary Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 7.3891E-01 2.9229E+Ol 1.6973E+OO Accumulated dose (rem) 7.3891E-01 2.9229E+Ol 1.6973E+OO Low Population Zone Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) l .1193E-01 4.4277E+OO 2.5711E-01 Accumulated dose (rem) l.1193E-01 4.4277E+OO 2. 5711E-01 Control Room Doses: Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 6. 1118E- 04 4.7834E-01 1.6296E-02 Accumulated dose (rem) 6 .1118E-04 4.7834E-01 1. 6296E-02 Exclusion Area Boundary Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) l.2601E-02 4.9861E-01 2.8953E-02 Accumulated dose (rem) 7.5151E-01 2.9728E+Ol 1.7262E+OO Low Population Zone Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) l.9088E-03 7.5530E-02 4.3859E-03 Accumulated dose (rem) l.1384E-01 4.5032E+OO 2.6149E-01 Control Room Doses: Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 3.4297E-02 2.6920E+Ol 9.1910E-01 Accumulated dose (rem) 3.4908E-02 2.7398E+Ol 9.3540E-01 Exclusion Area Boundary Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 64 of 102 Delta dose (rem) O.OOOOE+OO 0.0000E+OO O.OOOOE+OO Accumulated dose (rem) 7.5151E-Ol 2.9728E+Ol l.7262E+OO Low Population Zone Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) l .1384E-Ol 4.5032E+OO 2.6149E-Ol Control Room Doses: Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1. 4664E-02 1. 2116E+Ol 4.1798E-Ol Accumulated dose (rem) 4.9572E-02 3.9514E+Ol l.3534E+OO Exclusion Area Boundary Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 7.5151E-Ol 2.9728E+Ol l.7262E+OO Low Population Zone Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO 0.0000E+OO Accumulated dose (rem) l.1384E-Ol 4.5032E+OO 2.6149E-Ol Control Room Doses: Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1. 3526E-08 2.2222E-05 7.4822E-07 Accumulated dose (rem) 4. 9572E-02 3.9514E+Ol l.3534E+OO Exclusion Area Boundary Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO 0.0000E+OO O.OOOOE+OO Accumulated dose (rem) 7.5151E-Ol 2.9728E+Ol l.7262E+OO Low Population Zone Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO 0.0000E+OO Accumulated dose (rem) l.1384E-Ol 4.5032E+OO 2.6149E-Ol Control Room Doses: Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.0441E-28 3.7024E-24 l.2088E-25 Accumulated dose (rem) 4.9572E-02 3.9514E+Ol l.3534E+OO Exclusion Area Boundary Doses: Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 7.5151E-Ol 2.9728E+Ol l.7262E+OO Low Population Zone Doses:

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 65of102 Time (h) = 96. 0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO 0.0000E+OO 0.0000E+OO Accumulated dose (rem) 1.1384E-01 4.5032E+OO 2.6149E-01 Control Room Doses: Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9672E-78 6.8233E-74 2.2069E-75 Accumulated dose (rem) 4.9572E-02 3.9514E+Ol l.3534E+OO Exclusion Area Boundary Doses: Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 7.5151E-01 2.9728E+Ol l.7262E+OO Low Population Zone Doses: Time (h) = 720. 0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Accumulated dose (rem) 1.1384E-01 4.5032E+OO 2.6149E-01 Control Room Doses: Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0305-303 3.5826-299 1.1728-300 Accumulated dose (rem) 4.9572E-02 3.9514E+Ol l.3534E+OO I-131 Summary Reactor Coolant Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 6. 8411E+02 8.4155E+OO 9.8708E-02 0.004 6.8417E+02 6.0155E+Ol 6.9793E-01 0.167 O.OOOOE+OO 6.1181E+Ol 2.1952E-01 0.500 O.OOOOE+OO 6.1181E+Ol 1.9941E-02 0.800 O.OOOOE+OO 6.1181E+Ol 2.3019E-03 1.100 O.OOOOE+OO 6.1181E+Ol 2.6573E-04 1.400 O.OOOOE+OO 6. 1181E+Ol 3.0675E-05 1.700 O.OOOOE+OO 6 .1181E+Ol 3.5410E-06 2.000 O.OOOOE+OO 6 .1181E+Ol 4.0876E-07 2.300 0.0000E+OO 6.1181E+Ol 4.7186E-08 2.600 O.OOOOE+OO 6.1181E+Ol 5.4470E-09 2.900 O.OOOOE+OO 6.1181E+Ol 6.2878E-10 3.200 O.OOOOE+OO 6 .1181E+Ol 7. 2584E-ll 3.500 0.0000E+OO 6.1181E+Ol 8.3789E-12 3.800 0.0000E+OO 6.1181E+Ol 9.6723E-13 4.100 O.OOOOE+OO 6.1181E+Ol l .1165E-13 4.400 O.OOOOE+OO 6.1181E+Ol 1. 2889E-14 4.700 O.OOOOE+OO 6.1181E+Ol l.4879E-15 5.000 O.OOOOE+OO 6.1181E+Ol l.7175E-16 5.300 O.OOOOE+OO 6.1181E+Ol l.9827E-17 5.600 O.OOOOE+OO 6.1181E+Ol 2.2887E-18 5.900 O.OOOOE+OO 6.1181E+Ol 2.6421E-19 6.200 O.OOOOE+OO 6.1181E+Ol 3.0499E-20

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 66of102 6.500 0.0000E+OO 6 .1181E+Ol 3.5207E-21 6.800 O.OOOOE+OO 6.1181E+Ol 4.0642E-22 7.100 O.OOOOE+OO 6 .1181E+Ol 4.6916E-23 7.400 0.0000E+OO 6.1181E+Ol 5.4158E-24 7.700 O.OOOOE+OO 6.1181E+Ol 6.2518E-25 8.000 O.OOOOE+OO 6.1181E+Ol 7.2169E-26 8.300 O.OOOOE+OO 6 .1181E+Ol 8.3310E-27 8.600 0.0000E+OO 6.1181E+Ol 9.6170E-28 8.900 O.OOOOE+OO 6.1181E+Ol 1.1102E-28 9.200 0.0000E+OO 6.1181E+Ol l.2815E-29 9.500 O.OOOOE+OO 6.1181E+Ol 1.4794E-30 9.800 O.OOOOE+OO 6.1181E+Ol l.7077E-31 10.100 O.OOOOE+OO 6.1181E+Ol l.9713E-32 10.400 O.OOOOE+OO 6.1181E+Ol 2.2756E-33 24.000 0.0000E+OO 6.1181E+Ol 7.0802E-76

96. 000 O.OOOOE+OO 6.1181E+Ol 6.4083-301 720.000 0.0000E+OO 6.1181E+Ol O.OOOOE+OO Condenser Time (hr) I-131 (Curies) 0.000 5.6022E+03 0.004 4.0045E+04 0.167 4.0704E+04 0.500 4.0656E+04 0.800 4.0612E+04 1.100 4.0568E+04 1.400 4.0525E+04 1.700 4.0481E+04 2.000 4.0437E+04 2.300 4.0394E+04 2.600 4.0350E+04 2.900 4.0307E+04 3.200 4.0263E+04 3.500 4.0220E+04 3.800 4 . 0177E+04 4.100 4.0133E+04 4.400 4.0090E+04 4.700 4.0047E+04 5.000 4.0004E+04 5.300 3.9961E+04 5.600 3.9918E+04 5.900 3 . 9875E+04 6.200 3.9832E+04 6.500 3.9789E+04 6.800 3.9746E+04 7.100 3.9703E+04 7.400 3. 9660E+04 7.700 3.9618E+04 8.000 3.9575E+04 8.300 3.9532E+04 8.600 3 . 9490E+04 8.900 3.9447E+04 9.200 3.9405E+04 9.500 3.9362E+04 9.800 3.9320E+04 10.100 3.9278E+04 10.400 3.9235E+04 24.000 3.7365E+04

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 67of102 96.000 2.8849E+04 720.000 3.0666E+03 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO 0.004 2.9229E+Ol l.6973E+OO 4.4277E+OO 2.5711E-01 4.7834E-Ol l.6296E-02 0.167 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 2.7398E+Ol 9.3540E-Ol 0.500 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.8410E+Ol l.3152E+OO 0.800 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9387E+Ol l.3490E+OO 1.100 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9500E+Ol l.3529E+OO 1.400 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9513E+Ol l.3533E+OO 1.700 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 2.000 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 2.300 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 2.600 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 2.900 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 3.200 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 3.500 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 3.800 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 4.100 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 4.400 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 4.700 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 5.000 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 5.300 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 5.600 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 5.900 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 6.200 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 6.500 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 6.800 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 7.100 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 7.400 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 7.700 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 8.000 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 8.300 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 8.600 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 8.900 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 9.200 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 9.500 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 9.800 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 10.100 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-Ol 3.9514E+Ol l.3534E+OO 10.400 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 24.000 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol 1.3534E+OO 96.000 2.9728E+Ol l.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO 720.000 2.9728E+Ol 1.7262E+OO 4.5032E+OO 2.6149E-01 3.9514E+Ol l.3534E+OO Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 7.5151E-01 2.9728E+Ol l.7262E+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 68of102 Attachment 13.3 RADTRAD Nuclide Inventory File: PBCRDA3_def.txt Nuclide Inventory Name: RG 1.183 PBAPS CRDA EPU Core Inventory Normalized MACCS Sample 4030 MWt BWR Core Inventory Power Level: O.lOOOE+Ol Nuclides: 60 Nuclide 001: Co-58 7 0.6117120000E+07 0.5800E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 002: Co-60 7 0 .1663401096E+09 0.6000E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 003: Kr-83m 1 0.6588000000E+04 0.8300E+02 0.7014E+05 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 004: Kr-85 1 0 . 3382974720E+09 0.8500E+02 0.6668E+04 none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 005: Kr-85m 1 0.1612800000E+05 0 . 8500E+02 0 . 1559E+06 Kr-85 0 . 2100E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 006: Kr-87 1 0.4578000000E+04 0.8700E+02 0.3073E+06

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 69of102 Rb-87 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 007 : Kr-88 1 0.1022400000E+OS 0.8800E+02 0 . 4336E+06 Rb-88 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 008: Rb-86 3 0.1612224000E+07 0.8600E+02 0.1029E+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 009: Rb-88 3 0 . 1068000000E+04 0.8800E+02 0.3829E+02 none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 010: Sr-90 5 0.9189573120E+09 0.9000E+02 O.OOOOE+OO Y-90 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 011: Sr-91 5 0.3420000000E+OS 0.9100E+02 O.OOOOE+OO Y-9lm 0 . 5800E+OO Y-91 0.4200E+OO none O.OOOOE+OO Nuclide 012: Sr-92 5 0.9756000000E+04 0.9200E+02 O.OOOOE+OO Y-92 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 013: Y-90 9 0.2304000000E+06

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 70of102 0.9000E+02 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 014: Y-91 9 0.5055264000E+07 0.9100E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 015: Y-92 9 0.1274400000E+05

0. 9200E+02 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 016:

Y-93 9 0.3636000000E+05 0.9300E+02 0.0000E+OO Zr-93 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 017: Zr-95 9 0.5527872000E+07 0.9500E+02 0.0000E+OO Nb-95m 0.7000E-02 Nb-95 0.9900E+OO none O.OOOOE+OO Nuclide 018: Zr-97 9 0.6084000000E+05 0.9700E+02 0.0000E+OO Nb-97m 0.9500E+OO Nb-97 0.5300E-01 none O.OOOOE+OO Nuclide 019: Nb-95 9 0.3036960000E+07 0.9500E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 020: Mo-99

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 71of102 7 0.2376000000E+06 0.9900E+02 O.OOOOE+OO Tc-99m 0.8800E+OO Tc-99 0.1200E+OO none O.OOOOE+OO Nuclide 021: Tc-99m 7 0.2167200000E+OS 0.9900E+02 O.OOOOE+OO Tc-99 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 022: Ru-103 7 0.3393792000E+07 0.1030E+03 O.OOOOE+OO Rh-103m O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 023: Ru-105 7 0.1598400000E+OS 0 .1050E+03 O.OOOOE+OO Rh-105 O. lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 024: Ru-106 7 0.3181248000E+08 0.1060E+03 O.OOOOE+OO Rh-106 O. lOOOE+Ol none O. OOOOE+OO none O. OOOOE+OO Nuclide 025: Rh-105 7 0.1272960000E+06 0.1050E+03 O.OOOOE+OO none O.OOOOE+OO none 0 . 0000E+OO none O.OOOOE+OO Nuclide 026: Sb-127 4 0 . 3326400000E+06 0.1270E+03 O.OOOOE+OO Te-127m 0.1800E+OO Te-127 0.8200E+OO none O.OOOOE+OO

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 72of102 Nuclide 027: Sb-129 4 0.1555200000E+05 0.1290E+03 0.0000E+OO Te-129m 0.2200E+OO Te-129 0.7700E+OO none O.OOOOE+OO Nuclide 028: Te-127 4 0.3366000000E+05 0.1270E+03 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 029: Te-127m 4 0.9417600000E+07 0.1270E+03 O.OOOOE+OO Te-127 0.9800E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 030: Te-129 4 0.4176000000E+04 0.1290E+03 O.OOOOE+OO I-129 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 031: Te-129m 4 0 . 2903040000E+07 0.1290E+03 O.OOOOE+OO Te-129 0.6500E+OO I-129 0.3500E+OO none O.OOOOE+OO Nuclide 032: Te-131m 4 0.1080000000E+06 0 .1310E+03 0.0000E+OO Te-131 0.2200E+OO I-131 0.7800E+OO none O.OOOOE+OO Nuclide 033: Te-132 4 0.2815200000E+06

0. 1320E+03 0.0000E+OO I-132 O.lOOOE+Ol

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 73of102 none O.OOOOE+OO none O.OOOOE+OO Nuclide 034: I-131 2 0.6946560000E+06 0 .1310E+03 0.4079E+04 Xe-13lm O.llOOE-01 none O.OOOOE+OO none O.OOOOE+OO Nuclide 035: I-132 2 0.8280000000E+04 0 .1320E+03 0.5885E+04 none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 036: I-133 2 0.7488000000E+05 0 . 1330E+03 0.8393E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+OO none O.OOOOE+OO Nuclide 037: I-134 2 0.3156000000E+04 0.1340E+03 0.9321E+04 none O. OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 038: I-135 2 0.2379600000E+05 0 .1350E+03 0.7841E+04 Xe-135m 0.1500E+OO Xe-135 0.8500E+OO none O. OOOOE+OO Nuclide 039: Xe-13lm 1 0.1028160000E+07 0.1310E+03 0.5512E+04 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 040: Xe-133 1 0.4531680000E+06 0.1330E+03

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 74of102 0.1000E+07 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 041: Xe-133m 1 0.1890432000E+06 0.1330E+03 0.3124E+05 Xe-133 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 042: Xe-135 1 0.3272400000E+05 0.1350E+03 0.3901E+06 Cs-135 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 043: Xe-135m 1 0.9174000000E+03 0.1350E+03 0.1970E+06 Xe-135 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 044: Xe-138 1 0.8502000000E+03 0.1380E+03 0.8777E+06 Cs-138 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 045: Cs-134 3 0.6507177120E+08 0.1340E+03 0.1086E+02 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 046: Cs-136 3 0.1131840000E+07 0.1360E+03 0.3074E+Ol none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 047: Cs-137 3

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 75of102 0.9467280000E+09 0.1370E+03 0.6549E+Ol Ba-137m 0.9500E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 048: Cs-138 3 0.1932000000E+04 0.1380E+03 0.8380E+02 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 049: Ba-140 6 0.1100736000E+07 0.1400E+03 0 . 0000E+OO La-140 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 050: La-140 9 0.1449792000E+06 0.1400E+03 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 051: La-141 9 0 . 1414800000E+05 0.1410E+03 O.OOOOE+OO Ce-141 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 052: La-142 9 0.5550000000E+04 0.1420E+03 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 053: Ce-141 8 0.2808086400E+07 0.1410E+03 0.0000E+OO none O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO Nuclide 054:

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 76of102 Ce-143 8 0.1188000000E+06 0.1430E+03 O.OOOOE+OO Pr-143 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 055: Ce-144 8 0.2456352000E+08 0.1440E+03 0.0000E+OO Pr-144m 0 . 1800E-01 Pr-144 0.9800E+OO none O.OOOOE+OO Nuclide 056: Pr-143 9 0.1171584000E+07 0.1430E+03 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 057: Nd-147 9 0.9486720000E+06 0.1470E+03 O.OOOOE+OO Pm-147 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 058: Np-239 8 0.2034720000E+06 0.2390E+03 0.0000E+OO Pu-239 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 059: Pu-241 8 0.4544294400E+09 0.2410E+03 O.OOOOE+OO U-237 0 . 2400E-04 Am-241 0 . lOOOE+Ol none O.OOOOE+OO Nuclide 060: Cm-242 9 0.1406592000E+08 0.2420E+03 0.0000E+OO Pu-238 O.lOOOE+Ol none O.OOOOE+OO

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 77of102 none O.OOOOE+OO End of Nuclear Inventory File

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 78of102 Attachment 13.4 RADTRAD Nuclide Inventory File: PBCRDA_GLD_def.txt Nuclide Inventory Name: PBAPS CRDA Core Inventory - Gland Seal Release Normalized MACCS Sample 4030 MWt BWR Core Inventory Power Level: O.lOOOE+Ol Nuclides: 60 Nuclide 001: Co-58 7 0.6117120000E+07 0.5800E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 002: Co-60 7 0.1663401096E+09 0.6000E+02 0.0000E+OO none 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 003: Kr-83m 1 0.6588000000E+04 0.8300E+02 0.7014E+05 none 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 004: Kr-85 1 0.3382974720E+09 0.8500E+02 0.6668E+04 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 005: Kr-85m 1 0.1612800000E+05 0.8500E+02 0.1559E+06 Kr-85 0.2100E+OO none O.OOOOE+OO none 0.0000E+OO Nuclide 006: Kr-87 1

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 79of102 0.4578000000E+04 0.8700E+02 0.3073E+06 Rb-87 0.lOOOE+Ol none O.OOOOE+OO none 0.0000E+OO Nuclide 007: Kr-88 1 0.1022400000E+05 0.8800E+02 0.4336E+06 Rb-88 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 008: Rb-86 3 0.1612224000E+07 0.8600E+02 0.1029E+02 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 009: Rb-88 3 0.1068000000E+04 0.8800E+02 0.3829E+04 none 0.0000E+OO none O.OOOOE+OO none 0.0000E+OO Nuclide 010: Sr-90 5 0.9189573120E+09 0.9000E+02 0.0000E+OO Y-90 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 011: Sr-91 5 0.3420000000E+05 0.9100E+02 O.OOOOE+OO Y-91m 0.5800E+OO Y-91 0.4200E+OO none 0.0000E+OO Nuclide 012: Sr-92 5 0.9756000000E+04

0. 9200E+02 O.OOOOE+OO Y-92 O.lOOOE+Ol

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 80of102 none O.OOOOE+OO none O.OOOOE+OO Nuclide 013: Y-90 9 0.2304000000E+06 0.9000E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 014: Y-91 9 0.5055264000E+07 0.9100E+02 O.OOOOE+OO none O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO Nuclide 015: Y-92 9 0.1274400000E+05 0.9200E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none 0.0000E+OO Nuclide 016: Y-93 9 0.3636000000E+05 0.9300E+02 O.OOOOE+OO Zr-93 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 017: Zr-95 9 0.5527872000E+07 0.9500E+02 O.OOOOE+OO Nb-95m 0.7000E-02 Nb-95 0.9900E+OO none O.OOOOE+OO Nuclide 018: Zr-97 9 0.6084000000E+05 0.9700E+02 0.0000E+OO Nb-97m 0.9500E+OO Nb-97 0.5300E-01 none O.OOOOE+OO Nuclide 019: Nb-95

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 81of102 9 0.3036960000E+07 0.9500E+02 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 020: Mo-99 7 0.2376000000E+06 0.9900E+02 0.0000E+OO Tc-99m 0.8800E+OO Tc-99 0.1200E+OO none O.OOOOE+OO Nuclide 021: Tc-99m 7 0.2167200000E+05 0.9900E+02 O.OOOOE+OO Tc-99 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 022: Ru-103 7 0.3393792000E+07 0.1030E+03 O.OOOOE+OO Rh-103m O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 023: Ru-105 7 0.1598400000E+05 0.1050E+03 0.0000E+OO Rh-105 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 024: Ru-106 7 0.3181248000E+OB 0.1060E+03 O.OOOOE+OO Rh-106 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 025: Rh-105 7 0 .1272960000E+06 0.1050E+03 O.OOOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 82of102 none 0.0000E+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 026: Sb-127 4 0.3326400000E+06 0 . 1270E+03 O.OOOOE+OO Te-127m 0.lBOOE+OO Te-127 0.8200E+OO none O.OOOOE+OO Nuclide 027: Sb-12 9 4 0.1555200000E+05 0.1290E+03 O.OOOOE+OO Te-129m 0.2200E+OO Te-12 9 0.7700E+OO none O.OOOOE+OO Nuclide 028: Te-127 4 0.3366000000E+05 0.1270E+03 O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 029: Te-127m 4 0 . 9417600000E+07 0.1270E+03 O.OOOOE+OO Te-127 0.9800E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 030: Te-129 4 0.4176000000E+04 0 .1290E+03 0.0000E+OO I-129 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 031: Te-129m 4 0.2903040000E+07 0.1290E+03 0.0000E+OO Te-129 0.6500E+OO I-129 0.3500E+OO none O.OOOOE+OO Nuclide 032:

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 83of102 Te-131m 4 0.1080000000E+06 0.1310E+03 O.OOOOE+OO Te-131 0.2200E+OO I-131 0.7800E+OO none O.OOOOE+OO Nuclide 033: Te-132 4 0.2815200000E+06 0 .1320E+03 O.OOOOE+OO I-132 O.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO Nuclide 034: I-131 2 0.6946560000E+06 0.1310E+03 0.4079E+05 Xe-131m O.llOOE-01 none O.OOOOE+OO none O.OOOOE+OO Nuclide 035: I-132 2 0.8280000000E+04 0.1320E+03 0.5885E+05 none O.OOOOE+OO none O.OOOOE+OO none O. OOOOE+OO Nuclide 036: I-133 2 0.7488000000E+05 0.1330E+03 0.8393E+05 Xe-133m 0.2900E-01 Xe-133 0.9700E+OO none O.OOOOE+OO Nuclide 037: I-134 2 0.3156000000E+04 0.1340E+03 0.9321E+05 none O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO Nuclide 038: I-135 2 0.2379600000E+05 0 .1350E+03

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 84 of 102 0.7841E+05 Xe-135m 0.1500E+OO Xe-135 0.8500E+OO none O.OOOOE+OO Nuclide 039: Xe-13lm 1 0.1028160000E+07 0.1310E+03 0.5512E+04 none O.OOOOE+OO none O.OOOOE+OO none 0.0000E+OO Nuclide 040: Xe-133 1 0.4531680000E+06 0.1330E+03 0.1000E+07 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 041: Xe-133m 1 0.1890432000E+06 0 .1330E+03 0.3124E+05 Xe-133 0.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO Nuclide 042: Xe-135 1 0.3272400000E+05 0 .1350E+03 0.3901E+06 Cs-135 0.lOOOE+Ol none O.OOOOE+OO none 0.0000E+OO Nuclide 043: Xe-135m 1 0.9174000000E+03 0.1350E+03 0.1970E+06 Xe-135 O.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO Nuclide 044: Xe-138 1 0.8502000000E+03 0.1380E+03 0.8777E+06 Cs-138 0.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 85 of 102 Nuclide 045: Cs-134 3 0.6507177120E+08 0.1340E+03 0.1086E+04 none 0.0000E+OO none O.OOOOE+OO none 0.0000E+OO Nuclide 046: Cs-136 3 0.1131840000E+07 0.1360E+03 0.3074E+03 none O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO Nuclide 047: Cs-137 3 0.9467280000E+09 0.1370E+03 0.6549E+03 Ba-137m 0.9500E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 048: Cs-138 3 0.1932000000E+04 0.1380E+03 0.8380E+04 none O.OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 049: Ba-140 6 0.1100736000E+07 0.1400E+03 O. OOOOE+OO La-140 O.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO Nuclide 050: La-140 9 0.1449792000E+06 0.1400E+03 O.OOOOE+OO none O. OOOOE+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 051: La-141 9 0.1414800000E+05

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 86of102 0.1410E+03 O.OOOOE+OO Ce-141 O.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO Nuclide 052: La-142 9 0.5550000000E+04 0.1420E+03 O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO none O.OOOOE+OO Nuclide 053: Ce-141 8 0.2808086400E+07 0.1410E+03 O.OOOOE+OO none O.OOOOE+OO none 0.0000E+OO none O.OOOOE+OO Nuclide 054: Ce-143 8 0.1188000000E+06 0.1430E+03 O.OOOOE+OO Pr-143 O.lOOOE+Ol none 0.0000E+OO none O.OOOOE+OO Nuclide 055: Ce-144 8 0.2456352000E+08 0.1440E+03 O.OOOOE+OO Pr-144m O.lBOOE-01 Pr-144 0.9800E+OO none 0.0000E+OO Nuclide 056: Pr-143 9 0.1171584000E+07 0.1430E+03 0.0000E+OO none O.OOOOE+OO none 0.0000E+OO none 0.0000E+OO Nuclide 057: Nd-147 9

0. 9486720000E+06 0.1470E+03 O.OOOOE+OO Pm-147 O.lOOOE+Ol none O.OOOOE+OO

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 87of102 none O.OOOOE+OO Nuclide 058: Np-239 8 0.2034720000E+06 0.2390E+03 O.OOOOE+OO Pu-239 0.lOOOE+Ol none O.OOOOE+OO none 0.0000E+OO Nuclide 059: Pu-241 8 0.4544294400E+09 0.2410E+03 O.OOOOE+OO U-237 0.2400E-04 Am-241 O.lOOOE+Ol none O.OOOOE+OO Nuclide 060: Cm-242 9 0.1406592000E+08 0.2420E+03 O.OOOOE+OO Pu-238 0.lOOOE+Ol none O.OOOOE+OO none O.OOOOE+OO End of Nuclear Inventory File

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 88of102 Attachment 13.5 RADTRAD Release Fraction and Timing File: pbcrda_rft.txt Release Fraction and Timing Name: PBAPS Control Rod Drop Accident Fission Product Gap Inventory Duration (h) : NON-LOCA Accident chk inventory 0.0036E+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO Noble Gases: 0 . lOOOE+Ol O. OOOOE+OO O.OOOOE+OO 0.0000E+OO Iodine: O.lOOOE+Ol O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Cesium: O.lOOOE+Ol O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Tellurium: O. OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Strontium: O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Barium: O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Ruthenium: O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Cerium: O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Lanthanum: O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Non-Radioactive Aerosols (kg): O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO End of Release File

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 89of102 Attachment 13.6 RADTRAD Dose Conversion Factor File: pbcrda_fgll&12.txt HCGS_FGR11&12 added 7 nuclides; deleted Sr-89,Ba-139,Cm244,AM-242,Pu238-240 2/2001 Implicit daughter halflives (m) less than 90 and less than 0.100 of parent 9 ORGANS DEFINED IN THIS FILE: GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 60 NUCLIDES DEFINED IN THIS FILE: Co-58 y Co-60 y Kr- 83m data entered by Gopal J. Patel NUCORE Kr-85 Kr-85m Kr-87 Kr-88 Rb-86 D Rb-88 data entered by Gopal J. Patel NUCORE Sr-90 y Sr-91 y Including:Y-9lm Sr-92 y Y-90 y Y-91 y Y-92 Y Y-93 Y Zr-95 D Zr-97 y Including:Nb-97m , Including:Nb-97 Nb-95 y Mo-99 y Tc-99m D Ru-103 y Including:Rh-103m Ru-105 Y Ru-106 y Including:Rh-106 Rh-105 y Sb-127 w Sb-129 w Te-127 W Te-127m W Te-129 W Te-129m w Including:Te-129 Te-13lm w Including:Te-131 Te-132 w I-131 D I-132 D I-133 D I-134 D I-135 D Including:Xe - 135m Xe-13lm data entered by Gopal J. Patel NU CORE Xe-133 Xe-133m data entered by Go pal J. Patel NU CORE Xe-135 Xe-135m data entered by Gopal J. Patel NUCORE/10/08/2001 Xe-138 data entered by Gopal J. Patel NUCORE/10/08/2001 Cs-134 D Cs-136 D Cs-137 D Including:Ba-137m Cs-138 data entered by Gopal J. Patel NUCORE Ba-140 D

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 90of102 La-140 W La-141 D La-142 D Ce-141 Y Ce-143 Y Ce-144 y Including:Pr-144m, Including:Pr-144 Pr-143 Y Nd-147 Y Np-239 W Pu-241 Y Cm-242 W CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC Co-58 GONADS 4.660E-14 2.867E-ll 5.828E-10 9.970E-16-l.OOOE+OO 6.170E-10 l.040E-09 BREAST 5.300E-14 2.737E-ll 5.565E-10 9.520E-16-l.OOOE+OO 9.370E-10 l.790E-10 LUNGS 4 . 640E-14 2.617E-ll 5.319E-10 9.lOOE-16-1.000E+OO l.600E-08 8.530E-ll RED MARR 4.530E-14 2.671E-ll 5.430E-10 9.290E-16-l.OOOE+OO 9.230E-10 2.600E-10 BONE SUR 7.410E-14 3.795E-ll 7.716E-10 l.320E-15-l . OOOE+OO 6.930E-10 l.250E-10 THYROID 4 . 770E-14 2.720E-ll 5.530E-10 9.460E-16-l.OOOE+OO 8.720E-10 6.310E-ll REMAINDER 4.440E-14 2.585E-ll 5.255E-10 8.990E-16-l.OOOE+OO l.890E-09 l.580E-09 EFFECTIVE 4.760E-14 2.732E-ll 5.553E-10 9.500E-16-l.OOOE+OO 2.940E-09 8.090E-10 SKIN{FGR) 5.580E-14 3.278E-ll 6.664E-10 l.140E-15-l.OOOE+OO O.OOOE+OO 0.000E+OO Co-60 GONADS l.230E-13 7.056E-ll l.480E-09 2.450E-15-l.OOOE+OO 4.760E-09 3.190E-09 BREAST l.390E-13 6.739E-ll l.413E-09 2.340E-15-l.OOOE+OO l.840E-08 l.lOOE-09 LUNGS l . 240E-13 6.537E-ll l.371E-09 2.270E-15-l.OOOE+OO 3.450E-07 8.770E-10 RED MARR l . 230E-13 6.710E-ll l.407E-09 2.330E-15-l.OOOE+OO l.720E-08 l.320E-09 BONE SUR l.780E-13 8.956E-ll l.879E-09 3.llOE-15-1.000E+OO l.350E-08 9.390E-10 THYROID l . 270E-13 6.480E-ll l.359E-09 2.250E-15-l.OOOE+OO l.620E-08 7.880E-10 REMAINDER l . 200E-13 6.508E-ll l.365E-09 2.260E-15-l.OOOE+OO 3.600E-08 4.970E-09 EFFECTIVE l . 260E-13 6.768E-ll l.419E-09 2.350E-15-l.OOOE+OO 5.910E-08 2.770E-09 SKIN{FGR) l.450E-13 7.948E-ll l.667E-09 2.760E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Kr-83m GONADS l . 710E-18 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BREAST 5.050E-18 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO LUNGS l.640E-19 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO RED MARR 3 . 830E-19 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO BONE SUR 2.250E-18 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO THYROID 6.430E-19 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO REMAINDER 5 . JOOE-19 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO EFFECTIVE l.500E-18 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO SKIN{FGR) 3.560E-17 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Kr-85 GONADS l.170E-16 8.121E-14 l.704E-12 2.820E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST l.340E-16 7.891E-14 l.656E-12 2.740E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS l.140E-16 7.056E-14 l.481E-12 2.450E-18-l . OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR l.090E-16 6.998E-14 l.469E-12 2.430E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 2.200E-16 l.287E-13 2.702E-12 4.470E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID l.180E-16 7.459E-14 l.565E-12 2.590E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER l.090E-16 6.941E-14 l.457E-12 2.410E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE l.190E-16 7.603E-14 l.596E-12 2.640E-18-l.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN{FGR) l.320E-14 2.304E-ll 4.835E-10 8.000E-16-1 . 000E+OO O.OOOE+OO O.OOOE+OO Kr-85m GONADS 7.JlOE-15 2.594E-12 3.653E-12 l.570E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 8 . 410E-15 2.527E-12 3.560E-12 l.530E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 7.040E-15 2.379E-12 3.351E-12 l.440E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 6.430E-15 2.346E-12 3.304E-12 l.420E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR l.880E-14 5.286E-12 7.446E-12 3.200E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 7.330E-15 2.395E-12 3.374E-12 l.450E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 6.640E-15 2.313E-12 3.257E-12 l.400E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 7.480E-15 2.511E-12 3.537E-12 l.520E-16-l .O OOE+OO O.OOOE+OO O.OOOE+OO SKIN {FGR) 2.240E-14 2.247E-ll 3.164E-ll l.360E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Kr-87 GONADS 4.000E-14 4.962E-12 5 . 026E-12 7.610E-16-l.OOOE+OO 0.000E+OO O.OOOE+OO BREAST 4.500E-14 4.740E-12 4.802E-12 7.270E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 4.040E-14 4.603E-12 4.663E-12 7.060E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 91of102 RED MARR 4.000E-14 4.708E-12 4.769E-12 7.220E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 6.020E-14 6.514E-12 6.598E-12 9.990E-16-l.OOOE+OO 0.000E+OO O.OOOE+OO THYROID 4.130E-14 4.473E-12 4.531E-12 6.860E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 3.910E-14 4.590E-12 4.650E-12 7.040E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 4.120E-14 4.773E-12 4.835E-12 7.320E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) l.370E-13 8.802E-ll 8.916E-ll l.350E-14-l.OOOE+OO O.OOOE+OO O.OOOE+OO Kr-88 GONADS 9.900E-14 2.278E-ll 2.655E-ll l.800E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST l.llOE-13 2.177E-ll 2.537E-ll l.720E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS l.OlOE-13 2.139E-ll 2.493E-ll l.690E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR l.OOOE-13 2.190E-ll 2.552E-ll l.730E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR l.390E-13 2.886E-ll 3.363E-ll 2.280E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID l.030E-13 2.012E-ll 2.345E-ll l.590E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 9.790E-14 2.139E-ll 2.493E-ll l.690E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE l.020E-13 2.202E-ll 2.567E-ll l.740E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) l.350E-13 5.607E-ll 6.534E-ll 4.430E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Rb-86 GONADS 4.710E-15 2.788E-12 5.187E-ll 9.740E-17-l.OOOE+OO l.340E-09 2.150E-09 BREAST 5.340E-15 2.662E-12 4.953E-ll 9.300E-17-l.OOOE+OO l.330E-09 2.140E-09 LUNGS 4.710E-15 2.553E-12 4.750E-ll 8.920E-17-l.OOOE+OO 3.300E-09 2.140E-09 RED MARR 4.640E-15 2.619E-12 4.873E-ll 9.150E-17-l.OOOE+OO 2.320E-09 3.720E-09 BONE SUR 7.050E-15 3.635E-12 6.764E-ll l.270E-16-l.OOOE+OO 4.270E-09 6.860E-09 THYROID 4.840E-15 2.599E-12 4.836E-ll 9.080E-17-l.OOOE+OO l.330E-09 2.140E-09 REMAINDER 4.520E-15 2.542E-12 4.729E-ll 8.880E-17-l.OOOE+OO l.380E-09 2.330E-09 EFFECTIVE 4.810E-15 2.665E-12 4.958E-ll 9.310E-17-l.OOOE+OO l.790E-09 2.530E-09 SKIN(FGR) 4.850E-14 2.210E-10 4.lllE-09 7.720E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Rb-88 GONADS 3.260E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.310E-12 2.780E-12 BREAST 3.670E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.430E-12 2.820E-12 LUNGS 3.310E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.470E-10 2.910E-12 RED MARR 3.300E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.450E-12 2.760E-12 BONE SUR 4.620E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.470E-12 2.750E-12 THYROID 3.370E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.370E-12 2.430E-12 REMAINDER 3.210E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO l.380E-ll l.500E-10 EFFECTIVE 3.360E-14 0.000E+OO O.OOOE+OO 0.000E+00-1.000E+OO 2.260E-ll 4.710E-ll SKIN(FGR) l.830E-13 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Sr-90 GONADS 7.780E-18 9.590E-15 2.014E-13 3.330E-19-l.OOOE+OO 2.690E-10 5.040E-ll BREAST 9.490E-18 l.008E-14 2.116E-13 3.500E-19-l.OOOE+OO 2.690E-10 5.040E-ll LUNGS 6.440E-18 6.307E-15 l.324E-13 2.190E-19-l.OOOE+OO 2.860E-06 5.040E-ll RED MARR 5.440E-18 5.558E-15 l.167E-13 l.930E-19-l.OOOE+OO 3.280E-08 6.450E-09 BONE SUR 2.280E-17 2.393E-14 5.025E-13 8.310E-19-l.OOOE+OO 7.090E-08 l.390E-08 THYROID 7.330E-18 7.171E-15 l.506E-13 2.490E-19-l.OOOE+OO 2.690E-10 5.040E-ll REMAINDER 6.llOE-18 6.422E-15 l.348E-13 2.230E-19-l.OOOE+OO 5.730E-09 6.700E-09 EFFECTIVE 7.530E-18 8.179E-15 l.717E-13 2.840E-19-l.OOOE+OO 3.510E-07 3.230E-09 SKIN(FGR) 9.200E-15 4.032E-12 8.465E-ll l.400E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO Sr-91 GONADS 4.819E-14 2.155E-ll 5.062E-ll l.026E-15-l.OOOE+OO 5.669E-ll 2.520E-10 BREAST 5.477E-14 2.059E-ll 4.838E-ll 9.806E-16-l.OOOE+OO l.775E-ll 3.676E-ll LUNGS 4.803E-14 l.970E-ll 4.626E-ll 9.376E-16-l.OOOE+OO 2.170E-09 l.055E-ll RED MARR 4.691E-14 2.0llE-11 4.722E-ll 9.570E-16-l.OOOE+OO 2.275E-ll 5.659E-ll BONE SUR 7.674E-14 2.852E-ll 6.709E-ll l.360E-15-l.OOOE+OO l.306E-ll 2.070E-ll THYROID 4.938E-14 2.035E-ll 4.782E-ll 9.693E-16-l.OOOE+OO 9.930E-12 l.968E-12 REMAINDER 4.610E-14 l.948E-ll 4.573E-ll 9.268E-16-l.OOOE+OO 5.802E-10 2.557E-09 EFFECTIVE 4.924E-14 2.057E-ll 4.832E-ll 9.793E-16-l.OOOE+OO 4.547E-10 8.455E-10 SKIN(FGR) 9.938E-14 l.748E-10 3.987E-10 8.080E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Sr-92 GONADS 6.610E-14 l.593E-ll l.830E-ll l.300E-15-l.OOOE+OO l.020E-ll 8.180E-ll BREAST 7.480E-14 l.520E-ll l.745E-ll l.240E-15-l.OOOE+OO 6.490E-12 l.700E-ll LUNGS 6.670E-14 l.483E-ll l.703E-ll l.210E-15-l.OOOE+OO l.050E-09 7.220E-12 RED MARR 6.620E-14 l.520E-ll l.745E-ll l.240E-15-l.OOOE+OO 6.980E-12 2.290E-ll BONE SUR 9.490E-14 2.0lOE-11 2.308E-ll l.640E-15-l.OOOE+OO 4.360E-12 8.490E-12 THYROID 6.820E-14 l.446E-ll l.661E-ll l.180E-15-l.OOOE+OO 3.920E-12 l.300E-12 REMAINDER 6.450E-14 l.471E-ll l.689E-ll l.200E-15-l.OOOE+OO 2.900E-10 l.720E-09 EFFECTIVE 6.790E-14 l.532E-ll l.759E-ll l.250E-15-l.OOOE+OO 2.180E-10 5.430E-10 SKIN(FGR) 8.560E-14 2.280E-ll 2.618E-ll l.860E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Y-90

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 92of102 GONADS l.890E-16 l.586E-13 l.601E-12 5.750E-18-l.OOOE+OO 5.170E-13 l.430E-14 BREAST 2.200E-16 l.578E-13 l.593E-12 5.720E-18-l.OOOE+OO 5.170E-13 l.270E-14 LUNGS l.770E-16 l.313E-13 l.326E-12 4.760E-18-l.OOOE+OO 9.310E-09 l.260E-14 RED MARR l.620E-16 l.261E-13 l.273E-12 4.570E-18-l.OOOE+OO l.520E-ll 3.700E-13 BONE SUR 4.440E-16 3.228E-13 3.259E-12 l.170E-17-1.000E+OO l.510E-ll 3.670E-13 THYROID l.870E-16 l.385E-13 1.398E-12 5.020E-18-l.OOOE+OO 5.170E-13 l.260E-14 REMAINDER l.680E-16 l.291E-13 1.303E-12 4.680E-18-1.000E+OO 3.870E-09 9.680E-09 EFFECTIVE 1.900E-16 l.468E-13 l.482E-12 5.320E-18-l.OOOE+OO 2.280E-09 2.910E-09 SKIN(FGR) 6.240E-14 2.897E-10 2.924E-09 1.050E-14-1.000E+OO 0.000E+OO 0.000E+OO Y-91 GONADS 2.560E-16 1.756E-13 3.546E-12 6.llOE-18-1.000E+OO 8.200E-12 3.540E-12 BREAST 2.930E-16 l.713E-13 3.459E-12 5.960E-18-1.000E+OO 8.920E-12 5.540E-13 LUNGS 2.500E-16 1.526E-13 3.082E-12 5.310E-18-l.OOOE+OO 9.870E-08 2.020E-13 RED MARR 2.410E-16 l.521E-13 3.070E-12 5.290E-18-1.000E+OO 3.190E-10 6.590E-12 BONE SUR 4.560E-16 2.903E-13 5.862E-12 l.OlOE-17-1.000E+OO 3.lBOE-10 6.130E-12 THYROID 2.600E-16 1.564E-13 3.157E-12 5.440E-18-l.OOOE+OO 8.500E-12 l.290E-13 REMAINDER 2.390E-16 l.509E-13 3.047E-12 5.250E-18-1.000E+OO 4.200E-09 8.570E-09 EFFECTIVE 2.600E-16 l.650E-13 3.332E-12 5.740E-18-l.OOOE+OO l.320E-08 2.570E-09 SKIN(FGR) 3.850E-14 1.989E-10 4.016E-09 6.920E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Y-92 GONADS 1.270E-14 3.855E-12 4.872E-12 2.650E-16-l.OOOE+OO 2.610E-12 1.960E-11 BREAST l.440E-14 3.680E-12 4.652E-12 2.530E-16-l.OOOE+OO 1.500E-12 3.550E-12 LUNGS 1.270E-14 3.535E-12 4.468E-12 2.430E-16-1.000E+OO l.240E-09 1.390E-12 RED MARR l.250E-14 3.608E-12 4.560E-12 2.480E-16-l.OOOE+OO 2.070E-12 4.910E-12 BONE SUR l.950E-14 5.091E-12 6.435E-12 3.500E-16-1.000E+OO l.510E-12 1.750E-12 THYROID 1.300E-14 3.579E-12 4.523E-12 2.460E-16-l.OOOE+OO l.050E-12 l.770E-13 REMAINDER l.220E-14 3.506E-12 4.431E-12 2.410E-16-1.000E+OO 2.030E-10 1.700E-09 EFFECTIVE 1.300E-14 3.680E-12 4.652E-12 2.530E-16-1.000E+OO 2.llOE-10 5.150E-10 SKIN (FGR) l.140E-13 2.022E-10 2.556E-10 1.390E-14-l.OOOE+OO O.OOOE+OO 0.000E+OO Y-93 GONADS 4.670E-15 2.108E-12 4.989E-12 9.510E-17-l.OOOE+OO 5.310E-12 2.200E-11 BREAST 5.300E-15 2.026E-12 4.794E-12 9.140E-17-1.000E+OO 1.740E-12 3.130E-12 LUNGS 4.680E-15 l.937E-12 4.585E-12 8.740E-17-1.000E+OO 2.520E-09 8.670E-13 RED MARR 4.580E-15 1.972E-12 4.669E-12 8.900E-17-1.000E+OO 4.040E-12 4.930E-12 BONE SUR 7.580E-15 2.948E-12 6.977E-12 1.330E-16-1.000E+OO 3.140E-12 1.730E-12 THYROID 4.790E-15 l.908E-12 4.516E-12 8.610E-17-1.000E+OO 9.260E-13 l.260E-13 REMAINDER 4.SlOE-15 l.919E-12 4.543E-12 8.660E-17-l.OOOE+OO 9.250E-10 4.090E-09 EFFECTIVE 4.800E-15 2.021E-12 4.784E-12 9.120E-17-1.000E+OO 5.820E-10 l.230E-09 SKIN(FGR) 8.500E-14 2.726E-10 6.452E-10 l.230E-14-l.OOOE+OO O.OOOE+OO O.OOOE+OO Zr-95 GONADS 3.530E-14 2.182E-11 4.421E-10 7.590E-16-1.000E+OO l.880E-09 8.160E-10 BREAST 4.0lOE-14 2.084E-ll 4.223E-10 7.250E-16-1.000E+OO l.910E-09 1.050E-10 LUNGS 3.SlOE-14 l.989E-11 4.030E-10 6.920E-16-l.OOOE+OO 2.170E-09 2.340E-11 RED MARR 3.430E-14 2.030E-11 4.112E-10 7.060E-16-1.000E+OO l.300E-08 2.140E-10 BONE SUR 5.620E-14 2.875E-11 5.824E-10 l.OOOE-15-1.000E+OO l.030E-07 4.860E-10 THYROID 3.610E-14 2.076E-11 4.205E-10 7.220E-16-l.OOOE+OO 1.440E-09 8.270E-12 REMAINDER 3.360E-14 l.963E-11 3.978E-10 6.830E-16-1.000E+OO 2.280E-09 2.530E-09 EFFECTIVE 3.600E-14 2.078E-11 4.211E-10 7.230E-16-l.OOOE+OO 6.390E-09 l.020E-09 SKIN (FGR) 4.SOOE-14 2.561E-11 5.190E-10 8.910E-16-1.000E+OO 0.000E+OO O.OOOE+OO Zr-97 GONADS 4.331E-14 2.179E-11 7.799E-11 9.253E-16-l.OOOE+OO 1.840E-10 6.228E-10 BREAST 4.928E-14 2.083E-11 7.455E-11 8.846E-16-l.OOOE+OO 4.706E-11 8.137E-11 LUNGS 4.322E-14 l.992E-ll 7.127E-11 8.456E-16-1.000E+OO 4.108E-09 1.770E-11 RED MARR 4.224E-14 2.034E-11 7.279E-11 8.634E-16-l.OOOE+OO 6.376E-11 1.302E-10 BONE SUR 6.897E-14 2.881E-11 l.031E-10 1.224E-15-1.000E+OO 3.504E-11 4.558E-11 THYROID 4.443E-14 2.061E-11 7.377E-ll 8.755E-16-1.000E+OO 2.315E-11 2.671E-12 REMAINDER 4.139E-14 l.966E-11 7.035E-11 8.345E-16-l.OOOE+OO 2.041E-09 6.990E-09 EFFECTIVE 4.432E-14 2.078E-11 7.438E-11 8.824E-16-1.000E+OO l.171E-09 2.283E-09 SKIN (FGR) 9.835E-14 2.281E-10 8.148E-10 9.587E-15-1.000E+OO 0.000E+OO O.OOOE+OO Nb-95 GONADS 3.660E-14 2.253E-ll 4.435E-10 7.850E-16-1.000E+OO 4.320E-10 8.050E-10 BREAST 4.160E-14 2.150E-ll 4.231E-10 7.490E-16-1.000E+OO 4.070E-10 l.070E-10 LUNGS 3.650E-14 2.055E-11 4.045E-10 7.160E-16-l.OOOE+OO 8.320E-09 2.740E-11 RED MARR 3.560E-14 2.lOlE-11 4.135E-10 7.320E-16-l.OOOE+OO 4.420E-10 l.990E-10 BONE SUR 5.790E-14 2.957E-ll 5.819E-10 1.030E-15-1.000E+OO 5.130E-10 2.940E-10 THYROID 3.750E-14 2.144E-11 4.220E-10 7.470E-16-1.000E+OO 3.580E-10 1.lBOE-11 REMAINDER 3.490E-14 2.032E-11 4.000E-10 7.080E-16-l.OOOE+OO 1.070E-09 l.470E-09

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 93of102 EFFECTIVE 3.740E-14 2.147E-ll 4.226E-10 7.480E-16-l.OOOE+OO l.570E-09 6.950E-10 SKIN(FGR) 4.300E-14 2.598E-ll 5.112E-10 9.050E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO Mo-99 GONADS 7.130E-15 4.282E-12 4.403E-ll l.550E-16-l.OOOE+OO 9.510E-ll 2.180E-10 BREAST 8.130E-15 4.116E-12 4.233E-ll l.490E-16-l.OOOE+OO 2.750E-ll 3.430E-ll LUNGS 7.060E-15 3.867E-12 3.977E-ll l.400E-16-l.OOOE+OO 4.290E-09 l.510E-ll RED MARR 6.820E-15 3.923E-12 4.034E-ll l.420E-16-l.OOOE+OO 5.240E-ll 8.320E-ll BONE SUR l.240E-14 6.105E-12 6.278E-ll 2.210E-16-l.OOOE+OO 4.130E-ll 6.320E-ll THYROID 7.270E-15 4.033E-12 4.147E-ll l.460E-16-l.OOOE+OO l.520E-ll l.030E-ll REMAINDER 6.740E-15 3.812E-12 3.920E-ll l.380E-16-l.OOOE+OO l.740E-09 4.280E-09 EFFECTIVE 7.280E-15 4.061E-12 4.176E-ll l.470E-16-l.OOOE+OO 1.070E-09 1.360E-09 SKIN(FGR) 3.140E-14 l.039E-10 l.068E-09 3.760E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Tc-99m GONADS 5.750E-15 2.334E-12 3.877E-12 1.240E-16-l.OOOE+OO 2.770E-12 9.750E-12 BREAST 6.650E-15 2.258E-12 3.752E-12 l.200E-16-l.OOOE+OO 2.150E-12 3.570E-12 LUNGS 5.490E-15 2.127E-12 3.533E-12 l.130E-16-l.OOOE+OO 2.280E-11 3.140E-12 RED MARR 4.910E-15 2.070E-12 3.439E-12 1.lOOE-16-1.000E+OO 3.360E-12 6.290E-12 BONE SUR 1.630E-14 5.383E-12 8.942E-12 2.860E-16-l.OOOE+OO 2.620E-12 4.060E-12 THYROID 5.750E-15 2.145E-12 3.564E-12 l.140E-16-l.OOOE+OO 5.0lOE-11 8.460E-ll REMAINDER 5.150E-15 2.070E-12 3.439E-12 1.lOOE-16-1.000E+OO l.020E-ll 3.340E-ll EFFECTIVE 5.890E-15 2.277E-12 3.783E-12 l.210E-16-l.OOOE+OO 8.800E-12 l.680E-11 SKIN{FGR) 7.140E-15 2.710E-12 4.502E-12 1.440E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO Ru-103 GONADS 2.191E-14 l.404E-11 2.783E-10 4.892E-16-l.OOOE+OO 3.070E-10 5.720E-10 BREAST 2.512E-14 l.350E-ll 2.677E-10 4.705E-16-l.OOOE+OO 3.llOE-10 l.200E-10 LUNGS 2.180E-14 l.273E-11 2.522E-10 4.432E-16-l.OOOE+OO 1.561E-08 7.310E-11 RED MARR 2.lOOE-14 l.287E-11 2.551E-10 4.483E-16-l.OOOE+OO 3.190E-10 1.660E-10 BONE SUR 3.892E-14 l.958E-11 3.882E-10 6.823E-16-l.OOOE+OO 2.370E-10 9.631E-11 THYROID 2.241E-14 l.331E-ll 2.639E-10 4.638E-16-1.000E+OO 2.570E-10 6.250E-ll REMAINDER 2.080E-14 l.248E-11 2.472E-10 4.346E-16-l.OOOE+OO l.250E-09 2.llOE-09 EFFECTIVE 2.251E-14 l.332E-11 2.641E-10 4.642E-16-l.OOOE+OO 2.421E-09 8.271E-10 SKIN(FGR) 2.774E-14 l.785E-11 3.543E-10 6.229E-16-l.OOOE+OO O.OOOE+OO 0.000E+OO Ru-105 GONADS 3.720E-14 l.327E-11 l.861E-ll 8.070E-16-l.OOOE+OO 1.590E-11 9.670E-ll BREAST 4.240E-14 l.271E-11 l.783E-ll 7.730E-16-l.OOOE+OO 6.610E-12 l.590E-11 LUNGS 3.700E-14 l.210E-11 l.697E-ll 7.360E-16-l.OOOE+OO 5.730E-10 6.210E-12 RED MARR 3.590E-14 l.230E-ll 1.725E-ll 7.480E-16-l.OOOE+OO 7.700E-12 2.350E-ll BONE SUR 6.280E-14 l.809E-11 2.537E-ll 1.lOOE-15-1.000E+OO 4.620E-12 8.890E-12 THYROID 3.800E-14 l.260E-11 l.766E-ll 7.660E-16-l.OOOE+OO 4.150E-12 l.820E-12 REMAINDER 3.540E-14 l.189E-ll l.667E-ll 7.230E-16-l.OOOE+OO 1.610E-10 8.540E-10 EFFECTIVE 3.810E-14 l.265E-11 l.773E-ll 7.690E-16-l.OOOE+OO l.230E-10 2.870E-10 SKIN{FGR) 6.730E-14 7.368E-11 1.033E-10 4.480E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Ru-106 GONADS l.OlOE-14 6.411E-12 l.340E-10 2.230E-16-l.OOOE+OO 1.300E-09 l.640E-09 BREAST 1.160E-14 6.152E-12 l.286E-10 2.140E-16-1.000E+OO 1.780E-09 l.440E-09 LUNGS l.OlOE-14 5.836E-12 l.220E-10 2.030E-16-l.OOOE+OO l.040E-06 l.420E-09 RED MARR 9.750E-15 5.893E-12 l.232E-10 2.050E-16-l.OOOE+OO l.760E-09 l.460E-09 BONE SUR l.720E-14 8.883E-12 l.856E-10 3.090E-16-l.OOOE+OO l.610E-09 l.430E-09 THYROID l.030E-14 6.066E-12 l.268E-10 2.llOE-16-1.000E+OO l.720E-09 l.410E-09 REMAINDER 9.630E-15 5.721E-12 l.196E-10 l.990E-16-l.OOOE+OO l.200E-08 2.llOE-08 EFFECTIVE l.040E-14 6.095E-12 l.274E-10 2.120E-16-l.OOOE+OO l.290E-07 7.400E-09 SKIN{FGR) l.090E-13 4.082E-10 8.531E-09 l.420E-14-l.OOOE+OO O.OOOE+OO O.OOOE+OO Rh-105 GONADS 3.640E-15 2.127E-12 1.411E-ll 7.980E-17-l.OOOE+OO 2.llOE-11 5.800E-ll BREAST 4.160E-15 2.063E-12 l.369E-ll 7.740E-17-l.OOOE+OO 5.610E-12 8.970E-12 LUNGS 3.570E-15 l.935E-12 l.284E-ll 7.260E-17-l.OOOE+OO 9.580E-10 3.860E-12 RED MARR 3.380E-15 l.946E-12 l.291E-ll 7.300E-17-l.OOOE+OO 7.770E-12 l.470E-ll BONE SUR 7.530E-15 3.332E-12 2.210E-ll l.250E-16-l.OOOE+OO 4.460E-12 6.750E-12 THYROID 3.680E-15 l.983E-12 l.316E-ll 7.440E-17-l.OOOE+OO 2.880E-12 2.910E-12 REMAINDER 3.390E-15 l.885E-12 l.250E-ll 7.070E-17-l.OOOE+OO 4.530E-10 l.270E-09 EFFECTIVE 3.720E-15 2.031E-12 l.347E-ll 7.620E-17-l.OOOE+OO 2.580E-10 3.990E-10 SKIN{FGR) l.070E-14 4.691E-12 3.112E-ll l.760E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO Sb-127 GONADS 3.260E-14 l.985E-ll 2.441E-10 7.lOOE-16-1.000E+OO 2.520E-10 6.140E-10 BREAST 3.720E-14 l.904E-ll 2.341E-10 6.810E-16-l.OOOE+OO 9.120E-ll 7.600E-ll LUNGS 3.240E-14 l.809E-ll 2.224E-10 6.470E-16-l.OOOE+OO 6.940E-09 l.570E-ll RED MARR 3.140E-14 l.834E-ll 2.255E-10 6.560E-16-l.OOOE+OO l.610E-10 l.330E-10

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 94of102 BONE SUR 5.520E-14 2.720E-ll 3.345E-10 9.730E-16-l.OOOE+OO l.340E-10 5.240E-ll THYROID 3.330E-14 l.884E-ll 2.317E-10 6.740E-16-l.OOOE+OO 6.150E-ll 4.640E-12 REMAINDER 3.090E-14 l.775E-ll 2.183E-10 6.350E-16-l.OOOE+OO 2.330E-09 5.870E-09 EFFECTIVE 3.330E-14 l.890E-ll 2.324E-10 6.760E-16-l.OOOE+OO l.630E-09 l.950E-09 SKIN(FGR) 5.580E-14 7.967E-ll 9.799E-10 2.850E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Sb-129 GONADS 6.970E-14 2.336E-ll 3.231E-ll l.440E-15-l.OOOE+OO 2.150E-ll l.510E-10 BREAST 7.910E-14 2.222E-ll 3.074E-ll l.370E-15-l.OOOE+OO l.2BOE-ll 2.560E-ll LUNGS 6.980E-14 2.141E-ll 2.962E-ll l.320E-15-l.OOOE+OO 8.980E-10 9.390E-12 RED MARR 6.860E-14 2.190E-ll 3.029E-ll l.350E-15-l.OOOE+OO l.700E-ll 3.670E-ll BONE SUR l.070E-13 3.033E-ll 4.196E-ll l.870E-15-l.OOOE+OO l.460E-ll l.340E-ll THYROID 7.160E-14 2.174E-ll 3.007E-ll l.340E-15-l.OOOE+OO 9.720E-12 l.470E-12 REMAINDER 6.710E-14 2.125E-ll 2.939E-ll l.310E-15-l.OOOE+OO l.870E-10 l.450E-09 EFFECTIVE 7.140E-14 2.238E-ll 3.096E-ll l.380E-15-l.OOOE+OO l.740E-10 4.840E-10 SKIN (FGR) l.050E-13 8.273E-ll l.144E-10 5.lOOE-15-1.000E+OO 0.000E+OO O.OOOE+OO Te-127 GONADS 2.370E-16 l.191E-13 2.661E-13 5.480E-18-l.OOOE+OO 2.020E-12 4.020E-12 BREAST 2.730E-16 l.158E-13 2.588E-13 5.330E-18-l.OOOE+OO l.BBOE-12 3.000E-12 LUNGS 2.320E-16 l.060E-13 2.370E-13 4.BBOE-18-1.000E+OO 4.270E-10 2.890E-12 RED MARR 2.210E-16 l.058E-13 2.365E-13 4.870E-18-l.OOOE+OO 4.090E-12 6.570E-12 BONE SUR 4.650E-16 l.862E-13 4.162E-13 8.570E-18-l.OOOE+OO 4.090E-12 6.460E-12 THYROID 2.400E-16 l.106E-13 2.472E-13 5.090E-18-l.OOOE+OO l.840E-12 2.860E-12 REMAINDER 2.210E-16 l.036E-13 2.316E-13 4.770E-18-l.OOOE+OO l.llOE-10 6.130E-10 EFFECTIVE 2.420E-16 l.125E-13 2.515E-13 5.lBOE-18-1.000E+OO 8.600E-ll l.870E-10 SKIN(FGR) l.140E-14 l.173E-ll 2.622E-ll 5.400E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO Te-127m GONADS l.900E-16 4.689E-13 9.642E-12 l.630E-17-l.OOOE+OO l.lOOE-10 l.250E-10 BREAST 2.690E-16 5.150E-13 l.059E-ll l.790E-17-l.OOOE+OO l.lOOE-10 9.740E-ll LUNGS 7.620E-17 l.602E-13 3.295E-12 5.570E-18-l.OOOE+OO 3.340E-08 9.620E-ll RED MARR 6.430E-17 l.249E-13 2.567E-12 4.340E-18-l.OOOE+OO 5.360E-09 5.430E-09 BONE SUR 3.940E-16 9.005E-13 l.852E-ll 3.130E-17-l.OOOE+OO 2.040E-08 2.070E-08 THYROID l.500E-16 2.779E-13 5.714E-12 9.660E-18-l.OOOE+OO 9.660E-ll 9.430E-ll REMAINDER 8.640E-17 l.999E-13 4.lllE-12 6.950E-18-l.OOOE+OO l.660E-09 2.980E-09 EFFECTIVE l.470E-16 3.251E-13 6.684E-12 l.130E-17-l.OOOE+OO 5.BlOE-09 2.230E-09 SKIN(FGR) 8.490E-16 l.496E-12 3.076E-ll 5.200E-17-l.OOOE+OO 0.000E+OO O.OOOE+OO Te-129 GONADS 2.710E-15 3.889E-13 3.922E-13 6.510E-17-l.OOOE+OO 5.050E-13 l.590E-12 BREAST 3.120E-15 3.BOOE-13 3.832E-13 6.360E-17-l.OOOE+OO 5.390E-13 6.050E-13 LUNGS 2.640E-15 3.298E-13 3.326E-13 5.520E-17-l.OOOE+OO l.530E-10 4.910E-13 RED MARR 2.540E-15 3.298E-13 3.326E-13 5.520E-17-l.OOOE+OO 6.190E-13 7.640E-13 BONE SUR 4.BSOE-15 5.753E-13 5.802E-13 9.630E-17-l.OOOE+OO 6.220E-13 5.400E-13 THYROID 2.740E-15 3.525E-13 3.555E-13 5.900E-17-l.OOOE+OO 5.090E-13 3.360E-13 REMAINDER 2.520E-15 3.262E-13 3.289E-13 5.460E-17-l.OOOE+OO 7.280E-12 l.790E-10 EFFECTIVE 2.750E-15 3.590E-13 3.621E-13 6.0lOE-17-1.000E+OO 2.090E-ll 5.450E-ll SKIN(FGR) 3.570E-14 3.429E-ll 3.458E-ll 5.740E-15-l.OOOE+OO 0.000E+OO O.OOOE+OO Te-129m GONADS 3.321E-15 2.206E-12 4.799E-ll 8.561E-17-l.OOOE+OO l.783E-10 2.420E-10 BREAST 3.838E-15 2.181E-12 4.739E-ll 8.454E-17-l.OOOE+OO l.694E-10 l.664E-10 LUNGS 3.176E-15 l.741E-12 3.815E-ll 6.BOBE-17-1.000E+OO 4.040E-08 l.593E-10 RED MARR 3.071E-15 l.729E-12 3.793E-ll 6.768E-17-l.OOOE+OO 3.lOOE-09 3.500E-09 BONE SUR 5.772E-15 3.287E-12 7.147E-ll l.275E-16-l.OOOE+OO 7.050E-09 7.990E-09 THYROID 3.341E-15 l.923E-12 4.201E-ll 7.495E-17-l.OOOE+OO l.563E-10 l.572E-10 REMAINDER 3.048E-15 l.746E-12 3.822E-ll 6.819E-17-l.OOOE+OO 3.275E-09 7.196E-09 EFFECTIVE 3.337E-15 l.974E-12 4.308E-ll 7.686E-17-l.OOOE+OO 6.484E-09 2.925E-09 SKIN (FGR) 3.BllE-14 l.501E-10 3.360E-09 6.00lE-15-1.000E+OO O.OOOE+OO O.OOOE+OO Te-13lm GONADS 7.292E-14 4.020E-ll 2.343E-10 l.535E-15-l.OOOE+OO 2.345E-10 7.415E-10 BREAST 8.286E-14 3.853E-ll 2.246E-10 l.472E-15-l.OOOE+OO 9.309E-ll l.361E-10 LUNGS 7.265E-14 3.657E-ll 2.131E-10 l.397E-15-l.OOOE+OO 2.296E-09 6.335E-ll RED MARR 7.097E-14 3.736E-ll 2.178E-10 l.427E-15-l.OOOE+OO l.417E-10 2.435E-10 BONE SUR l.174E-13 5.467E-ll 3.189E-10 2.090E-15-l.OOOE+OO 2.276E-10 3.248E-10 THYROID 7.471E-14 3.741E-ll 2.lBlE-10 l.429E-15-l.OOOE+OO 3.669E-08 4.383E-08 REMAINDER 6.965E-14 3.626E-ll 2.113E-10 l.385E-15-l.OOOE+OO 9.509E-10 3.153E-09 EFFECTIVE 7.463E-14 3.825E-ll 2.229E-10 l.461E-15-l.OOOE+OO l.758E-09 2.514E-09 SKIN(FGR) l.038E-13 l.033E-10 6.lBBE-10 4.056E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Te-132 GONADS l.020E-14 6.812E-12 7.706E-ll 2.450E-16-l.OOOE+OO 4.150E-10 5.410E-10

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 95of102 BREAST l.lBOE-14 6.756E-12 7.643E-ll 2.430E-16-l.OOOE+OO 3.630E-10 3.500E-10 LUNGS 9.650E-15 5.727E-12 6.479E-ll 2.060E-16-l.OOOE+OO l.670E-09 3.300E-10 RED MARR 8.950E - 15 5.588E-12 6.322E-ll 2.0lOE-16-1.000E+OO 4.270E-10 4.440E-10 BONE SUR 2.420E-14 l.273E-ll l.441E-10 4.580E-16-l.OOOE+OO 7.120E-10 8 . 300E-10 THYROID l.020E-14 5.978E-12 6.762E-ll 2.150E-16-l.OOOE+OO 6.280E-08 5.950E-08 REMAINDER 9.160E-15 5.644E-12 6.385E-ll 2.030E-16-l.OOOE+OO 7.890E-10 l.490E-09 EFFECTIVE l.030E-14 6.339E-12 7.171E-ll 2.280E-16-l.OOOE+OO 2.550E-09 2.540E-09 SKIN(FGR) l.390E-14 8.313E-12 9.405E-ll 2.990E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO I-131 GONADS l.780E-14 l.119E-ll l.789E-10 3.940E-16-l.OOOE+OO 2.530E-ll 4.070E-ll BREAST 2.040E-14 l.082E-ll l.730E-10 3.BlOE-16-1.000E+OO 7.BBOE-11 l . 210E-10 LUNGS l.760E-14 l.016E-ll l.626E-10 3.580E-16-l.OOOE+OO 6.570E-10 l.020E-10 RED MARR l.680E-14 l.022E-ll l.635E-10 3.600E-16-l.OOOE+OO 6.260E-ll 9.440E-ll BONE SUR 3.450E-14 l.675E-ll 2.679E-10 5.900E-16-l.OOOE+OO 5.730E-ll 8.720E-ll THYROID l.BlOE-14 l.053E-ll l.685E-10 3.710E-16-l.OOOE+OO 2.920E-07 4.760E-07 REMAINDER l.670E-14 9.908E-12 l.585E-10 3.490E-16-l.OOOE+OO 8.030E-ll l.570E-10 EFFECTIVE l.820E-14 l.067E-ll l.707E-10 3.760E-16-l.OOOE+OO 8.890E-09 l.440E-08 SKIN(FGR) 2.980E-14 l.825E-ll 2.920E-10 6.430E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO I-132 GONADS l.090E-13 2.523E-ll 2.771E-ll 2.320E-15-l.OOOE+OO 9.950E-12 2.330E-ll BREAST l.240E-13 2.414E-ll 2.652E-ll 2.220E-15-l.OOOE+OO l.410E-ll 2 . 520E-ll LUNGS l.090E-13 2.305E-ll 2.532E-ll 2.120E-15-l.OOOE+OO 2.710E-10 2.640E-ll RED MARR l.070E-13 2.360E-ll 2.592E-ll 2.170E-15-l.OOOE+OO l.400E-ll 2.460E-ll BONE SUR l.730E-13 3.327E-ll 3.655E-ll 3.060E-15-l.OOOE+OO l.240E-ll 2.190E-ll THYROID l.120E-13 2.381E-ll 2.616E-ll 2.190E-15-l.OOOE+OO l.740E-09 3.870E-09 REMAINDER l.050E-13 2.283E-ll 2.509E-ll 2.lOOE-15-1.000E+OO 3.780E-ll l.650E-10 EFFECTIVE l.120E-13 2.403E-ll 2.640E-ll 2.210E-15-l.OOOE+OO l.030E-10 l.820E-10 SKIN(FGR) l.580E-13 8.199E-ll 9.007E-ll 7.540E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO I-133 GONADS 2.870E-14 l.585E-ll 6.748E-ll 6.270E-16-l.OOOE+OO l.950E-ll 3.630E-ll BREAST 3.280E-14 l.519E-ll 6.468E-ll 6.0lOE-16-1.000E+OO 2.940E-ll 4.680E-ll LUNGS 2.860E-14 l.446E-ll 6.156E-ll 5.720E-16-l.OOOE+OO 8.200E-10 4.530E-ll RED MARR 2.770E-14 l.466E-ll 6.242E-ll 5.BOOE-16-1.000E+OO 2.720E-ll 4.300E-ll BONE SUR 4.870E-14 2.161E-ll 9.202E-ll 8.550E-16-l.OOOE+OO 2.520E-ll 4.070E-ll THYROID 2.930E-14 l.502E-ll 6.393E-ll 5.940E-16-l.OOOE+OO 4.860E-08 9.lOOE-08 REMAINDER 2.730E-14 l.418E-ll 6.038E-ll 5.610E-16-l.OOOE+OO 5.000E-11 l.550E-10 EFFECTIVE 2.940E-14 l.509E-ll 6.425E-ll 5.970E-16-l.OOOE+OO l.580E-09 2.BOOE-09 SKIN (FGR) 5.830E-14 l.150E-10 4.897E-10 4.550E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO I-134 GONADS l.270E-13 l.200E-ll l.202E-ll 2.640E-15-l.OOOE+OO 4.250E-12 l.lOOE-11 BREAST l.440E-13 l.145E-ll l.147E-ll 2.520E-15-l.OOOE+OO 6.170E-12 l.170E-ll LUNGS l.270E-13 l.lOOE-11 l.102E-ll 2.420E-15-l.OOOE+OO l.430E-10 l.260E-ll RED MARR l.250E-13 l.127E-ll l.129E-ll 2.480E-15-l.OOOE+OO 6.0BOE-12 l.090E-ll BONE SUR l.960E-13 l.568E-ll l.571E-ll 3.450E-15-l.OOOE+OO 5.310E-12 9 . 320E-12 THYROID l.300E-13 l.127E-ll l.129E-ll 2.480E-15-l.OOOE+OO 2.BBOE-10 6.210E-10 REMAINDER l.220E-13 l . 091E-ll l.093E-ll 2.400E-15-l.OOOE+OO 2.270E-ll l.340E-10 EFFECTIVE l.300E-13 l.150E-ll l.152E-ll 2.530E-15-l.OOOE+OO 3.550E-ll 6.660E-ll SKIN (FGR) l.870E-13 4.477E-ll 4.485E-ll 9.850E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO I-135 GONADS 8.078E-14 3.113E-ll 5.489E-ll l.599E-15-l.OOOE+OO l.700E-ll 3.610E-ll BREAST 9.143E-14 2.971E-ll 5.240E-ll l . 526E-15-l.OOOE+OO 2.340E-ll 3 . 850E-ll LUNGS 8.145E-14 2.886E-ll 5.089E-ll l.482E-15-l.OOOE+OO 4.410E-10 3.750E-ll RED MARR 8.054E-14 2.965E-ll 5.228E-ll l.523E-15-l.OOOE+OO 2.240E-ll 3.650E-ll BONE SUR l.184E-13 3.983E-ll 7.024E-ll 2.046E-15-l.OOOE+OO 2.0lOE-11 3.360E-ll THYROID 8.324E-14 2.852E-ll 5.030E-ll l.465E-15-l.OOOE+OO 8.460E-09 l.790E-08 REMAINDER 7.861E-14 2.883E-ll 5.084E-ll l.481E-15-l.OOOE+OO 4.700E-ll l.540E-10 EFFECTIVE 8.294E-14 2.989E-ll 5.271E-ll l.535E-15-l.OOOE+OO 3.320E-10 6.0BOE-10 SKIN (FGR) l.156E-13 9 . 826E-ll l.733E-10 5.047E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-13lm GONADS 4.570E-16 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BREAST 6.020E-16 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O. OOOE+OO LUNGS 2.670E-16 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO RED MARR 2.270E-16 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BONE SUR l.060E-15 0.000E+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO THYROID 3.910E-16 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO REMAINDER 2.710E-16 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 3.890E-16 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO 0.000E+OO

CALCULATION NO. PM-1057 REV.No. 5 PAGE NO. 96 of 102 SKIN(FGR} 4.820E-15 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Xe-133 GONADS l.610E-15 l.465E-12 2.052E-ll 5.200E-17-l.OOOE+OO 0.000E+OO O.OOOE+OO BREAST l.960E-15 l.505E-12 2.107E-ll 5.340E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS l.320E-15 l.045E-12 l.464E-ll 3.710E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR l.070E-15 8.791E-13 l.231E-ll 3.120E-17-l.OOOE+OO 0.000E+OO O.OOOE+OO BONE SUR 5.130E-15 4.254E-12 5.958E-ll l.510E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID l.510E-15 l.181E-12 l.653E-ll 4.190E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER l.240E-15 l.042E-12 l.460E-ll 3.700E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE l.560E-15 l.299E-12 l.819E-ll 4.610E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR} 4.970E-15 l.953E-12 2.734E-ll 6.930E-17-l.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-133m GONADS l.420E-15 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BREAST l.700E-15 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO LUNGS l.190E-15 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO RED MARR l.lOOE-15 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BONE SUR 3.230E-15 0.000E+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO THYROID l.360E-15 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO REMAINDER l.150E-15 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO EFFECTIVE l.370E-15 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO SKIN (FGR} l.040E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Xe-135 GONADS l.170E-14 5.455E-12 l.194E-ll 2.530E-16-l.OOOE+OO 0.000E+OO O.OOOE+OO BREAST l.330E-14 5.325E-12 l.166E-ll 2.470E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS l.130E-14 4.959E-12 l.086E-ll 2.300E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR l.070E-14 4.959E-12 l.086E-ll 2.300E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 2.570E-14 9.120E-12 l.997E-ll 4.230E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID l.180E-14 5.023E-12 l.lOOE-11 2.330E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER l.080E-14 4.829E-12 l.058E-ll 2.240E-16-l.OOOE+OO 0.000E+OO O.OOOE+OO EFFECTIVE l.190E-14 5.217E-12 l.142E-ll 2.420E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR} 3.120E-14 4.506E-ll 9.867E-ll 2.090E-15-l.OOOE+OO 0.000E+OO O.OOOE+OO Xe-135m GONADS 2.000E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO BREAST 2.290E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO LUNGS l.980E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO RED MARR l.910E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BONE SUR 3.500E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO THYROID 2.040E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO REMAINDER l.890E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO EFFECTIVE 2.040E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO SKIN(FGR} 2.970E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Xe-138 GONADS 5.590E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BREAST 6.320E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO LUNGS 5.660E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO RED MARR 5.600E-14 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO BONE SUR 8.460E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO THYROID 5.770E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO REMAINDER 5.490E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 5.770E-14 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO SKIN (FGR} l.070E-13 O.OOOE+OO 0.000E+OO O.OOOE+00-1.000E+OO 0.000E+OO O.OOOE+OO Cs-134 GONADS 7.400E-14 4.607E-ll 9.646E-10 l.600E-15-l.OOOE+OO l.300E-08 2.060E-08 BREAST 8.430E-14 4.406E-ll 9.224E-10 l.530E-15-l.OOOE+OO l.080E-08 l.720E-08 LUNGS 7.370E-14 4.204E-ll 8.802E-10 l.460E-15-l.OOOE+OO l.180E-08 l.760E-08 RED MARR 7.190E-14 4.262E-ll 8.922E-10 l.480E-15-l.OOOE+OO l.180E-08 l.870E-08 BONE SUR l.200E-13 6.105E-ll l.278E-09 2.120E-15-l.OOOE+OO l.lOOE-08 l.740E-08 THYROID 7.570E-14 4.377E-ll 9.163E-10 l.520E-15-l.OOOE+OO l.llOE-08 l.760E-08 REMAINDER 7.060E-14 4.147E-ll 8.681E-10 l.440E-15-l.OOOE+OO l.390E-08 2.210E-08 EFFECTIVE 7.570E-14 4.377E-ll 9.163E-10 l.520E-15-l.OOOE+OO l.250E-08 l.980E-08 SKIN(FGR} 9.450E-14 6.249E-ll l.308E-09 2.170E-15-l.OOOE+OO 0.000E+OO O.OOOE+OO Cs-136 GONADS l.040E-13 6.223E-ll l.102E-09 2.180E-15-l.OOOE+OO l.880E-09 3.040E-09 BREAST l.180E-13 5.966E-ll l.056E-09 2.090E-15-l.OOOE+OO l.670E-09 2.650E-09 LUNGS l.040E-13 5.710E-ll l.OllE-09 2.000E-15-1.000E+OO 2.320E-09 2.620E-09 RED MARR l.OlOE-13 5.824E-ll l.031E-09 2.040E-15-l.OOOE+OO l.860E-09 2.950E-09 BONE SUR l.660E-13 8.422E-ll l.491E-09 2.950E-15-l.OOOE+OO l.700E-09 2.710E-09

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 97of102 THYROID l.070E-13 5.852E-ll l.036E-09 2.050E-15-l.OOOE+OO l.730E-09 2.740E-09 REMAINDER 9.950E-14 5.652E-ll l.OOlE-09 l.980E-15-l.OOOE+OO 2.190E-09 3.520E-09 EFFECTIVE l.060E-13 5.966E-ll l.056E-09 2.090E-15-l.OOOE+OO l.980E-09 3 . 040E-09 SKIN(FGR) l.250E-13 7.251E-ll l.284E-09 2.540E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Cs-137 GONADS 2.669E-14 l.669E-ll 3.530E-10 5.840E-16-l.OOOE+OO 8.760E-09 l.390E-08 BREAST 3.047E-14 l.596E-ll 3.376E-10 5.585E-16-l.OOOE+OO 7.840E-09 l.240E-08 LUNGS 2.649E-14 l.517E-ll 3.209E-10 5.309E-16-l.OOOE+OO 8.820E-09 l . 270E-08 RED MARR 2.583E-14 l.542E-ll 3.260E-10 5.394E-16-l.OOOE+OO 8.300E-09 l.320E-08 BONE SUR 4.382E-14 2.238E-ll 4.734E-10 7.832E-16-l.OOOE+OO 7.940E-09 l.260E-08 THYROID 2.725E-14 l.588E-ll 3.358E-10 5.556E-16-l.OOOE+OO 7.930E-09 l.260E-08 REMAINDER 2.536E-14 l.490E-ll 3.152E-10 5.215E-16-l.OOOE+OO 9.120E-09 l.450E-08 EFFECTIVE 2.725E-14 l.585E-ll 3.353E-10 5.546E-16-l.OOOE+OO 8.630E-09 l.350E-08 SKIN(FGR) 4.392E-14 5.253E-ll l.llOE-09 l.836E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Cs-138 GONADS l.170E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 3.280E-12 8.000E-12 BREAST l.330E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 4.020E-12 8.000E-12 LUNGS l.190E-13 0.000E+OO O.OOOE+OO 0.000E+00-1.000E+OO l.590E-10 8.530E-12 RED MARR l.180E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 3.950E-12 7.370E-12 BONE SUR l.700E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 3.SSOE-12 6.470E-12 THYROID l.210E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 3.570E-12 5.730E-12 REMAINDER l.lSOE-13 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO 2.060E-11 l.570E-10 EFFECTIVE l.210E-13 0.000E+OO O.OOOE+OO O.OOOE+00-1.000E+OO 2.740E-ll 5.250E-11 SKIN (FGR) 2.170E-13 O.OOOE+OO O.OOOE+OO O.OOOE+00-1.000E+OO O.OOOE+OO O.OOOE+OO Ba-140 GONADS 8.410E-15 5.451E-12 9.607E-11 1.910E-16-1.000E+OO 4.300E-10 9.960E-10 BREAST 9.640E-15 5.280E-12 9.305E-11 1.850E-16-1.000E+OO 2.870E-10 1.590E-10 LUNGS 8.270E-15 4.852E-12 8.550E-ll 1.700E-16-l.OOOE+OO 1.660E-09 6.630E-11 RED MARR 7.930E-15 4.880E-12 8.601E-11 l.710E-16-1.000E+OO 1.290E-09 4.390E-10 BONE SUR 1.550E-14 8.020E-12 l.413E-10 2.810E-16-l.OOOE+OO 2.410E-09 5.530E-10 THYROID 8.530E-15 5.109E-12 9.003E-ll 1.790E-16-l.OOOE+OO 2.560E-10 5.250E-11 REMAINDER 7.890E-15 4.766E-12 8.399E-11 1 . 670E-16-1.000E+OO l.410E-09 7.370E-09 EFFECTIVE 8.580E-15 5.137E-12 9.053E-ll 1.800E-16-l.OOOE+OO l.OlOE-09 2.560E-09 SKIN(FGR) 2.520E-14 5.565E-11 9.808E-10 1.950E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO La-140 GONADS 1.140E-13 6.027E-11 4.425E-10 2.240E-15-l.OOOE+OO 4.540E-10 l.340E-09 BREAST l.290E-13 5.758E-11 4.228E-10 2.140E-15-1.000E+OO l.450E-10 l.800E-10 LUNGS l.150E-13 5.596E-11 4.109E-10 2.080E-15-l.OOOE+OO 4.210E-09 4.0lOE-11 RED MARR l.140E-13 5 . 731E-11 4.208E-10 2.130E-15-1.000E+OO 2.140E-10 2.810E-10 BONE SUR l.690E-13 7.776E-ll 5.709E-10 2.890E-15-1.000E+OO 1.410E-10 9.770E-ll THYROID 1.lBOE-13 5.462E-11 4.0lOE-10 2.030E-15-1.000E+OO 6.870E-11 6.400E-12 REMAINDER l.llOE-13 5.569E-11 4.089E-10 2.070E-15-l.OOOE+OO 2.120E-09 6.260E-09 EFFECTIVE 1.170E-13 5.812E-11 4.267E-10 2.160E-15-1.000E+OO l.310E-09 2.280E-09 SKIN(FGR) l.660E-13 2.217E-10 l.628E-09 8.240E-15-l.OOOE+OO O.OOOE+OO O. OOOE+OO La-141 GONADS 2.330E-15 7.315E-13 9.675E-13 4.740E-17-1.000E+OO l.OlOE-11 3.770E-12 BREAST 2.640E-15 7.007E-13 9.267E-13 4.540E-17-l.OOOE+OO 9.840E-12 7.070E-13 LUNGS 2.340E-15 6.713E-13 8.879E-13 4.350E-17-l.OOOE+OO 6.460E-10 2 . 720E-13 RED MARR 2.310E-15 6.852E-13 9.063E-13 4.440E-17-l.OOOE+OO 2.930E-11 l.070E-12 BONE SUR 3.490E-15 9.923E-13 l.312E-12 6.430E-17-l.OOOE+OO l.200E-10 6.060E-13 THYROID 2.390E-15 6.590E-13 8.716E-13 4.270E-17-l.OOOE+OO 9.400E-12 5.290E-14 REMAINDER 2.260E-15 6.682E-13 8.838E-13 4.330E-17-1.000E+OO 2.280E-10 l.240E-09 EFFECTIVE 2.390E-15 7.007E-13 9.267E-13 4.540E-17-1.000E+OO l.570E-10 3.740E-10 SKIN(FGR) 6.580E-14 l.667E-10 2.204E-10 1.080E-14-l.OOOE+OO 0.000E+OO 0.000E+OO La-142 GONADS l.400E-13 1.978E-11 2.034E-11 2.540E-15-l.OOOE+OO l.660E-11 6.990E-11 BREAST l.570E-13 l . 885E-11 l.938E-ll 2.420E-15-l.OOOE+OO 1.130E-11 1.540E-ll LUNGS 1.420E-13 l.846E-11 1.898E-11 2.370E-15-1.000E+OO 3.0lOE-10 8.400E-12 RED MARR l.420E-13 l.900E-ll l.954E-11 2.440E-15-l.OOOE+OO 1.360E-11 l.930E-11 BONE SUR 1.950E-13 2.484E-11 2.554E-11 3.190E-15-l.OOOE+OO 1.llOE-11 7.400E-12 THYROID l.450E-13 1.768E-ll 1.818E-ll 2.270E-15-1.000E+OO 8.740E-12 l.160E-12 REMAINDER l.380E-13 1.853E-11 1.906E-ll 2.380E-15-1.000E+OO 8.070E-11 5.200E-10 EFFECTIVE 1.440E-13 l.916E-11 1.970E-11 2.460E-15-1.000E+OO 6.840E-11 l.790E-10 SKIN (FGR) 2.160E-13 9.lllE-11 9.368E-11 l.170E-14-l.OOOE+OO O.OOOE+OO O.OOOE+OO Ce-141 GONADS 3.380E-15 2.213E-12 4.332E-ll 7.710E-17-l.OOOE+OO 5.540E-11 l.080E-10 BREAST 3.930E-15 2.170E-12 4.247E-11 7.560E-17-l.OOOE+OO 4.460E-11 l.llOE-11

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 98of102 LUNGS 3.170E-15 1.951E-12 3.820E-11 6.BOOE-17-1.000E+OO 1.670E-08 1.430E-12 RED MARR 2.830E-15 1.860E-12 3.641E-11 6.480E-17-1.000E+OO 8.960E-11 3.390E-11 BONE SUR 9.410E-15 5.166E-12 1.0llE-10 1.BOOE-16-1.000E+OO 2.540E-10 2.300E-11 THYROID 3.350E-15 2.003E-12 3.922E-11 6.980E-17-1.000E+OO 2.550E-11 1.BOOE-13 REMAINDER 2.980E-15 1.894E-12 3.708E-11 6.600E-17-1.000E+OO l.260E-09 2.500E-09 EFFECTIVE 3.430E-15 2.llBE-12 4.146E-11 7.380E-17-1.000E+OO 2.420E-09 7.830E-10 SKIN(FGR) l.020E-14 3.788E-12 7.416E-11 1.320E-16-1.000E+OO 0.000E+OO O.OOOE+OO Ce-143 GONADS 1.280E-14 7.900E-12 4.958E-11 2.980E-16-1.000E+OO 7.530E-11 2.120E-10 BREAST 1.470E-14 7.688E-12 4.825E-11 2.900E-16-1.000E+OO 1.660E-ll 2.320E-11 LUNGS 1.230E-14 6.893E-12 4.325E-11 2.600E-16-1.000E+OO 3.880E-09 3.820E-12 RED MARR 1.170E-14 6.787E-12 4.259E-11 2.560E-16-1.000E+OO 2.960E-11 5.070E-11 BONE SUR 2.520E-14 1.323E-ll 8.302E-11 4.990E-16-1.000E+OO 1.640E-11 1.610E-11 THYROID 1.280E-14 7.211E-12 4.525E-11 2.720E-16-1.000E+OO 6.230E-12 4.350E-13 REMAINDER 1.170E-14 6.734E-12 4.226E-11 2.540E-16-1.000E+OO l.420E-09 3.890E-09 EFFECTIVE l.290E-14 7.396E-12 4.642E-11 2.790E-16-1.000E+OO 9.160E-10 1.230E-09 SKIN(FGR) 3.960E-14 1.058E-10 6.638E-10 3.990E-15-1.000E+OO 0.000E+OO O.OOOE+OO Ce-144 GONADS 2.725E-15 6.328E-13 1.319E-11 6.088E-17-1.000E+OO 2.390E-10 6.987E-11 BREAST 3.129E-15 6.274E-13 1.307E-11 5.922E-17-1.000E+OO 3.480E-10 1.223E-11 LUNGS 2.639E-15 5.228E-13 1.089E-11 5.362E-17-1.000E+OO 7.911E-07 6.551E-12 RED MARR 2.507E-15 4.755E-13 9.907E-12 5.247E-17-1.000E+OO 2.880E-09 8.923E-11 BONE SUR 5.441E-15 1.646E-12 3.429E-11 1.127E-16-l.OOOE+OO 4.720E-09 1.280E-10 THYROID 2.753E-15 5.529E-13 1.152E-11 5.418E-17-1.000E+OO 2.920E-10 5.154E-12 REMAINDER 2.534E-15 5.086E-13 l.060E-11 5.283E-17-1.000E+OO 1.910E-08 1.890E-08 EFFECTIVE 2.773E-15 5.909E-13 1.231E-11 5.766E-17-1.000E+OO l.OlOE-07 5.711E-09 SKIN(FGR) 8.574E-14 7.648E-13 1.594E-11 1.250E-14-l.OOOE+OO O.OOOE+OO O.OOOE+OO Pr-143 GONADS 2.130E-17 2.264E-14 4.032E-13 7.930E-19-1.000E+OO 4.370E-18 8.990E-18 BREAST 2.550E-17 2.330E-14 4.149E-13 8.160E-19-1.000E+OO 2.220E-18 1.090E-18 LUNGS 1.860E-17 1.642E-14 2.923E-13 5.750E-19-1.000E+OO 1.330E-08 1.910E-19 RED MARR 1.620E-17 1.493E-14 2.659E-13 5.230E-19-1.000E+OO 1.480E-11 1.030E-12 BONE SUR 5.930E-17 5.454E-14 9.711E-13 1.910E-18-1.000E+OO l.490E-ll 1.030E-12 THYROID 2.050E-17 1.802E-14 3.208E-13 6.310E-19-1.000E+OO 1.680E-18 2.660E-20 REMAINDER 1.760E-17 1.642E-14 2.923E-13 5.750E-19-1.000E+OO 1.970E-09 4.220E-09 EFFECTIVE 2.lOOE-17 2.002E-14 3.564E-13 7.0lOE-19-1.000E+OO 2.190E-09 1.270E-09 SKIN(FGR) 1.760E-14 5.711E-ll 1.017E-09 2.000E-15-1.000E+OO 0.000E+OO O.OOOE+OO Nd-147 GONADS 6.130E-15 4.218E-12 7.235E-11 1.480E-16-1.000E+OO 8.410E-11 1.790E-10 BREAST 7.120E-15 4.132E-12 7.088E-11 1.450E-16-1.000E+OO 3.450E-ll 1.870E-11 LUNGS 5.820E-15 3.648E-12 6.257E-11 1.280E-16-1.000E+OO 1.060E-08 2.440E-12 RED MARR 5.400E-15 3.505E-12 6.013E-11 1.230E-16-1.000E+OO 9.190E-ll 5.050E-11 BONE SUR 1.320E-14 8.265E-12 1.418E-10 2.900E-16-1.000E+OO 3.260E-10 2.220E-11 THYROID 6.120E-15 3.876E-12 6.648E-11 1.360E-16-1.000E+OO 1.820E-11 2.640E-13 REMAINDER 5.530E-15 3.562E-12 6.lllE-11 1.250E-16-1.000E+OO 1.760E-09 3.760E-09 EFFECTIVE 6.190E-15 3.961E-12 6.795E-11 1.390E-16-1.000E+OO 1.850E-09 l.lBOE-09 SKIN(FGR) 1.950E-14 3.135E-ll 5.377E-10 1.lOOE-15-1.000E+OO 0.000E+OO O.OOOE+OO Np-239 GONADS 7.530E-15 4.691E-12 4.380E-11 1.710E-16-1.000E+OO 7.450E-11 1.620E-10 BREAST 8.730E-15 4.636E-12 4.329E-11 1.690E-16-1.000E+OO 1.630E-11 1.720E-11 LUNGS 7.lBOE-15 4.115E-12 3.842E-ll 1.500E-16-1.000E+OO 2.360E-09 2.400E-12 RED MARR 6.500E-15 4.005E-12 3.740E-11 1.460E-16-1.000E+OO 2.0BOE-10 4.660E-11 BONE SUR 2.000E-14 1.00lE-11 9.349E-11 3.650E-16-1.000E+OO 2.030E-09 3.590E-11 THYROID 7.520E-15 4.197E-12 3.919E-11 1.530E-16-1.000E+OO 7.620E-12 2.070E-13 REMAINDER 6.760E-15 4.005E-12 3.740E-11 1.460E-16-l.OOOE+OO 9.590E-10 2.770E-09 EFFECTIVE 7.690E-15 4.471E-12 4.175E-11 1.630E-16-1.000E+OO 6.780E-10 8.820E-10 SKIN(FGR) 1.600E-14 7.215E-12 6.737E-ll 2.630E-16-1.000E+OO 0.000E+OO O.OOOE+OO Pu-241 GONADS 7.190E-20 6.653E-17 1.396E-15 2.310E-21-l.OOOE+OO 2.760E-07 5.660E-11 BREAST 8.670E-20 7.229E-17 1.517E-15 2.510E-21-1.000E+OO 2.140E-11 2.790E-15 LUNGS 6.480E-20 4.090E-17 8.584E-16 1.420E-21-l.OOOE+OO 3.lBOE-06 4.480E-15 RED MARR 5.630E-20 4.003E-17 8.403E-16 1.390E-21-1.000E+OO l.430E-06 2.780E-10 BONE SUR 2.190E-19 1.385E-16 2.908E-15 4.810E-21-1.000E+OO 1.780E-05 3.480E-09 THYROID 6.980E-20 4.522E-17 9.491E-16 1.570E-21-1.000E+OO 9.150E-12 1.0lOE-15 REMAINDER 6.090E-20 4.291E-17 9.007E-16 1.490E-21-l.OOOE+OO 6.020E-07 1.850E-10 EFFECTIVE 7.250E-20 5.558E-17 1.167E-15 1.930E-21-l.OOOE+OO 1.340E-06 2.070E-10 SKIN(FGR) 1.170E-19 2.033E-16 4.268E-15 7.060E-21-l.OOOE+OO 0.000E+OO O.OOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 99 of 102 Cm-242 GONADS 7.830E-18 4.893E-14 l.013E-12 l.700E-18-l.OOOE+OO S.?OOE-07 5.200E-09 BREAST 1. 480E-l 7 6.159E-14 l.275E-12 2.140E-18-l.OOOE+OO 9.440E-10 8.9SOE-12 LUNGS l.130E-18 3.022E-15 6.257E-14 l.OSOE-19-1.000E+OO l.SSOE-05 8.840E-12 RED MARR l.890E-18 6.562E-15 l.359E-13 2.280E-19-l.OOOE+OO 3.900E-06 3.S?OE-08 BONE SUR l.060E-17 4.231E-14 8.759E-13 l.470E-18-l.OOOE+OO 4.870E-OS 4.460E-07 THYROID 4. 910E-18 l.261E-14 2.610E-13 4.380E-19-l.OOOE+OO 9.410E-10 8.820E-12 REMAINDER 2.270E-18 l.079E-14 2.23SE-13 3.7SOE-19-l.OOOE+OO 2.4SOE-06 4.020E-08 EFFECTIVE 5.690E-18 2.751E-14 S.697E-13 9.560E-19-l.OOOE+OO 4.670E-06 3.lOOE-08 SKIN(FGR) 4.290E-17 2.700E-13 5.589E-12 9.380E-18-l.OOOE+OO 0.000E+OO O.OOOE+OO

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 100of102 1st Pass Attributes - General Overview Yes No Attribute The purpose/scope is clear and well defined. You should be able to IZI D understand the purpose without resorting to consultation with the preparer. (4.3.2) IZI D The reason or need for the product is clearly discussed. (4.3.2) You possess the proper knowledge and skill sets needed for the review. If IZI D additional expertise is needed, those reviews have been scheduled to ensure that appropriate knowledgeable "experts" are utilized for reviews. The Methodology is appropriate for the purpose and scope of the document, IZI D and is clearly documented.

CALCULATION NO. PM-1057 REV. No. 5 PAGE NO. 101of102 2nd Pass Attributes - Technical Review Yes No Attribute [8'.J D Input Parameters are clearly listed, defined with source documentation. [8'.J D The Inputs are valid and are referenced to a quality documented reference. [8'.J D Assumptions are reasonable and well documented. The Methodology is appropriate and Equations Used have been verified- [8'.J D Ensure proper methodology & units If an Alternate Calculation Tools or Methods was used as the review method, [8'.J D that analysis has been attached to the final document The Numerical calculations and computations have been verified correct- [8'.J D validate the numbers The acceptance criteria is consistent with the Design Basis, Design Standards [8'.J D and applicable codes. Does the analysis consider new potential failure modes and disposition them as [8'.J D appropriate? If none are indicated, is this appropriate? Does the product consider the most limiting or bounding design basis [8'.J D conditions? Are the results consistent with actual plant response and do they appear [8'.J D reasonable? [8'.J D Does the conclusion clearly support the purpose as described?

CAL..CUl.ATION NO. PM-1057 REV.No. 5 PAGE NO. 102of102 3rct Pass Attributes - Administrative Yes No Attribute C8J D Check references- are they the correct rev C8J D Check procedures used- are they the correct rev [gl D Assumptions are reasonable and well documented [gl D Check for Spelling Errors, Punctuation and Grammar [gl D Check for simplicity and readability [gl D Are the proper forms included in the document and filled out correctly [gl D Check Page and Attachment Numbering [gl D Right Boxes Checked on Forms l8l D Proper process has been used, Major Rev, Minor Rev, EC/ECR etc.

      ~      D      Appropriate boxes are signed off or marked NIA
                                                             ~

Reviewer: _ _M_a_r_k_D_ru

                       ....c....k_e_..r__

Print I Signature+ t0~~-h __________... 7... 11,_4....,/2-.0-.1,_4........ Date}}

ML14247A524

Text

Subject:

SUMMARY

2.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

SUMMARY

2.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

Response

Response

Response

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

Title:

1.0 PURPOSE

2.0 METHODOLOGY

4.0 ASSUMPTIONS

7.0 CALCULATIONS

SUMMARY

Conclusions:

9.0 REFERENCES

Subject:

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