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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20137D0511997-03-20020 March 1997 Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for Relief ML20134K2621997-02-10010 February 1997 Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01 ML20129H3901996-10-30030 October 1996 Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal Flood ML20129F4031996-09-27027 September 1996 Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for Relief ML20059C3751993-12-29029 December 1993 Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 ML20058G2781993-11-29029 November 1993 Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) ML20056F5301993-08-11011 August 1993 Safety Evaluation Re Licensee Response to Reg Guide 1.97, BWR Neutron Flux Monitoring. Criteria of NEDO-31558, Acceptable for Current BWR Operating License & Const Permit Holders ML20127P5431993-01-25025 January 1993 Safety Evaluation Supporting Amend 145 to License DPR-35 ML20126F8121992-12-23023 December 1992 Safety Evaluation Accepting Facility Design W/Respect to RG 1.97 ML20244C2901989-06-0606 June 1989 Draft Safety Evaluation of Util Compliance W/Atws Rule (10CFR50.62) Re Alternate Rod Injection & Recirculation Pump Trip Sys.Alternate Rod Injection Sys Not in Compliance W/Atws Rule Re Diversity ML20235V7341989-03-0303 March 1989 Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station ML20154P6611988-09-28028 September 1988 SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4) ML20151D0551988-07-18018 July 1988 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20151E2041988-07-15015 July 1988 Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test ML20154J9101988-05-17017 May 1988 Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities ML20155F8871988-03-24024 March 1988 Safety Evaluation Concluding That Internal Smoke Seals for Conduits Passing Through Fire Barriers from One Fire Area to Another Consistent W/Branch Technical Position 9.5-1 & Acceptable,Per Util 880203 Submittal ML20236Y3991987-11-10010 November 1987 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input Encl ML20236V3081987-10-28028 October 1987 Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 Encl ML20235M1611987-09-30030 September 1987 Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing ML20236Y3591987-07-22022 July 1987 Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also Encl ML20206G8141987-03-26026 March 1987 Safety Evaluation Re Util Requests for Relief from Inservice Insp Requirements for Surface & Volumetric Exam of RHR Sys HX Nozzles & Exam of 100% Required Vol for nozzle-to-vessel Welds.Requests Granted W/Listed Conditions ML20215H9581987-03-17017 March 1987 Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input Encl ML20212L8941987-01-15015 January 1987 Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses ML20236Y3501986-09-0303 September 1986 Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl ML20212N8401986-08-22022 August 1986 SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation ML20155F8931986-08-20020 August 1986 Safety Evaluation Accepting Util 831116 Request for Four Exemptions from 10CFR50,App R,Section Iii.G.Level of Fire Safety in Listed Fire Zones Equivalent to Safety Achieved by Compliance W/Requirements ML20206L9511986-08-12012 August 1986 Safety Evaluation on Util Response to Generic Ltr 83-28, Items 3.1.1,3.1.2,.3.2.1,3.2.2 & 4.5.1 Re Maint & Test Procedures for safety-related Equipment & on-line Functional Testing of Reactor Trip Sys.Responses Acceptable ML20205C0621986-07-31031 July 1986 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl ML20236Y3361986-07-10010 July 1986 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability ML20199L2541986-07-0101 July 1986 Safety Evaluation Supporting Amend 96 to License DPR-35 ML20206D1741986-06-0606 June 1986 Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall Design ML20203N3801986-04-30030 April 1986 Safety Evaluation Supporting Util 840625,1204,06,850521 & 1011 Responses to Generic Ltr 86-04 Concerning Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii).Facility Does Not Require Recombiner Capability ML20236Y3711986-04-0101 April 1986 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components,Respectively. SALP Input Also Encl ML20137V7621986-02-12012 February 1986 SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping ML20135E5211985-09-11011 September 1985 Safety Evaluation Supporting post-trip Review Program & Procedures ML20134H3571985-08-13013 August 1985 Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining Welds ML20140G1431985-07-0505 July 1985 Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs ML20129C6901985-05-16016 May 1985 Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1 ML20206K6161985-03-13013 March 1985 SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl 1999-09-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EXEMPTION FROM APPENDIX B. TABLE 1. FOR DERIVED AIR ,
CONCENTRATION VALUES FOR KRYPTON-89 AND XENON-137 PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated September 13, 1993, Boston Edison Company (BECo) requested an exemption from Title 10 of the Code of Federal Regulations (10 CFR) Section 20.1902(d), " Posting of airborne radioactivity areas," which requires that the licensee shall post each airborne radioactivity area with a conspicuous sign or signs bearing the radiation symbol and the word as, " CAUTION, AIRBORNE RADI0 ACTIVITY AREA" OR " DANGER, AIRBORNE RADI0 ACTIVITY AREA."
Section 20.1003 defines " airborne radioactivity areas" as "a room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations --
(1) In excess of the derived air concentrations (DACs) specified in appendix B, to f5 20.1001 - 20.2401, or ....."
Some airborne radionuclides, in particular the noble gases (such as argon, krypton and xenon) are not metabolized to an appreciable extent by the body. .
The methodology for calculating the DAC for these radionuclides is based on consideration of the external dose due to submersion in air containing the <
radionuclide. The DAC for a particular radionuclide is the maximum.
concentration of that radionuclide in air that, for a 2,000-hour exposure, will result in a dose that is equal to or less than each of the applicable :
limits in 10 CFR 20.1201 for occupational dose. These applicable limits are- l 5-rem effective dose equivalent (H ),15-rem eye dose equivalent, 50-rem dose equivalent to other organs or tiss,ues, and shallow dose equivalent of 50-rem to the skin.
The radionuclides Kr-89 and Xe-137 are not listed individually in . Appendix B to 10 CFR 20.1001 - 20.2402. Both of these noble gas radionuclides decay by j beta emission and have half-lives (3.16 minutes for_ Kr-89 and 3.83 minutes for !
Xe-137) of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; therefore, the DAC, calculated for submersion, l for both Kr-89 and Xe-137 is 10'7 pCi/ml (in accordance with the' provision at !
the end of Appendix B to 10 CFR 20.1001 - 20.2402 for "any single radionuclide i not listed above with decay mode other than alpha emission or spontaneous l fission.") j 9401050139 931229 4 PDR ADOCK 05000293 P PDR \
l Section 20.2301 provides that the Commission may, upon application by a licensee or upon its own initiative, grant an exemption from the requirements of the regulations in 10 CFR Part 20 if it determines the exemption is authorized by law and would not result in undue hazard to life or property.
By their submittal dated September 13, 1993, the BECo requested an exemption, pursuant to 10 CFR 20.2301, to use derived air concentrations (DACs) of 10' yCi/ml for Kr-89 and 10-5 pCi/ml for Xe-137 instead of using the generic (default) value of 10~7 pCi/ml for these radionuclides, which is provided in Appendix B to 10 CFR 20.1001 - 20.2402. In this request proposes to use the DACs of 10 pCi/ml for Kr-89 and 10'gdpCi/ml exemption, BECoat for Xe-137 the Pilgrim Nuclear Power Station when determining whether an area is, and requires posting as, an airborne radioactivity area.
2.0 DISCUSSION AND EVALUATION Criteria and background information used for this evaluation include the following:
- 1. 10 CFR Part 20, Standards for Protection Against Radiation, 5%
20.1003, 20.1902(d), and Appendix B to ES 20.1001 - 20.2402.
- 2. Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and !
Air Concentration and Dose Conversion Factors for Inhalation, Submersion, I and Ingestion, 1988.
- 3. David C. Kocher, Radioactive Decay Data Tables - A Handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessments, U.S. ;
Department of Energy Report DOE / TIC-Il026, 1981.
l
- 4. Letter from Keith Eckerman, Oak Ridge National Laboratory, to John Buchanan, U.S. NRC, November 1, 1993.
In its September 13, 1993 letter, BEco states that the requested exemption is i needed because Kr-89 and Xe-137 are a significant fraction of the noble gas '
radioactivity in a boiling water reactor and the DAC of 10' pCi/ml provided in Appendix B to 10 CFR 20.1001 - 20.2402 is too small for these particular radionuclides. BECo notes that the " maximum permissible concentration (MPC)"
for Kr-89 and Xe-137 given in Appendix B to 10 CFR 20.1 - 20.3 (which is is 10 Ci/ml rather applicable than at theBEco 10-7 pCi/ml. Pilgrim plant states until that the January use of the1,1994) 10' pCi/ml value for the Kr-89 and Xe-137 DACs would cause over posting of airborne radioactivity !
areas, which erodes the significance of the posting and consumes resources. j BECo also states that the use of the 10'7 pCi/ml value for the Kr-89 and -
Xe-137 DACs would result in undue hardship and would overburden operational staff by posting areas that are normally not required to be posted while providing little to no benefit.
l l
BEco further states that: (1) the exemption request does not decrease any safety measures employed at the plant and does not invalidate previous commitments or requirements to comply with regulation, (2) the exemption request relates to occupational radiation exposure, and (3) the exemption ,
request is authorized by law, will not present undue risk to public health and safety, and is consistent with common defense and security.
To determine the radiation dose equivalent values corresponding to the BEco-requested values of the DACs for Kr-89 and Xe-137, the NRC staff used dose conversion factors calculated by Dr. Keith Eckerman, Group Leader, Radiation Dosimetry Research Group, Oak Ridge National Laboratory (ORNL), which were provided in his letter dated November 1. 'Q93. In performing these calculations, Dr. Eckerman used nuclea m . data for Kr-89 and Xe-137 taken from the report by D. C. Kocher. Dr. __ a and his group at ORNL calculated the DACs and other quantities contained in Appendix B to 10 CFR Parts 20.1001 - 20.2402 and in Federal Guidance Report No.11. Dr. Eckerman '
provided the dose equivalent rate conversion factors for Kr-89 and Xe-137 in the SI units of [(sieverts/second) per (bequerel/ cubic meter)]. These factors were converted to factors with conventional units of [(rem / hour) per (microcurie / cubic centimeter)] by multiplying by a factor of 1.332 x 10".
These dose equivalent rate conversion factors are listed in Table 1. In this table, the H is the dose "effe,ctive dose equivalent" equivalent to asthe remaining defined in 10 organs or tissues and Hand Federal , is CFR 20.1003 Guidance Report No. 11.
The dose equivalent rate conversion factors from Table I were use to calculate thedoseequivalent,inunitsofrem,tpatcorrespondstoanexpopureof2,000 3 3 i
hours at the BEco-requested DACs of 10' pCi/cm for Kr-89 and 10' pCi/cm for Xe-137. The results of these calculations, together with the corresponding Part 20 dose limits, are shown in Table 2.
All of the calculated doses in Table 2 are below the corresponding Part 20 limits and, therefore, are acceptable.
l l
l l
I Y
}:?
i Table 1. Dose Conversion Factors for Krypton-89 and Xenon-137 Krvoton-89 (Sv/s) Der (Ba/m3 ) 3 (rem /h) oer (uCi/cm ) i Gonad 9.19 x 10"' l.224 x 10*' 1 Breast 1.03 x 103 1.372 x 10 3 '
Lung 9. 29 x 10 1.237 x 10 3 Red Harrow 9.22 x 10 1.228 x 10 3 Bone Surface 1.34 x 103 1.785 x 10 3 :
Thyroid 9. 51 x 10 1.267 x 10 3 l H' 8.99 x 10 l.198 x 1033
- H 9.45 x 10' 1.259 x 10 Skin 1.99 x 103 2.651 x 10 3 <
Eye 1.31 x 103 1.745 x 103 '
Xenon-137 (Sv/s) per (Bo/m 3) 3 (rem /h) Der (uCi/cm )
Gonad 8.75 x 10 l.166 x 10'2 Breast 1.02 x 10 1.359 x 10 i Lung 8.94 x 103 1.191 x 10 2 ,
Red Harrow 8.66 x 105 1.154 x 10 2 Bone Surface 1.54 x 10' 2.051 x 10 2 ;
Thyroid 9.16 x 105 1.220 x 10 2 H' 8.56 x 105 1.140 x 10 2 H 9.20 x 105 1.225 x 10 2 Skin 1.35 x 103 1.798 x 10 32 -;
Eye 5.04 x 10 6.71 x 10 _j l
i i
a:
Table 2. Dose Equivalent Values (ren hours at the BEco-Requested DACs (10 ) ACi/cmCorreggondingtoanExposure'pf2,000 for Krypton-89 and.10' #Ci/cm3 -
for Xenon-137) Together with the Corresponding Part 20 Dose Limits (rem)
Krypton-89 Xenon-137 - Part 20 Limit Gonad 2.45 2.33 50.
Breast 2.74 2.72 50.
Lung 2.47 2'38
. 50.
Red Harrow 2.46 2.31 50.
3one Surface 3.57 4.10 50.
Thyroid 2.53 2.44 50. _
2.39 H, 2.28 50.
H 2.52 2.45 5.
Skin 5.30 36. 50.
Eye 3.49 13.4 15, i 1
'I d
-1 5
, 9 7 .wr.. e a m e--- ,- J
} .
I BEco, in its exemption request, included skin dose and whole-body dose values for Kr-89 and Xe-139 calculated using dose conversion factors from Regulatory '
Guide 1.109. These values (in units of rea) are as follows:
Krvoton-89 Xenon-137 "Whole Body" 3.8 3.2 Skin 6.1 31.
These doses appear to be in reasonable agreement with the corresponding doses calculated by Dr. Eckerman, considering that the "whole body dose" used in RG '
l.109 is not the same dose quantity as the " effective dose equivalent" as defined in 10 CFR 20.1003 and that computational models used by Dr. Eckerman to obtain the dose conversion factors reported above are not the models that were used to obtain the dose conversion factors for RG 1.109. BEco did not provide calculated doses for organs or tissues other than the skin. BECo did state that the eye dose is even less restrictive for these two radionuclides than the skin dose and the whole body dose; however, BECo provided no basis for that statement, and the validity of the statement appeared to be questionable for Xe-137 considering the relative magnitudes of the BECo values for the Xe-137 "whole body" and skin doses and the high energy (4.3 MeV maximum, 1.77 MeV average) of the beta radiation emitted in the decay of Xenon-137. The results of the dose calculations by Dr. Eckerman show that the eye dose is limiting in the case of Xe-137; nevertheless, as shown in Table 2, theeyedosegorrespondingtoa2,000-hourexposureattheBECo-requestedDAC of 10-5 yCi/cm is below the limiting dose-equivalent value of 15 rem.
3.0 SAFETY
SUMMARY
The submersion doses corresponding to a 2,000-hour exposure at a DAC of ,
10 for Kr-89 or at a DAC of 10'5 for Xe-137 are below the limiting dose values used for determining the radionuclide-specific DAC values in Appendix B to 10 CFR Part 20.1001 - 20.2402 (and in Federal Guidance Report No.11).
Therefore, these DAC values are ac,ceptable alternatives for use in place of the generic (default) value of 10' yCi/ml for these radionuclides (that is specified in of Appendix B to 10 CFR 20.1001 - 20.2402) when determining whether an area is, and requires postii.g as, an airborne radioactivity area.
4.0 CQNCLUSION The staff has concluded, based on the considerations discussed above, that:
(1) there is a reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) the issuance of this exemption is authorized by law and will not result in undue hazard to life or property.
Principal Contributor: John D. Buchanan Dated: December 29, 1993 m