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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20128G1661996-10-0303 October 1996 Summarizes 960924 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Preliminary Responses to Staff RAI Concerning Request to Change EALs for TMI-1.List of Participants & Copy of Preliminary Response to RAI Encl 1999-09-29
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months 1999-09-29
[Table view] |
Text
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APPENDIX II
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OCT 3 01985 MEMORANDUM FOR: Richard A. Weller, Leader Safety and Environmental Review Section Three Mile Island Program Office Office of Nuclear Reactor Regulation l T11RU: Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Office of tbclear Material Safety and Safeguards FROM: Charles R. Marotta, Senior Criticality and Shielding Engineer Transportation Certification Branch 4
Division of Fuel Cycle and Material Safety j Office of Nuclear Material Safety and Safeguards SUSJECT: CRITICALITY SAFETY EVALUATION OF A LOADED CANISTER I
DROPPING ITS CONTENTS ONTO A S!!!!LAR LOADF.D CANISTER
- IN A MAXIMUM VOLUME STORAGE UNIT
- 1. Introduction and Summary As agreed in our conference phone call with Phil Grant and John Thomas on Friday, October 18, 1985, I have analyzed the criticality aspects of the accidental dropping of the contents of a loaded canister
, onto a similar loaded stored canister. The analysis indicates that .
i for the loading limitations per canister, maxinum storage volume per canister available and 4350 ppm boron in water, such an accident '
coses no criticality hazard and under very conservative assumptions (discussed below), the keff shutdown range is between 32% (max) to 13%(min). A total of six KEND Monte Carlo (123 gps) cases were ,
analyzed and form the basis of the above conclusion. Results are given in Table 2. The computer input-output for these cases are on file in Transportation certification Branch, NMSS.
- 2. Problem Definition The concern of the subject accident scenario is the criticality state of a stored loaded canister when surrounded by the dropped i contents of a similar canister. The stored canister resides in a
, parallelipiped borated (4350 ppm) water region of dinensions 18 inches 1
by 18 inches by 14 feet - a volume of 892.000 cc.
0511110296 851105 PDR ADOCK 05000320 P PDR
_.________________________-_--.___-_-____-----_.-._----_s- _ _ . - . - -
Richard A. Weller 3. Problem Solution: Assumptions and Method _s The approach in solving the above problem was to assume all canister contents to have a maximum payload of dry 900 kg U(3)0 7 pellets -
this nominal value is 4-1/2% higher than the greatest ayload (C61 kg - total) for a knock-out canister.
To understand the detailed approach taken (described below) in solving-the problem, the following criticality observations are reviewed. They were established in previous studies.
I a. The as-built pellet is the form and geometry of the fuel to affect the optimum Vol fuel to Vol water ratio (V /Vp )gboth for unborated water and borated water,
- b. Unborated water; maximum reactivity exists for fuel as pellet for Vp/Vy = 30/70, water is more important than fuel.
- c. Borated water; maximum reactivity for fuel pellet shif ts to Vr/Vu= 60/40 over the boration of 2500 ppm to 4500 ppm boron.
, Fuel is more important than the borated water. But the ratio goes from 58/42 to 62/38 over the boration range showing the small dependence on ppm; we have thus assumed an average value of 60/40,
- d. Since the above ratios (30/70 and 60/40) represent optimum values and further increase of fuel into the system would decrease reactivity, small uranium slurry volume and/or uranium fines in the moderator region give a crude-first approximation of reactivity reduction. This is not exactly correct since 1
introducing fuel in the moderator region shifts the optimum value. This has been neglected and is considered a second order effect on the assumption the system spectrum remains constant and the shift is small.
i With the above as background, Table 1 can be constructed showing how mcny canister-full contents can be accommodated in the water storage paralleliped of 892.000 cc total volume. The canister contents are assumed to be 900 kg 00 at density 10 grams /cc. No canister structural material or cani,ter s poison material is considered present in the storage volume.
Richard A. Weller TABLE 1 Number of Canister Contents in Storage Volume U0, Volume Volume H O vp/Vp 2
j 90,000 cc U0 112 802,000 cc H 2
2 180,000 cc U0,, "253
'712,000 cc H O 2
270,000 cc U0 9 3
622,000 cc H O .434ch=.428) 70 2
360,000 cc UO 532,000ccH6 2
5 450,000 cc 00, 442,000 cc H D '
2 6
540,000 cc U0
.,52,000ccHf 1.538cS(-1.500) 40 2
This Table 1 shows that it will take about six canister contents to approach the optimum 60/40 ratio for borated systems and about only three canister contents to approach the optimum 30/70 for unborated systems.
The criticality analysis of the cases specified in Table 2 were modeled as cells as a discrete pellet region surrounded by its associated moderator close-fitting into the 18" x 18" cross-sectional area. This gave a UO, mass loading of 2764 kg (vs 2700 = 3 x 900) for the 30/70 ratio and 5678 kg U0 7 (vs 5400 6 x 900) for the 60/40 ratio due to the arithmeticaT discrepencies of fitting prescribed volume fractions into a fixed region. The 30/70 case is very slightly non-conservative, whereas, the 60/40 is quite conservative since more fuel is a more reactive situation here.
i Richard A. Weller 4. Discussion of Results and Conservatisms Comparison of Cases 1 and 4 show that keff will decrease by 0.14 for the unborated case by increasing the fuel by a factor of 2 in line with neximum reactivity for the 30/70 mixture. For the horated cases, a comparison of Cases 2 and 5 and Cases 3 and 6, an increase in keff of 0.14 and 0.19 results respectively by increasing the fuel by a factor of 2 in line with maximum reactivity for the 60/40 mixture.
Case 6 represents approximately six canister-fulls filling the storage volume at the most reactive mixture 60/40 for 4350 ppm boron in the storage water. If one considers the canister poisons and structural materials as well as the core (canister contents) material to contain control-rod poisons, fixed poisons, core structure material, fission products and lower average core enrichment, all the tabulated keffs of Table 2 can be decreased by at least 0.10.
Since only 2 canister contents represent the accident conditions, subcriticality is assured by a large margin.
In addition, Case 7 represents a 14 foot deep infinite slab of Case 6 contents with a resulting keff of 1.085.
Case 3 of Table 2 rerun as an infinite systen in the X-Y-Z direction, gave a koo of 0.8021.
Case 7 of Table 2 rerun as an infinite systen in the X-Y-Z direction, gave a koo of 1.095.
r r
-. - . , . , , ~ - ,
l Richard A.- Weller l l
TABLE 2 KEN 0 K_,2s for an 18 inch x 18 inch x 14 feet Para 11elepiped Canister a 5torage Volume Containing Most Reactive U(3)0,,-li.,0 tiixture (for baron concentrations of zero, 3000 ppm and 4350' ppm in water)
. KEN 0 PPf1 Vfuel Contents of Storagg Volume5 (c) 3 l No.
Case Boron Vwater keff(a)(b) (18"xl8"xl68"=31.5ft=8.92x10cm) j i 2764 kg U(3)02; 618 kg H 2O
.1 0 30/70 1.239 zero gas boron i2 3000 30/70 0.775 1893 gas boron 3 4350 30/70 0.677 2746 gms boron i 5678 kg U(3)0 ; 362 kg H gG 2
4 0 l 60/40 1.099 zero gas boron I
5 3000 j60/40 0.918 1113 gms boron 6 4350 , 60/40 0.871 1614 gas boron
~
K-INF(X-Y) 5678 kg O[3T6 ; 362 kg H 0 2 z i7 4350 ,
60/40 1.085 1614 gms boron i
(a)to within 10.003 for 1 std. dev.
(b)all cases (except No. 7) reflected by 1 foot all around appropriate borated-water reflector.
(c) storage volume does not contain any structural (internal and external) canister materials or canister poisons.
(d) reflected top and bottom, 2 direction by 1 foot of borated water.
i i v 1
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s.
Charles R. Marotta l
l l
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Dr. Thomas Mur ley Millis Simby. Site Manager Regional Administrator. Region ! U.S. Department of Energy U.S. huclear Regulatory Comission P.O. Boa 88
, 631 Park Avenue Middleto n. PA 17D57 0311 King of Prussia. PA 19406 Da vid J. Mc Go f f John F. Wolfe. Isa.. Chairman, Division of Three Mile Island Programs Administrative Judge #l*23 p 3409 $nepherd $t. U.S. Department of Energy Chevy Chase. MD. 20015 hashington. D.C. 20545
- Cr. Oscar H. Paris William Lochstet Administrative Judge 104 Cavey Laboratory Atomic Safety and Licensing Pennsylvania State University Board Panel University Park. PA 16802 -
U.S. muclear Regulatory Comission Washington, D.C. 2C555 Pandy Myers. Editorial she Patriot Dr. Frederick H. Shon 312 Market St.
Administrative Judge Marrisburg PA 17105 Atomic Safety and Licensing Board Panel Rcbert 9. Borsum U.S. Nuclear Regdlatory Comission Babcock & Wi1 Con Washington D.C. 20555 huclear Po er Generation Division Suite 220 -
Karin W. Carter 7910 Woodmount Ave.
Assistant Attorney General Bethesda. MD. 20814 505 taccutive house P.O. Som 2357 Michael Churchat11. Esq.
3 harrisburg PA 17120 PILCOP '
Dr. Judith M. Johnsrud 1315 hainut St.. Suite 1632 Philadelphia, PA 19107 invironmental Coalition on i
hvClear Power Linda W. Little 433 Orlando Ave. 5000 Hermitage 04 State College. PA 16801 Raleigh.hC 27612 George F. Tro= bridge. Esq. Marvin I. Lewis Sha. Pittman. Potts and 6504 Bradford Terrace Trowbridge Philadelphia, PA 1914g
- , 1800 M. St.. W.
Washington. D.C. 20036 Jane Lee
AtDaic Safety and Licensing Board Panel Etters.PA 17319 U.S. huclear Regulatory Comission J
,,."_ bashington, D.C. 20555 J.B. Liberman. Esquire Atomic Safety and Licensing Appeal Panel Berlack.Israels. Liberman 26 droa hay U.S. huclear Regulatory Comission Washington, D.C. 20555 heu York. NY 10004 secretary Welter W. Cohen. Consumer Advocate Department of Justice U.S. huclear segulatory Comission Stra= berry Square 14th Floor ATTh: Chief. Docketing & Service Branch Marrisburg. PA 17127 Washington. D.C. 20555 Mr. Larry Hochendoner Ed=ard O. $=artz Dauphin County Comissioner Board of Superviscr$
P.O. Box 1295 Londonderry Township Marrisburg.*PA 17108-1295 RFD #1 Geyers Church Ad.
Middletown. PA 17057 John E. Minni:h. Chairperson.
Campnin County Board of Comissioners , Robert L. Knupp. Esquire Dauphin County Courthouse Assistant Solicitor Knupp and Andrews Front and Market Streets P.O. Boa P Harrisburg, PA 17101 407 N. Front $t.
Dauphin County Office of Emergency Harrisburg. PA 17108 Prepa rednes s Court House. Room 7 John Levin. Esovire -
Front & Market Streets Pennsylvania Pubitt Utilities Coaum.
. Harrisburg. PA 17101 P.O. Som 3265
- m Harrisburg. PA 17120 U.S. [nvironmental Protection Agency Region III Office ATTw
- [IS Coordinator Curtis Building (Sixth Floor)
, 6th & Walevt 5treetl -
Philadelphia, PA 19106 Mr. Edwin tintner' taecutive Vice President i N Thomas M. Gerusky. Director General Public Utilities nuclear Corp. '
i O Bureau of Radiation Protection 100 Interpace Parkway
- t_ Department of Environmental arsources Parsippany NJ 07054 lM P.O. Box 2063 i Q$ Marrisburg. PA 17120 l h. Den Kennedy se Crable
- - Office of Envirorumental Planning tancastee k = tra e et f laviroenneatal kesources f, s narrisourg, PA 17120
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