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Category:ARCHIVE RECORDS
MONTHYEARML20154H9871998-08-28028 August 1998 Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release ML20154P8941998-05-13013 May 1998 Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas ML20217E1661998-03-18018 March 1998 Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers ML20133F6511997-01-14014 January 1997 Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel ML20134M2121996-11-22022 November 1996 Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants ML20148T7361996-11-0808 November 1996 Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals ML20148T7511996-11-0606 November 1996 Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20128Q3321996-10-18018 October 1996 Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants ML20129E9941996-10-10010 October 1996 Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity ML20148T6971996-09-11011 September 1996 Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs ML20148T6801996-09-0606 September 1996 Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0321993-12-0808 December 1993 Rev 0 to Bwst ML20148F1331993-09-30030 September 1993 Rev 0 to Make-Up Tank ML20148F1601993-09-27027 September 1993 Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways ML20058P1681993-09-27027 September 1993 Package Consisting of Attachment to Employee Concerns Programs ML20148F0541993-09-17017 September 1993 Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A ML20057B9641993-09-10010 September 1993 AX114 & AX115 Ci Loading ML20057C0201993-09-0101 September 1993 Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1451993-09-0101 September 1993 Rev 0 to Nuc Serv Closed Cooling Water Surge Tank ML20057C0191993-08-31031 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20148F1071993-08-31031 August 1993 Rev 0 to Intermediate Colsed Cooling Surge Tank ML20148F1221993-08-31031 August 1993 Rev 0 to Intermediate Closed Cooling Chem Mix Tank ML20148F1521993-08-31031 August 1993 Rev 0 to Nuc Svc Cool Chem Mix Tank ML20057C0211993-08-30030 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20057C0161993-08-26026 August 1993 Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend ML20126M2391992-07-13013 July 1992 Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector Program ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary IA-86-608, Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island1987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island ML20213A0411987-01-29029 January 1987 Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island IA-86-293, Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response1986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20215L2161986-10-0909 October 1986 Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response ML20154M5021985-05-23023 May 1985 Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20126B8311984-12-11011 December 1984 Supporting Documentation Re once-through Steam Generators ML20135H3531984-06-19019 June 1984 Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2 ML20024B4941983-07-0606 July 1983 Slide Presentation Entitled Control Room Indications. ML20078B6461983-04-0505 April 1983 Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc ML20083N6661982-10-19019 October 1982 TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc Overview ML20082R1511982-09-15015 September 1982 Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification ML20083N6581982-08-0404 August 1982 Informal Technical Communication Re 820721 Meeting in Livingston,Nj Concerning Schedule for Qualification Program of Tube Repair & Results of Preliminary Tests.Ornl 820817 Memo Re 820808-09 Meeting & Summary of 820915 Meeting Encl ML20054K0801982-06-10010 June 1982 Request for OMB Review & Supporting Statement Re Psychological Stress of TMI-1 Restart on Residents Living in General Vicinity.Estimated Respondent Burden Is 853-h ML20071J0471982-04-0707 April 1982 Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status Review 1998-08-28
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20154H9871998-08-28028 August 1998 Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release ML20154P8941998-05-13013 May 1998 Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas ML20217E1661998-03-18018 March 1998 Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust ML20217E1971998-03-17017 March 1998 Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening ML20217E1171998-03-17017 March 1998 Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability ML20217F9501997-07-24024 July 1997 Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers ML20148T7361996-11-0808 November 1996 Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals ML20148T7511996-11-0606 November 1996 Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level ML20129E9941996-10-10010 October 1996 Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity ML20148T6971996-09-11011 September 1996 Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs ML20148T6801996-09-0606 September 1996 Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level ML20148F0251994-02-0808 February 1994 Rev 0 to Condensate Storage Tank B ML20148F0081994-02-0808 February 1994 Rev 0 to Condensate Storage Tank a ML20148F0321993-12-0808 December 1993 Rev 0 to Bwst ML20148F1331993-09-30030 September 1993 Rev 0 to Make-Up Tank ML20148F1601993-09-27027 September 1993 Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways ML20148F0541993-09-17017 September 1993 Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A ML20057B9641993-09-10010 September 1993 AX114 & AX115 Ci Loading ML20148F1451993-09-0101 September 1993 Rev 0 to Nuc Serv Closed Cooling Water Surge Tank ML20148F1071993-08-31031 August 1993 Rev 0 to Intermediate Colsed Cooling Surge Tank ML20148F1221993-08-31031 August 1993 Rev 0 to Intermediate Closed Cooling Chem Mix Tank ML20148F1521993-08-31031 August 1993 Rev 0 to Nuc Svc Cool Chem Mix Tank ML20057B9581993-08-27027 August 1993 FH109/FH300 Ci Estimate ML20196K6431991-07-20020 July 1991 Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis ML20136B1461979-04-0303 April 1979 Calculations Made for Hydrogen Bubble in Reactor Vessel ML20136A9851979-03-30030 March 1979 Hydrogen Burn Vessel Explosion Possibility Calculations ML20136B1421979-03-30030 March 1979 Calculations Re Containment Hydrogen Bubble ML20125D8981978-08-31031 August 1978 Calculation Data Re Davis-Besse 1 Pressurizer Levels During Reactor Trips ML20076J8441977-08-14014 August 1977 Graph of Reactivity Worths at 532 F & 2155 Psig 1998-08-28
[Table view] |
Text
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. s y Enclosure 4 NUCLEAN CalculatlOn Sheet Sob) set Calc. No, Rev. No.
ESTIMATED RM-G-22/23 READINGS WITH LOCA AT TS RCS 66t2-%023 0 LIMIT P & tember 6,19% f_,;) f._, ey),,)g
'Q t i
- 1. Problem Statement The reading on RM-G-22 and 23 during a LOCA at the Tech Spec RCS hu g estimated.
2 Results Summary Based on the assumptions made in this calculation, it is estimated that RM-G-22 and 23 will read approximately 22 R/hr dtIring a LOCA at the Tech Spec RCS limit.
~3. References 3.1 TMI ODCM 3.2 EPA 400 3.3 TDR 989 Rev 1, TMI-l Cycle 8 Reload ( The basis for FSAR Table 14.2-4).
- 4. Assumntions 4.1 The Tech Spec isotopic activity of the RCS was based on TS 3.1.4.3 which prevents operation when RCS dose equivalent iodine (DEI) is above 1 uCi/cc. The isotopic activities for RCS with 1% failed fuel in Reference 3.3 result in a DEI of 7.68 uCi/cc. To develop and RCS activity with a DEI of 1 uCi/ce, the isotopic activities in Reference 3.3 were divided by 7.68. The resulting mix has a DEI of I uCi/cc and is esemad to be the TS RCS activity.
4.2 The dose rate at the monitor was determined using dose factors for imme sion exposure in a uniform semi-infinite cloud. For noble gases, the gamma air dose factors in Referece 3.1 were used.
Gamma air dose factors were not available for the iodmes, so the TEDE dose factors from Reference 3.2 were used. This is conservative, since the gamma air dose factor would be expected to be higher than the TEDE dose factor.
3 4.3 , It is asmmad hat t the volume of the Reactor Building is 2.0E+6 ft and the volume of the RCS is 66,595 gallons.
4.4 It is assumed that the activity in the RCS is instantaneously released and dispersed into the Reactor Building when the LOCA occurs - .
0 9707090294 970701 PDR F ADOCK 05000289 PDR
. . 1 G;>u NUCLEAn Calculation Sheet Subject Calc. No. Rs v. No. !
ESTIMATED RM-G-22/23 READINGS WITH LOCA AT TS RCS 6612 96-023 0 LIMIT i i
ortpmater Dese Revtewed by Date i PARFTIT September 6.19%
- 5. Data and Calculations 5.1 As discussed in Assumption 4.1, the factor used to convert 1% failed fuel to Tech Spec RCS activity I is calculated as follows:
FSAR 1% FF FSAR 1% FF RCS RCS i (SoTOPE ACTMTY DCF DEI i (uCug) (uCUg) h131 5.71E+00 1.48E+06 5.71E+00 b132 1.92E +00 5.35E+04 6.94E-02 L133 6.07E+00 4 00E+06 1.64E+00 b134 7.57E 01 3.73E+03 1.91E 03 k135 3.08E+00 124E+06 2.58E 01 TOTAL DEI 7.66E+00 !
DEI = (b137 ACTMTY)(b137 DCF) 6-131 DCF 5.2 The dose rate from each isotope at the monitor location is the product of the concentration (uCi/cc) and it dose conversion factor (mrad /hr/uCi/cc). The dose from each isotope is then summed to determme the total dose rate at the location. The calculation is summarized below:
ESTIMATED Rb" G-T! AND 23 DOSE RATE DURING LOCA AT TS RCS LIMIT RB VOLUME 2.00E+06 ft* .
, RCS VOLUME 66595 gal FSAR RMG-22/23 l 1% FF TS RCS RB RB DCF DOSE ,
RCS 1 uC1/cc DEI ISOTOPE ACTIVITY CONC MIEgg RATE (uCi/cc) (uCi/cc) (uCi) (uCi/cc) uCUcc (Redhr) 0.53 6.90E-02 KR43M 1.74E+07 3.07E-04 2.20E+03 6.77E-04 2.43 3.16E 01 KR45M 7.98E+07 1.41E-03 1.40E+05 1.98E 01 9.75 1.27E+00 KR45 3.20E+06 5.65E-03 1.96E+03 1.11E 02 1.28 1.67E-01 KR47 4.20E+07 7.42E-04 7.04E+05 5.22E 01
, 3.95 5.14E 01 KR48 1.30E+08 2.29E-03 1.73E+06 3.97E+00 2.88 3.49E-01 XE 1312 a.60E+07 1.55E 03 1.78E+04 2.77E 02 4.22 5.49E 01 XE 133M 1.39E+08 2.45E 03 3.73E+04 9.13E 02 392.00 5.10E+01 XE 133 1.29E+10 2 27E-01 4.03E+04 9.15E+00
. 0.49 6.32E 02 XE-135M 1.59E+07 2.81E-04 3.83E+05 1.08E.01 8.37 1.09E+00 XE 135 2.75E+08 4.85E 03 2.19E+05 1.06E+00 0.69 9.01E 02 XE-138 2.27E+07 4.01E 04 1.0$E+06 4.22E-01 '
5.71 7.43E 01 1-131 1.87E+08 '3.31E 03 2.20E+05 7.28E O'1.
1.92 2.50E 01 1-132 6.30E+07 1.11E-03 1.40E+06 . 1.56E+00 6.07 7.90E 01 1-133 1.99E+08 3.52E 03 3.50E+05 1.23E+00 0.76 9.86E 021-134 2.48E+07 4.39E44 1.60E+06 7.02E 01 3.08 4.01E 01 1-135 1.01E+08 1.79E 03 9.50E+05 1.70E+00 443.92 5.78E+01 TOTAL 21.5 4
- - . . . - . - - . ~ - . . . - . - - - . . - . . - - - . . _ . . . - - . . ~ . - - . - . . - . . - . . - . .
i
~ '
f , ..-:
'l I i h i
! h TMi Radio 6ogical contmie Departmental Procedure 6610 PLN-4200.01
- noe w m.
1 Offsite Dose Calculation Manual (ODCM) 12 l l
I '
TABLE 4.3 i . i i Does Factors for Nolde Genes and De.cghters*
i-Gamma Beta i Total Body Sidn Does Gamma Air Beta Air I Does Factor (a) Factor (b) Does Factor Dose Factor !
j Ki 1 5 Mi N, i
!- Radio- (mrom/yr per (rmm/yr per (mrad /yr, pet (mrad /yr per nuctide aci/mi act/m3 --.
acl/m; aci/mi Kr-83m 7.58E 02" -
1.93E + 01 2.00E+02 l
Kr-86m 1.17E + 03 1.46E + 03 1.23E + 03 1.97E +03 Kr 85 1.61 E +01 1.34E + 03 1.72E+01 1.96E + 03 g j i
Kr 47 5.9eE+03 9.73E +03 . 6.17E +03 1.03E + 04 Kr-88 1.47E + 04 '2.37E +03 1.52E +04 2.RBE +03 Krse 1.eeE +04 1.01E +04 1.73E +04 1.00E+04 Kr-90 1.50E+04 7.29E+03 1.SSE +04 7.83E +03
- Xe-131m 9.15E +01 4.7eE+02 1.5eE+02 1.11E+03 i Xe 133m 2.51E +02 k94E+02 3.27E+02 1.4aE +03 i'
Xe-133 2.94E + 02 3.00E +02 3.53E+02 1.06E+03 Xe-136m 3.12E +03 7.11E+02 3.3eE +03 7.30E +02 Xe-136 1.81E +03 1.seE+03 1.93E+03 '2.4eE+03 Xe-137 1.48E+03 1.22E +04 1.51E +0S 1.27E +04 Xe 138 8.83E +03 4.'13E + 03 9.21E +03 4.75E+03
]
Ar 41 8.44E+03 2.eeE +03 9.30E +03 3.2eE + 03 !
- Does factors are for immersion suposure in uniform somWnAnite doud of noble gas radionucHdes that may be I detected ingessous ofEueras. Does facnor values are taken from Regidplary Guide 1.100 (Rev.1), Table B 1. i "7.58E 02 = 7.56 x 10%
(a) Total body does factor for gemme pensastion depIh of 5 cm into the body ,
(b) Sidn does factor et a tissue depth or tissue donety thicknees of 7 mg/cm2, 120.0 .
l 4
. -w - - - -
- - - - . - - - - - - ~ -^^^^ ~ ~ ~ ^ '~"~'~ ~ ~~
. N j Table 5-3 Dose Conversion Factors (DCF) and Derived Response Levels (D External Exposure Due to Immersion in Contaminated Air
< DCP DRL6 Radionuclide rem per pCicm'8 h pCi cm.a h H 0.0E+00 0.0E+00 C-14 0.0E+00
! Na 22 0.0E+00
" 1.3E+03 7.8E-04 Na-24 2.7E+03 i
P-32 3.7E-04 0.0E+00 0.0E+00
~
P-33 0.0E+00 I S-35 0.0E+00
! 0.0E+00 0.0E+00 Cl 36 4.8E-06 l K-40 2.1E+05 9.2E+01 1.1E-02 K-42 1.7E+02 6.0E-03
- Ca-45 9.3E-09 1.1E+08 Sc-46 1.2E+03 Ti-44 8.4E-04
' 7.7E+01 1.3E-02 V-48 1.7E+03 i
- Cr-51 5.8E-04 1.8E+01 5.6E-02 i '
Mn-54 5.0E+02 2.0E-03 Mn 56 1.1E+03 9.4E-04 Fe-55 1.3E-02 7.FE+01
' Fe-59 7.0E+02 .
1.4E-03 O. 58 5.8E+02 1.7E-03 Co-00 1.5E+03 6.7E-04 Mi 63 0.0E+00
- 0.0E+00
' Cu-64 1.1E+02 9.2E-03 Zn-65 ~ 3.4E+02 2.9E-03 Ge-68 5.2E-02
- 1.9E+01 Se-75 2.3E+02 4.4E-03 Kr-85 1.3E+00 7.8E-01 Kr-85m 9.3E+01 . .
1.1E-02 Kr-87 5.1E+02 2,0E-03 Kr-88 1.3E+03 7.8E44 5 25
. h%
l Table 5-3, Continued DCF* DRL' Radionuclide rem per pCi cm' h ,
pCi em' h
} Sb 126 1.6E+03 6.2E-04 Sb-127 3.9E+02 2.6E-03 Sb-129 8.6E+02 .1.2E-03 Te-127m 1.8E+00 5.6E-01 Te-129 3.1E+01 3.2E-02 l
Te-129m 2.0E+01 5.1E-02
! Te-131m '
8.5E+02 1.2E-03
- Te-132 1.2E+02 8.0E-03 '
- Te-134 5.1E+02 2.0E-03 I-125 6.3E+00 . 1.6E-01 I-129 4.8E+00 2.1E-01 I-131 2.2E+02 4.6E-03 I-132 1.4E+03 7.4E-04 I-133 3.5E+02 2.9E-03 I-134 1.6E+03 6.4E-04 i I-135 9.5E+02 1.1E-03 Xe-131m 4.9E+00 2.0E-01 Xe-133 2.0E+01 5.0E-02
~
Xe-133m 1.7E+01 5.9E-02 Xe-135 1.4E+02 7.0E-03 Xe-135m 2.5E+02 4.1E-03 Xe-137 1.1E+02 . 9.2E-03 Xe-138 7.1E+02 1.4E-03 Cs-134 9.1E+02 1.1E-03 Cs-136 1.3E+03 7.8E-04 Cs/Ba-137' 3.5E+02 2.9E-03 Cs-138 1.4E+03 6.9E-04 Ba-133 2.1E+02 ,
4.8E-03 Ba-139 2.1E+01 4.SE-02 Ba-140 '1.1E+02 9.3.E-03 5-27 4