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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20154E5161998-10-0101 October 1998 Rev 10 to AP-961, Earthquake ML20154C2691998-09-29029 September 1998 Rev 19 to AR-304, ESD Annunciator Response ML20154C2751998-09-29029 September 1998 Rev 18 to AR-701, Ssf P Annunciator Response ML20154E5361998-09-28028 September 1998 Rev 34 to AR-403, PSA H Annunciator Response ML20154F0841998-09-28028 September 1998 Rev 21 to AR-503, ICS K Annunciator Response ML20154E5271998-09-28028 September 1998 Rev 20 to AR-301, ESA Annunciator Response ML20154Q0061998-09-24024 September 1998 Rev 8-0 to Crystal River Unit 3 Security Training & Qualification Plan ML20237B4431998-08-10010 August 1998 Rev 14 to AR-703, Ssf R Annunciator Response ML20236W9711998-07-30030 July 1998 Rev 24 to AR-402, PSA G Annunciator Response ML20236P9891998-07-13013 July 1998 Rev 22 to AR-501, ICS I Annunciator Response ML20249C1531998-06-20020 June 1998 Rev 4 to EOP-14, Emergency Operating Procedure Enclosures ML20249A3341998-06-0505 June 1998 Rev 10 to AP-330, Loss of Nuclear Service Cooling ML20247E6861998-05-0606 May 1998 Rev 20 to AR-603, Tgf O Annunciator Response ML20217Q4621998-04-30030 April 1998 Rev 15 to Crystal River Unit 3 ASME Section XI Pump & Valve Program Inservice Testing Program ML20247E6621998-04-30030 April 1998 Rev 10 to AP-250, Radiation Monitor Actuation ML20216A9981998-04-24024 April 1998 Rev 30 to AR-303, ESC Annunciator Response ML20217E1481998-04-20020 April 1998 Rev 21 to AR-302, Esb Annunciator Response ML20217C1441998-04-17017 April 1998 Rev 20 to ICS K Annunciator Response ML20217C2631998-04-17017 April 1998 Rev 13 to AR-703, Ssf R Annunciator Response 1999-03-09
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CRYSTAL RIVER - UNIT #3 0FF-SITE DOSE CALCULATION MANVAL i
i Approved By: b dAAd h V
Date: A q1 1940-Revision: 15 9009070181 900823 PDR ADOCK 05000302 ,
R PDC
l i
' , Calculation of Ingestion Dose Factor 1 Grass-Cow Milk Pathway c- -
Qr(Vap) f p fs (1 - fp fs) **A tih R D/Q = K' Fm(r)(DFLj)a +
i - -
Aj + Aw Yp e'A ttf Y3 where: Unit = m2 . mrem /yr per #C1/sec Reference Table R.G.1.109 K' =
A constant of unit convarsion,106 pCi/ Ci. I i
=
QF The cow's consumption rate, 50 kg/ day (wet weight) E-3 U
ap
=
The receptor's milk consumption rate for age (a), E-5 in liters, yr l Infant & Child - 330 Teen - 400 Adult - 310 Yp -
The agricultural productivity by unit area of pasture E-15 feed grass 0.7 kg/mZ Ys
" The agricu1%ni oroductivity of unit eea of E-15 stored feed 2.0 kg/m2 Fm = The stable element transfer coefficients, in days /kg. E_- 1 r =
Fraction cf deposited activity retained on cow's E-15 feed grass 1.0 radioiodine 0.2 particulates tr Transport time from pasture to receptor, in sec. E-15 '
l.73x100 sec (2 days) 4 th Transport time from crop field to receptor, in sec. E-15 i 7.78x100 sec. (90 days)
(DFLj)a - The maximum organ ingestion dose factor for the ith 5
E-Il to !
radienuclide for the receptor in age group (a), E-14 in mrem /pCi i Aj =
The decay constant for the ith radionuclide, in sec -I Aw The decay constant for removal of activ;ty on ; eaf and E-15 ;
plant surfaces by weathering 5.73 x 10 4 sec - 4 (corresponding to a 14 day half-life).
fp =
Fraction of the year that the cow is on pasture ----
(dimensionless) = 1*.
fs -
Fraction of the cow feed that is pasture grass ---
while the cow is on pasture (dimensionless) = 1*. -
- Milk cattle are considered to be fed from two potential sources, pasture grass and stored feeds.
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8.1' Oriain and Purnose of the Offsite Dose Calculation Manual The Offsite Oose calculation Manual was developed t'o support the implementation of the Radiological Effluent Technical Specifications required by 10 CFR 50, Appendix I, and 10 CFR 50.36. The purpose of the manual is to provide the NRC with- sufficient information relative to effluent monitor setpoint calculations, effluent related dose calculations, and environmental monitoring to demonstrate compliance with the Radiological Effluent Technical Specifications.
6.2 Channes it is recognized that changes to-the Offsite Dose Calculation Manual may be required during the operational life of Crystal River Unit 3. All <
changes shall ne reviewed and approved by the PRC arlor to implementation.
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The NRC shall be informed of all changes to tie 00CM by providing a description of the change (s) in the first Semiannual Radioactive Effluent-Release Repor'. following the date the change became effective.
6.3 Review ,
In addition to the change review in 6.2 above, the NGRC shall review the OOCH and its implementing procedures at least once per 24 months.
6.4 Unclanned Releases in order to better ensure that Technical Specification 6.9.1.5.d and 6.5.1.6.k are met, the following definition of " unplanned release" was developed. This definition should be used as " guidance only."
11 i
An " UNPLANNED RELEASE" is:
- 1) A release of radioactive waste to the plant environs which has not been -evaluated and released in accordance with approved procedures and Technical Specifications.
Radioactive waste in this context means radioactive material that I is awaiting evaluation before being released in a controlled l fashion. This includes plant condensate, and the contents of all of the waste tanks (i.e., ECST's, LSST's, WGOT's, SDT-1).
4 i
Examples:
Releasing the wrong waste tank, or sampling the wrong tank and l releasing the correct tank; I
l 2) A release of radioactive material through a designated effluent i pathway, which is due to equipment failure or human error, and causes i actuation of an effluent monitor warning alarm; J
l l
t o
! 87-
.t
[L-3)
Any sustained but not throug _ release of gaseous radioactive material from the RCA, i or human error,h a normal effluent pathway, due to equipment failure 1 which exceeds 1 MPC, restricted area.
Examples:
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Releases from the RB equipment _ hatch RCA'in excess of 1 MPC, restricted area.
Relee,es from the IB RCA in excess of 1 MPC, restricted area.
Not Examples of Unplanned Releases:
Short term increases and analysis activities. in effluent monitor count rate due to sampling -
Controlled releases due to planned maintenance activities.
Minor transient releases due to normal plant operations, such as waste
. processing warning alarm or power changes which may cause an- effluent monitor's to actuate. l Events within the Auxiliary Building which may actuate a process monitor alarm but effluent monitor are not warning of sufficient magnitude to actuate an alarm.
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