|
|
| Line 22: |
Line 22: |
| ** N/A . 4. 0 PRECAUTIONS AND LIMITATIONS 5.0 5.1 5.1.l 5.1.2 5.1.4 The .attached tables are based.on equilibrium core activities and Reg Guide i. 4 (Reference 2 2) release rates. Depending on core J.if e at time of accident these tables may erroneous results. PROCEDURE Determining Damage From 0 to 24 Hours After:Accident Determine tne dose rate from the Control Room entrance radiation mon:ttor. | | ** N/A . 4. 0 PRECAUTIONS AND LIMITATIONS 5.0 5.1 5.1.l 5.1.2 5.1.4 The .attached tables are based.on equilibrium core activities and Reg Guide i. 4 (Reference 2 2) release rates. Depending on core J.if e at time of accident these tables may erroneous results. PROCEDURE Determining Damage From 0 to 24 Hours After:Accident Determine tne dose rate from the Control Room entrance radiation mon:ttor. |
| This monitor appears as 1111 on the area radiation monitor strip chart recorder (RR".'"2302). | | This monitor appears as 1111 on the area radiation monitor strip chart recorder (RR".'"2302). |
| Absolute dose rate is obtained by subtracting normal.background | | Absolute dose rate is obtained by subtracting normal.background |
| (#11 reading before t=O) from the dose rate after accident occurs. | | (#11 reading before t=O) from the dose rate after accident occurs. |
| in Figure 1 to determine percent failed fuel. If the point determined is between two curves,, state results *as range between those* curves. (ie, 10%-50%, etc.). | | in Figure 1 to determine percent failed fuel. If the point determined is between two curves,, state results *as range between those* curves. (ie, 10%-50%, etc.). |
| Line 42: |
Line 42: |
| '#*kt! '"'1Y<fiE 4 ** 2WWS.* | | '#*kt! '"'1Y<fiE 4 ** 2WWS.* |
| z Q .... < ['!. i!. :,; 0: u-.. :q N ' I x ;rJ'I) 10 0 a* .,.* :' A . A Rev. 0 **i-*1 ... T T -r-. . *;r:-! :-rn . | | z Q .... < ['!. i!. :,; 0: u-.. :q N ' I x ;rJ'I) 10 0 a* .,.* :' A . A Rev. 0 **i-*1 ... T T -r-. . *;r:-! :-rn . |
| e*-:J: b Figure 1 * . , ' I*.*:: I**:. r :*.i :_:.::I.;: | | e*-:J: b Figure 1 * . , ' I*.*:: I**:. r :*.i :_:.::I.;: |
| :.1.: | | :.1.: |
| fl'}/-.:: (S': ://r-r1e': | | fl'}/-.:: (S': ://r-r1e': |
| Line 75: |
Line 75: |
| * i .:.---.!* : , t ;* . ;; :., : | | * i .:.---.!* : , t ;* . ;; :., : |
| * i *1 j **:'*:* . : ... ; i : ... :.; .. : . L . . . ... **:* .. | | * i *1 j **:'*:* . : ... ; i : ... :.; .. : . L . . . ... **:* .. |
| -: ; | | -: ; |
| ::. :*:--. | | ::. :*:--. |
| * .*. . .. : ... :. _ .. | | * .*. . .. : ... :. _ .. |
| Line 81: |
Line 81: |
| -.. -* -___ | | -.. -* -___ |
| .-.. ... | | .-.. ... |
| .. as :: | | .. as :: |
| :: , g JO . :'. , - | | :: , g JO . :'. , - |
| ... ........ . £-am .: .*. . .: .. : .... :!-. . ........ --*** '! ... ': ...... . --* ... '':** I : ottl .) *1* . '. . .. *** 1-': ***.. '!* ** 1 .... '. \ | | ... ........ . £-am .: .*. . .: .. : .... :!-. . ........ --*** '! ... ': ...... . --* ... '':** I : ottl .) *1* . '. . .. *** 1-': ***.. '!* ** 1 .... '. \ |
| Line 92: |
Line 92: |
| *** * -* -! __ . . ! ... ,.. . .. , .. -* . * .. . _...... -I' --* -::; | | *** * -* -! __ . . ! ... ,.. . .. , .. -* . * .. . _...... -I' --* -::; |
| __ | | __ |
| .. | | .. |
| :_* ___ :_-.. | | :_* ___ :_-.. |
| .. *.: *. *.-_=.-_=.* | | .. *.: *. *.-_=.-_=.* |
| =.* .. ;_*. | | =.* .. ;_*. |
| :_=. | | :_=. |
| .. _*_=.* = *. *.: | | .. _*_=.* = *. *.: |
| -=-* | | -=-* |
| =-_* ... _::._*_. | | =-_* ... _::._*_. |
| .. =. *.* ::_. __ | | .. =. *.* ::_. __ |
| :: | | :: |
| L: - | | L: - |
| .. . _ | | .. . _ |
| .. | | .. |
| .11 -'.. '. .. : . l if)) f; if! l i:; '..;::: . :.: ; ! !: : : '.1 ;.: : i ! ; n :! l:: | | .11 -'.. '. .. : . l if)) f; if! l i:; '..;::: . :.: ; ! !: : : '.1 ;.: : i ! ; n :! l:: |
| ::-;* _ *,::r | | ::-;* _ *,::r |
| .. | | .. |
| Line 116: |
Line 116: |
| ****i *-;-******-***: | | ****i *-;-******-***: |
| **:* .. ; ..... . ' pro; * | | **:* .. ; ..... . ' pro; * |
| .. :.;:*::1:::::**::::.::!::::;:_: | | .. :.;:*::1:::::**::::.::!::::;:_: |
| ::::: * * .. -* ... -* .. -... | | ::::: * * .. -* ... -* .. -... |
| . : .; .. ... =* ,: .. ;; | | . : .; .. ... =* ,: .. ;; |
|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
ML20137G3581996-02-15015 February 1996
Rev 6 to CPC Pnp Process Control Program
ML18064A8141995-06-29029 June 1995
Procedure EOF App B, INPO Emergency Response Assistance Agreement, Dtd 950426
ML20100H2621995-06-18018 June 1995
Rev 2 to Reactor Vessel Exam Program Plan Interval 2,Period 3 & Interval 3,Period 1
ML18064A8881995-03-16016 March 1995
Rev 0 to Palisades Nuclear Power Plant Third Interval ISI Program for Class 1,2 & 3 Components & Supports, Vols I & II
ML18064A6301995-03-0303 March 1995
Rev 7 to App H, Emergency Planning EOF Training Matrix.
ML18064A6341995-02-27027 February 1995
Project Plan,Alloy 600,Palisades Nuclear Plant, Rev 1,dtd 950227
ML20072K7741994-07-15015 July 1994
Rev 0 to Palisades Performance Enhancement Plan
ML20072K7641994-07-0606 July 1994
Rev 1 to Palisades Plant Restart Plan from 1994 Forced Outage
ML18059B0481994-06-0303 June 1994
Attachment 4 to Procedure EM-09-13,Rev 1, ISI Pressure Testing Program Procedure.
ML20069D3081994-05-24024 May 1994
Suitability,Training & Qualification Plan
ML20069G2511994-05-20020 May 1994
Rev 30 to Procedure MO-7A-2, Emergency Diesel Generator 1-2 (K-6B)
ML20069G2391994-05-20020 May 1994
Rev 30 to Procedure MO-7A-1, Emergency Diesel Generator 1-1 (K-6A)
ML20064E4831994-03-0606 March 1994
ASME Section XI Repair Program, 0054-00101-001-100,rev 0
ML20064E5011994-03-0404 March 1994
Procedure for Application & Exam of Weld Overlay Repairs to Austenitic Stainless Steel Piping Systems, 0054-00101-001-101,rev 0
ML18059A6981994-02-23023 February 1994
Reactor Vessel Integrity Project Plan.
ML18059A6881994-02-15015 February 1994
Editorial Changes to Rev 6 to Emergency Implementing Procedure EI-6.13, Protective Action Recommendations for Offsite Populations.
ML18059B0201993-12-31031 December 1993
Methods of Alleviating Adverse Consequences of Fluctuating Water Levels in Great Lakes - St Lawrence River Basin, Rept to Govts of Canada & Us,Dtd 931231
ML18059A5541993-11-19019 November 1993
Rev 4 to Attachment 3 to Procedure REC-1, Recovery Plan Format.
ML18059A4781993-10-27027 October 1993
Rev 5 to Administrative Procedure 9.11, Engineering Analysis.
ML18059A4231993-10-0707 October 1993
Rev 0 to Palisades Plant Pressurizer Safe End Crack Repair Action Plan.
ML20059A5181993-09-30030 September 1993
Public Version of Rev 36 to General Ofc Emergency Planning Procedure,App G, Emergency Telephone Numbers. W/931019 Release Memo
ML18058B7871992-12-15015 December 1992
Rev 3 to HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18058B0341992-05-11011 May 1992
Rev 6 to Odcm.
ML18058A4331992-05-0707 May 1992
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team, Page 3,reflecting Editorial Changes
ML20090A3401992-02-27027 February 1992
Rev 5 to ODCM
ML18058A1461992-01-27027 January 1992
Rev 45 to General Office Emergency Planning Gort/Eof Procedures Index
ML18058A1471991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-3, Emergency Operations Facility Administrator. Approval Summary Encl
ML18058A1441991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team. Approval Summary Encl
ML18058A1451991-12-0909 December 1991
Rev 6 to General Ofc Emergency Planning Procedure EOF-2, Emergency Operations Facility Director. Approval Summary Encl
ML20091S2361991-12-0909 December 1991
Rev 8 to General Ofc Emergency Planning Procedure GEN-3, On-Shift Sys Power Controller. Approval Summary Encl
ML18058A1421991-12-0909 December 1991
Rev 7 General Office Emergency Planning Procedure GORT-1, General Office Response Team (Gort). Approval Summary Encl
ML18058A1431991-12-0909 December 1991
Rev 10 to General Ofc Emergency Planning Procedure GEN-1, Overview. Approval Summary Encl
ML18057B3281991-10-17017 October 1991
Rev 2 to Procedure EI-15.2, Quarterly Communications Test Telephone Number,Verifications.
ML20086T2811991-09-16016 September 1991
Rev 0 to Functional Description FC-888,covering Replacement of All Four Channels of Reactor Protection Sys Power Supply Assemblies,Trip Unit Assemblies,Interconnection Modules, Bistable Trip Units & Auxiliary Trip Units
ML18057B0221991-05-10010 May 1991
Rev 15 to EM-09-04, Inservice Testing of Selected Safety- Related Pumps, Reflecting Complete Rewrite of Procedure to Omit Vertical Lines
1998-04-29
[Table view] |
Text
- . . PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE PROC HO EIB-3 PAGE 1 OF 8 REVISION O
- consumers Power *TITLE. DETERMINATION .OF OF CORE I DAMAGE DATE 4/29/80 REVIEWED BY PRC -DATE 4/28/80 QA-05 1.0 PURPOSE To provide a method of estimating the degree of core damage during accident conditions.
DATE 2. 0 :REFERENCES 2.2 2.1 Palisades Nuclear Plant, FSAR Table 11-1. 3.0
- N/A . 4. 0 PRECAUTIONS AND LIMITATIONS 5.0 5.1 5.1.l 5.1.2 5.1.4 The .attached tables are based.on equilibrium core activities and Reg Guide i. 4 (Reference 2 2) release rates. Depending on core J.if e at time of accident these tables may erroneous results. PROCEDURE Determining Damage From 0 to 24 Hours After:Accident Determine tne dose rate from the Control Room entrance radiation mon:ttor.
This monitor appears as 1111 on the area radiation monitor strip chart recorder (RR".'"2302).
Absolute dose rate is obtained by subtracting normal.background
(#11 reading before t=O) from the dose rate after accident occurs.
in Figure 1 to determine percent failed fuel. If the point determined is between two curves,, state results *as range between those* curves. (ie, 10%-50%, etc.).
- Record results on data shee*t.
ffff UfUi*',Jt U
g
. ' @. . . . PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE . . Tl T LE .. DETERMINATION OF EXTENT OF CORE DAMAGE PROC tlO EI8-3 PAGE 2 OF 8 REVISION o . DATE 4/29/80 I . consumers Power 5.2 Determining Damage.for Greater*thari 24 Hours 5.2.2 Determine dosa. rate from monitors RIA 1805, 1806, 1807 and 1808. These monitors appear as follows On strip chart recorder RR-3202: RIA No. 1805 1806 . 1807 1808 . ! Recorder Point No
- 19 20 21 22 Absolute dose rate is found by subtracting normal background (see 5.1.2). If four readings are 0btained>
use appropriate curves in Figures 2-5 and find an average value. Record __ r.esults on data sheet and submit for review by Health Physicist .and Site Emergency Director.
6.0 ACCEPr:ANCE N/A .... _ 7.0 ATTACHMENTS AND RECORDS 7.1 Figure 1 -Dose. Rc;i.te V?. Time for Control Rcom Entrance Monitor. 7.2 . l'igure .2 -Dos.e Rate vs. Time for Containment
/}1805 7 *. 3 Figure 3 -Dose Rate vs.
for Containment Monitor
7.4 Figure
4 -:-.Dose Rate vs. Time for Containment Monitor #1807. . 7.5 Figure 5 -Dose Rate vs. Time for Containment Monitor-ffl808
- 7.6. . Data sheet. for determining extent of core damage *.. Htv&&ii:IQ!
ssrn ;w:uz.ewaa
-J+iH4JI&WtZ:W&J4
'#*kt! '"'1Y<fiE 4 ** 2WWS.*
z Q .... < ['!. i!. :,; 0: u-.. :q N ' I x ;rJ'I) 10 0 a* .,.* :' A . A Rev. 0 **i-*1 ... T T -r-. . *;r:-! :-rn .
e*-:J: b Figure 1 * . , ' I*.*:: I**:. r :*.i :_:.::I.;:
- .1.:
fl'}/-.:: (S': ://r-r1e':
i;.9/'l:":.:
I :**:.;_;-;:
.. *;*:-:.r.::.:*:*: ***--* *-. 1---1 .. . -*** ---*-.....,._._, ........ ----:-r ......
0 ,
- .....! .
' '-LJ
.... _;._!--'-
_.__ ... :-.1--.-!--
I :;* () rt 2 i**-* *--i==---._
____.. '--**f.----.
'
... --_.___.,. __ , ______ ] t. l\*I . [. **-.----1-._..._
+-r--._...-
-*--* _,::t===+/-t:;-.---c::
___ . t:* -. ,._:-. --....
1---.
--.... . . P.---:
t* I---'=i-* **1-i-**---
'1--* i ; :
V _,., , r ----
- -:--..L...: . -, -*-. ' 11 , , , . . . . ::t::t:::
-,-i-< 1* 1 1
- . . , . : . : ; . , *..:..-+ . , . 1 I , , . --, -r: . :..-=:-i .* i * . . . -. /I, 8 (1.h0"'7 / .,J.t"J't:1;>,i/
J.*'f:! 7"'!.!-?(' "" ; y, 11 1>1 "' ., I* 9 r -t -: . 1-L. J; )7J' ... ll'*' ... iJ * ..... 1q,r*11t*r*o I I .I.*, .... , .... , .. ****!***-!-***
' i {J:::'.t;::
1,E1 ff Jilli n 1 11 ' ' T-i '."' -: !', '..!!
- i .:.---.!* : , t ;* . ;; :., :
- i *1 j **:'*:* . : ... ; i : ... :.; .. : . L . . . ... **:* ..
-: ;
- . :*:--.
... '. .*--** .. *:-.* ............
-.. -* -___
.-.. ...
.. as ::
- , g JO . :'. , -
... ........ . £-am .: .*. . .: .. : .... :!-. . ........ --*** '! ... ': ...... . --* ... :** I : ottl .) *1* . '. . .. *** 1-': ***.. '!* ** 1 .... '. \
- * ::.c;rtl 1 " 1 t ii . 1: !: '* ! . e . . * . . . .... * .. _-.-...._ . I
.: .. ____
.... . *-.... _ _ _ _ _ _ ,
'1 0;tffl
- -_--f i*: -* ** -* * * * * *** -*** * *** *** **-** ** *
- * -* -! __ . . ! ... ,.. . .. , .. -* . * .. . _...... -I' --* -::;
__
..
- _* ___ :_-..
.. *.: *. *.-_=.-_=.*
=.* .. ;_*.
- _=.
.. _*_=.* = *. *.:
-=-*
=-_* ... _::._*_.
.. =. *.* ::_. __
L: -
.. . _
..
.11 -'.. '. .. : . l if)) f; if! l i:; '..;::: . :.: ; ! !: : : '.1 ;.: : i ! ; n :! l::
- -;* _ *,::r
..
1****1*-**1****l*-**J****l****1****1*
- 1****1****f****f*********I
'.1 .i . e I J /Ot ... :*-*-*
- -*** **--.. ,---** *i*. .. ...
.. :.;:*::1:::::**::::.::!::::;:_:
- * * .. -* ... -* .. -...
. : .; .. ... =* ,: .. ;;
DATA. SHEET FOR DETERMINING EXTENT OF CORE DANAGE ..
- EI8-3 Rev. 0 Page 8 4/29/80 Time (Post'-Accident)
Hours, Days I Noni tor Location* . ---.. ........ ---... Dose Rate % Failed Fuel >-. Technician . , . Reviewed by Health.
Reviewed by Site Ernerg.
