|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212F9221999-09-23023 September 1999 Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm ML20211L2871999-09-0202 September 1999 Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F ML20210R3581999-08-13013 August 1999 Proposed Tech Specs Allowing Performance of CRDM & Ni Instrumentation Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling,while Fuel Is in Reactor Vessel ML20210Q4101999-08-0606 August 1999 Proposed Tech Specs Section 3/4.6.4, Vacuum Relief, Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers & Revising Action Statements & Srs,Per NUREG-1433 ML20209G3581999-07-14014 July 1999 Proposed Tech Specs Pages Re Amend to Licenses NPF-11 & NPF-18,revising TS Allowing LCS Units 1 & 2 to Operate at Uprated Power Level of 3489 Mwt ML20209D3231999-07-0707 July 1999 Proposed Tech Specs,Revising MCPR Safety Limits & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20209D3931999-07-0707 July 1999 Proposed Tech Specs,Changing Proposed Degraded Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable Value ML20206T1401999-05-19019 May 1999 Proposed Tech Specs Section 3/4.4.4, Chemistry, Relocating to UFSAR ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20207A9491999-02-23023 February 1999 Rev 4 to LaSalle County Station Restart Plan for Unit 2 ML20195E0101998-11-0909 November 1998 Proposed Tech Specs Re Application for Amends to Licenses NPF-11 & NPF-18,adding Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer ML20195E0541998-11-0909 November 1998 Proposed Tech Specs Pages Re Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value to TS 3/4.3.3 & TS Table 3.3.3-2 ML20154M4641998-10-16016 October 1998 Proposed Tech Specs,Lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect ML20151Y5991998-09-14014 September 1998 Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only ML20236U5511998-07-24024 July 1998 NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station ML20217M6671998-05-0101 May 1998 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20217N9541998-04-30030 April 1998 Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm ML20217P2511998-04-28028 April 1998 Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20216E3221998-04-0707 April 1998 Proposed Tech Specs Pages Re Addition of Ventilation Filter Testing Program ML20217J2981998-03-24024 March 1998 Proposed Tech Specs Deleting Unit 1 License Condition 2.C.(30)(a) in Entirety ML20202C8971998-02-0202 February 1998 Proposed Tech Specs Re Changes to Relocate Fire Protection Requirements ML20203G5051997-12-12012 December 1997 Proposed Tech Specs,Modifying Bypass Logic for Msli Valve Isolation Acuation Instrumentation on Condenser Low Vacuum ML20199K5481997-11-24024 November 1997 Proposed Ts,Adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for Rwcs Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms & Eliminating RHR Sys Steam Condensing Mode Isolation Actuation Instrumentation ML20211P9331997-10-15015 October 1997 Proposed Tech Specs Eliminating Unnecessary Detail from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3771997-09-26026 September 1997 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20216H7711997-09-0404 September 1997 Corrected TS Bases Sections B 3/4.2.1 & B 3/4.2.3 Re Thermal Limits ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20217Q7981997-08-26026 August 1997 Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20141J5671997-08-12012 August 1997 Proposed Tech Specs Surveillance Requirement 4.7.1.3.c Re Ultimate Heat Sink by Deletion of Sediment Deposition Insp in Lake Screen House ML20151K9551997-08-0101 August 1997 Proposed Tech Specs Changing Title of Site Quality Verification Director to Manager of Quality & Safety Assessment ML20148U2591997-07-0101 July 1997 Proposed Tech Specs to Change Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases. TS Affected Are TS Definition 1.4,TS Tables 3/4.3.2-1 & 3/4.3.6-1 & Bases for TS 3/4.3.1 ML20148Q4301997-07-0101 July 1997 Proposed Tech Specs Reflecting Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation & Unnecessary Challenges to ESF ML20148N0201997-06-19019 June 1997 Proposed Tech Specs,Relocating Fire Protection Requirements ML20141L0371997-05-27027 May 1997 Proposed Tech Specs,Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administrative Changes ML20148D9561997-05-16016 May 1997 LSCS Unit 1/Unit 2 Restart Plan ML20137W5131997-04-14014 April 1997 Proposed Tech Specs Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation Design Change ML20140C9231997-03-31031 March 1997 Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index ML20216H8691997-03-31031 March 1997 Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F ML20134A1931997-01-20020 January 1997 Proposed Tech Specs 3/4.1.3.5 Re Control Rod Scram accumulators,3/4.4.4.3.2 Re Reactor Coolant Sys Operational leakage,3/4.5.1 Re ECCS - operating,3/4.5.3 Re ECCS, Suppression Chamber & 3/4.6.2.1 Re Suppression Chamber ML20135E6841996-12-0202 December 1996 Proposed Tech Specs,Requesting Amend to Section 3.4.2 to Revise SRV Configuration to Include Only 13 of Current 18 SRVs ML20134L0221996-11-30030 November 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12 ML20129J4491996-10-31031 October 1996 Proposed Tech Specs Re Elimination of Seismic Monitoring Instrumentation Requirements ML20129B7981996-10-14014 October 1996 Proposed Tech Specs 2.1.2 Re Thermal Power,High Pressure & High flow,5.3 Re Reactor core,4.0 Re Design features,3/4.1.3 Re Control Rods & 3/4.2.4 Re Linear Heat Generation Rate ML20116A9601996-07-15015 July 1996 Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections ML20115D8781996-07-0808 July 1996 Cycle 8 Startup Test Rept ML20113C8641996-06-21021 June 1996 Proposed Tech Specs,Including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0641996-04-16016 April 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20107A8641996-04-0808 April 1996 Proposed Tech Specs for Siemens Power Corp Fuel Transition ML20097C9051996-02-0202 February 1996 Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program ML20096G3411996-01-18018 January 1996 Proposed Tech Specs,Changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High 1999-09-23
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212F9221999-09-23023 September 1999 Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm ML20211L2871999-09-0202 September 1999 Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20207A9491999-02-23023 February 1999 Rev 4 to LaSalle County Station Restart Plan for Unit 2 ML20151Y5991998-09-14014 September 1998 Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only ML20236U5511998-07-24024 July 1998 NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station ML20217N9541998-04-30030 April 1998 Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm ML20217P2511998-04-28028 April 1998 Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20217Q7981997-08-26026 August 1997 Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20148D9561997-05-16016 May 1997 LSCS Unit 1/Unit 2 Restart Plan ML20216H8691997-03-31031 March 1997 Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F ML20140C9231997-03-31031 March 1997 Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index ML20134L0221996-11-30030 November 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12 ML20097C9051996-02-0202 February 1996 Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program ML20095F4041995-12-0202 December 1995 Rev 1 to Procedure LZP-1250-1, A-Model Operation ML20093H1791995-10-10010 October 1995 Rev 1 to Pump & Valve Inservice Testing Program Plan,2nd Ten Year Interval for LaSalle County Station Units 1 & 2 ML20094D9271995-09-30030 September 1995 Rev 1.7 to ODCM Chapters 10,11,12 & App F for LaSalle Station ML20077Q5601994-12-30030 December 1994 Offsite Dose Calculation Manual Revisions to Chapters 10-12 & Appendix F for Lasalle Station ML20149G2551994-10-17017 October 1994 Rev 0 to ISI Plan for LaSalle County Nuclear Station Units 1 & 2 Second Ten-Year ISI Interval ML20149G2591994-10-17017 October 1994 Rev 0 to LaSalle County Station Units 1 & 2 Pump & Valve IST Program Plan 2nd Ten-Yr Interval ML20065G5401994-03-23023 March 1994 Rev 1 to Test Procedure TR-213, One Hour Fire Test of Darmatt KM1 Sys for Protecting Cable Tray,Conduit,Supports & Junction Boxes in LaSalle Nuclear Power Station Units 1 & 2 DG Corridors ML20063F8921994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Lasalle County Station ML20059M9671993-10-27027 October 1993 Rev 1 to LZP-1130-2, Core Damage Assessment ML20045B5921993-05-28028 May 1993 Rev 1 to Procedure LZP-1210-4, Reporting of Transportation Accident. ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20114C7321992-08-20020 August 1992 Revised Annex to Chapter 11 to ODCM Re Exposure Pathway &/Or Sample ML20101M3611992-06-25025 June 1992 Offsite Procedures,Including Rev 16 to LZP-1110-01,Rev 2 to LZP-1110-2,Rev 4 to LZP-1120-2,Rev 4 to LZP-1210,Rev 0 to LZP-1210-3 & Rev 0 to LZP-1210-4 ML20079C0351991-05-0303 May 1991 Rev 2 to Procedure LZP-1330-30, Transfer of Wastes from Hrss Waste Tank & Waste Sump ML20043G4791990-05-18018 May 1990 Offsite Procedures,Including Rev 1 to LZP-1330-12,Rev 2 to LPZ-1330-13,Rev 1 to LZP-1330-14 & Rev 6 to LPZ-1330-14 ML19327A7521989-08-16016 August 1989 Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20236G5971987-07-0101 July 1987 Rev 0 to Units 1 & 2 Combined Inservice Testing Program for Pumps & Valves,Lasalle County Station,Comm Ed ML20212B2791986-07-28028 July 1986 Revised Std Radiological Monitoring Program,Lasalle County Station ML20214P6431986-06-18018 June 1986 Rev 1 to Procedure 8601-009, Model 103 Long-Term Test Plan ML20205F5721986-05-31031 May 1986 Rev 12 to Offsite Dose Calculation Manual List of Tables for La Salle Section 8.0 ML20203L3551986-04-30030 April 1986 Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor ML20155F4541986-04-18018 April 1986 Snubber Reduction Program for Nuclear Piping Sys,Lasalle County Nuclear Station Units 1 & 2 ML20138Q1261985-11-30030 November 1985 Rev 11 to site-specific Sections 7.2 & 8.0 to Offsite Dose Calculations Manual ML20138B2711985-11-22022 November 1985 Rev 0 to LaSalle Station Proactive Mgt Plan ML20116C9751985-04-0909 April 1985 NUREG-0737,Suppl 1,Detailed Control Room Design Review Program Plan Suppl 3 ML20127J3041985-03-11011 March 1985 Rev 0 to LAP-100-15, Control of Vendor Equipment Technical Info ML20086J8191984-10-17017 October 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures LZP-1200-5 Re Generating Station Emergency Procedure Guidelines for Offsite Protective Actions & LZP-1310-1 Re Notifications ML20087J2501984-03-15015 March 1984 Rev 0 to Procedure LTS-1000-35, Fire Damper Operability Test ML20087H1501984-03-0505 March 1984 Rev 1 to Procedure LTS-1000-36, Fire Damper Visual Insp ML20079L7441983-12-29029 December 1983 Public Version of Rev 3 to Emergency Plan Implementing Procedure LZP-1210-1, Hazardous Matl Incidents Reporting ML20079P0331983-11-21021 November 1983 Public Version of Revised Emergency Procedures LZP-1330-21, Determination of Reactor Coolant Chloride... Sampling Sys & LZP-1330-25, Sampling of Reactor Coolant at High Radiation Sample Sys ML20083H8761983-11-17017 November 1983 Public Version of Rev 2 to Emergency Plan Implementing Procedure LZP-1360-2, Use of Potassium Iodide (Ki) as Thyroid Blocking Agent & Revised Index ML20083G5071983-11-0404 November 1983 Public Version of Rev 2 to Emergency Plan Implementing Procedure LZP-1200-4, Classification of Liquid Release. Revised Index Encl ML20090L6481983-10-31031 October 1983 Rev 6 to Procedure Lts 300-4, Unit 1/2 Integrated Primary Containment Leak Rate Test ML20085K4251983-10-0303 October 1983 Public Version of Rev 5 to Emergency Plan Implementing Procedure LZP-1110-1, Station Director (Acting Station Director),Receipt Form & 10CFR50.59 Format for Safety Evaluation 1999-09-23
[Table view] |
Text
- - - . - , .. _ . _ _
e .
pi
. . LAP 82022; ATTACHMENT F
- - Revision 19 1 , ,.;..,. <
@ge 1 of 2) Aprilf,19R? j 20 10CFR50.59 FORMAT FOR SAFETY EVALUATION STATION UNIT TEST /PRCCEDURE No [_ E 8 / 8 8 d .'2 /
SYSTEM .
tuepammT:ou oP 'ItEAc.we. cooca aJr
. S 2-TEST / PROCEDURE TITLE C*.ottw coweenersea 4T 78t. 6M {EVISION i
EQUIPMENT NAME M4 EQUlPMENT NUNSER MA --
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SAFET( 'cVALUATION: Answer the following questiens with a ":<yds" er "no", a ,
reasons justifyirg the decision:.
5[ 1. Is the pechobility cf en occurrence or,the coczequence of en accident, or
' ty es previously evelueted in the Finci id'ety Aralysis Raport l
equipment importent to Yes __ No, Gecausa: ,C W g pe- 4 ,c Shm m of &2% h ^^ O W& l N f incrossed?
l i
l
- 2. Is ths possibility fer en eccident er malfunctionYes
' e Fi i Sciety Anclyst:t Report creeted?
c/ a different type thengn No, Beceuse:
evolu u; l
i
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r y' #oted ^ in
= f44A. ,
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t s h 3.
Is the mergin er screry, es defined in the basis for f:ny ' Technicci M6'%<.'
n S=ee!!!c=r ki l X No, Because: Ma* <
Yes ~74* *fa u- w On 0-e.:
j
- p ees s c.u s w > %C O (
I
!' Any answer checked "YES" should be reper:se'in, the Annual Recor-:.
[
to the NRC f./
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Cet Peri:-med 54 v / 4 wg 82060goog4 820527 g F
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LAP-320-2 i
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Revision ;9 i
. April 7,, 1982
. . *
- ATTACHMENT F 2,1 fina!. '
-m .
.; ) SAFUY EVALUATION CHECKLIST (10 CFR 50.53) j g
TEST / PROCEDURE No. /.J A/ 27o - 2/
REVISION 2
. f_. '
Doec this c:nstitute a change to procedures as described in Safety Analysis Report?
'.5
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.I_ te: ( )
,-- s a =anga in == Tec nical Icecsfica:ica
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}inrcivee?
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Answr the f:llcwing cuestiens wi-M i *y::' :
-, SAFUY DAL' TIC:l:
'c and pr:vids,s;ecific reas ns justi'ying the facisicn:
Is ce :r:bability cf (n.=c: r secs. -Mt c:nsecuence of 2n C' 1.
ac:t:an:, Or ..al fune.icn of saf t:7 rtil:ad stui:: snt, 12 ;rt,i:::!y evatus:ad in ce Final Safety analysis .tecert, incruse ? .
r
~r Yes % No ,
e
{..
Is ths ;:ssibill:7 fcr an acciden er . aifunc:f =n of a dif:'are.n:
.ds '^
2.
ty:t can any crtvicusly evaluated n'f o:Me Yes ,
Fina! Saft'y * :
17 :15 Re;:cr: crts 2d?
y,
'ad
basis f:r any T4 =-10:1 3.. Is the ::artin of safety, as defined in -
Scec1#ica:1:n, riducad7 Yes No.
~ s- A11 Ans.*en No ,
, ?-
_ :ns ;nraer - Yes ( ) *
- eE271i 2*.Or/ C0::"l rid.$ I -n -
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, .= .. LAP 820 ATTACHMENT F Revision 19 ,
Qage 1 of 2} A ril 7, tort 20 10CFR50.59 FCRMAT FOR SAFETY EVALUATION STATION A IIe UNIT SYSTEM T TEST /PRCCEDURE No df8 /.,Do - 72.
.F.ST/ PROCEDURE TITLF, c.aiseenw ofe: io wwu /N QW% REVISION 6
g e g g g gg y Q g g , g (_, fA der EqulPMENT NAME Mo)& to 3 foggy EqulPMENT NUMBER 0 PL 6 (J', _.
..m_--
DESCRIPTION OF TEST /PRCCEDURE ' / M N C*f bkyk N M M N.
SAFiiY EVAWATICN: Answer the following questions with a "yes" er "no", and gw reasons justifyiry the decisien:
I
- 1. Is the probo'nility of an occurrence er t!w cor=equence of en accident, or m
' .- es previously ownluoted in ths Finel Sciety Anclysis Resort equipment impertent to safe
- i. 47 Yes _ .
No, Becausa: ,& m %
h' .o , m e Oa LA_e -
- 2. Is the possraility fer en uccident er malfunction'Yes of a different V No, Seccuse:type then eny evolueted in the Final Seisty Analysis Repert created? '
h# 7f,Y a- ,
ese .
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Is the mergin ei sciety, es defined in the basis for cny Technicel Saecifie= tion
- 3. '
Yes M No, Secause: orf f e,/- m 62.fr/ ~4
. W. '
Any answer checked "YES" should be reported in :he Annual Recort.
- o the NRC s $2f A lL C=ta - I Periermed Sh_
- Aq,rrousi 17 ** ht 3sie,f3G!h r:
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LAP-320-2 .-
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9 April 7, 1982
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(Page 2 of 2)
CFR 50.33)
.;-) ,. ,
g SAFETY EVALUATION CHECKLIST l tr l (1p 'US -ZL.
- REVISION 2-1:
. w r '
Does this constitute a change to procedures m ,
as described in Safety Analysis Report?
,I (es ( ) .'!c D T
,O } is a :nanga in == Tecnnic.a.1 5;ect fica ica t
a.. ifavcivec? .
_ .l 'to M - r - . . . . .. .
g
- Answer the fellcwing Jesticns wiu a 'ys ' : P* '.
L.. SAFEif E7AL"ATIC.1:
and ;r:vids,s;:ecific reascns jus:1'ying the tectsfen:
L. Is ens :r:bability cf an. cc: .- snes. Se c:nsecuence cf inas ;rtvf:::17
' ac:ican , er malfune:1 n of saft:/ rela:ad ecuf::incriare? snt, .
evatustad in the Final Safaty Analysts Re:cet, m _Yes No, f . .
r Is the ;essibility fer an accident cr' eaifunc:f =n of a if2,- f 1fer:n: 7 :11 L' ^
. 2.
ty;s than ar.y ;rtvicusly evalua:xd in :he Final Saft:y Mfo, ne:cr creatad? \ Yes y %
u
, n .
1 3.. Is the argin of saft:y, as defined in :he.N obasis f:r my c:n-f:
Yes , .
Scecificatica, reducad?
Q.
G .
i
'- Anv Ansser - Yes ( )
,i A11 Ans ers No r
Recus : ec . ective .'tucitar f ?.aquI a =: / Cemi.s.s f.:n .
tu: :r n:' n ?y :.~enes. .
l .
r -- ' *u=:--n:i:n ?ec ived ( )
1- * ,
t.L Initia a Fr:cswrt/ Test "l0T?.: I. lemnts:icn
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Per':r-ed by )/]
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LAP 82022-j .
~ '
ATTACHMENT F Revision 19 (Page 1 of 2} April 7, 19At
- 20 10CFR50.59 FCRMAT FCR SAFETY EVALUATION STATION [d.[d UNIT SYSTEM M TEST /PRCCEDURE No d M/280 ~ 2.,7 Mreeg. of E x C ae6 A NT- P W, f.MD .
TEST / PROCEDURE TITLE-+ D o- Nr WE H845 .
REVISION I EQUIPMENI' NAME ))A Ale EQUIPMENT NUMBER ,_
m OESCRIPTION CF TEST / PROCEDURE ' ,,v/ound y NEy frna W G f aud d &dt$vC/ g y u M Ct-x " , M -a "
aea in,u n w g _
~ w M L.gw:/c.5/0ws - -
t e
SAFEiY EVALUATION: Answer the following questiens with a "yes* cr "no", and ,,,
reasons Justifyirg the decision:
(
Is the pechobility of en occurrence or the coresquence of en occident, or ma
'.- 1. es previously evaluated in ths ~ l Sefety Anclysis Racert equipment importent to safe No, Becausa: he,4.h h a./Je increased? Yes Yks QW, & &
(d4 & a aM ' .
- 2. Is the posibility fer en uccident or malfunction of a different Yes type th=n any W No, Because:
evaluated in the Final Scisty Analysis Report created?
w h '
YSb $.
- 3. Is the margin of sciety, es defined in the basis fer cny Technic =I% Specific 4kad.o tion,
~ Yes M No, Secause: 'BefJg g o.,J. e cu:.e. M m&O -
- Note: Any answer checked "YES" should be reported in the Annuel Report.
o the NRC
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April 7, 1982 ATTA:HMENT F 21 fina!'
(Page 2 of 2) ej ,. ,
g SAFETY EVALUATION CHECXLIST (10 CFR 50.53)
TEST / PROCEDURE No. 4.7//3fo-g3
- RE'llSION / -
n -
.g!-
Oces this constitute a change to procedures
- l as described in Safety Analysis Report?
5 1
(es ( ) '!c W p '
- s a cang i n == ecnnical 5:ec1fi:2:ica
.s _ . ,
'invcivec7 *
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SAFIi7 I7ALUATIC;I: Ansner the felicwing :uesti:ns wi th a 'ys:' :r ' :' ,
and pr:vids,ssecific reascas justifying :he incisien: i b !. .
!s one :r:bability cf an, cce.:r seca. :Me ::nsecuence efas2n;rtvi:::!y
. ' ac:ican:, or =alfuncti:n cf saf t:y rtil:ac equi:. snt, evalcated in the Final Safety analysis Re:ce. increass? .
-m Yes 5C No.
F. .
L..
4
- . ym Is the ;cssibill y f:r- in accident er maifunett:n Of a it f f ar n:
C 2.
^ tytt than any crsvicusly evalua:ad in the Fina! Safety 2,uly:is Yes V No, w Re ert creatad?
m *
'. M+ .
31 3.. Is One margin of safa:y as defined in :te basis f:r any Tc=ni:
Yes >< No , .
Sceci'icati:n. reduced?
I 1I "
Anv Ansser
- Yes ( 1 All Ans*deM Mc M a .. .
Recue: inc . tetive ?!ucitar F :aqui z=: / Omri.$.s ica
, 2:==M : 1 i:n ! Jr :.' tete. .
s
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}- ATTACHMENT F Revision 19 (Page 1 of 2} April 7, 14A7 l' .
10CFR50.53 FORMAT FOR SAFETY EVALUATION il'AT10N [a UNIT l l
SYSTEM d TEST /PRCCEDURE No d'2// iI.3d 'M 1
pyrygisc., of Q.wTR&MS1'AIK.
l ,
0-TEST / PROCEDURE TITLE 4r Tw6 N255 REVISION EqulPMENT NAME
OESCRIPTION OF TEST / PROCEDURE' c[t.,40rM NM#I M a & c />ee a f a<J k njo Ae- a%Ay @-M&,
N N .
Q mho<.a/ af& -
Wd c.% 4- o vs-d A Y-t b
= end provide- senific
' SAred EVAL.UATION: Answer the fellowing gestiens with a "yes" cr "no",
reesens justifyirs the decision:
Is the prc'chility of en occurrence er the cer=ewence of en ce Pident, or mcl 1
' .- 1. e ecpipment inwnt to sciety es previously ow:lueted in ths 4 AbrFinci y Sciety Anclys Yes % No, Becausa: , M wa.,,g increeed? % GCA+OM0
/>c f nx.smC4 & ~d>u % Mk /uusx sM-sa s u 4/ Q s W<.d,&L .no ey cc4a.cpw #J
- 2. Is theinpersi'aility evaluated fer Repcer the Final Saisty Analysis en cceident created? er malfunction Yes See usa:
of a
,9 * . w epe?v a'ad n Y y ( A , d d V N M CL M
<^'<e d d b r l snc.tw4 cf mene l
g in ep,_terg, c2 defined in the xgbcsis fer eny Technic
- 3. Is the g'gix,pwsW ,?5 Y&& ""'
"YES" shoul b ted in the Annual Recort.
, e' y enec to the NRC
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q-Revision j9
. A III 7., 1982 21 fina!.
.", 5 - ATTACHMENT F
~
- - (Page 2 of 2)
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SAFETY EVALUATION CHECKLIST (10 FR 50.53) (::,
.*-)* ,. ,
g TEST / PROCEDURE No. L /33)62
- REV I3(CN *2 Does this constitute a change to precedures m ,
as described in Safety Analysis Report?
.lo
~
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p' li,s a =anga in == 7te nical Scecifica-ica
.i..'.}fnvcived? .I
.,cws. - r ..
Ansner- Os felicwing :uesticns w121 'y'.:'
- P ' :' ,
- I L. SAF1E'i / IVAL"ATIC I
and ;r: rids,scecific etascns justifying me incisicn:
C 1,. Is es :re: ability cf an ec=r tnes. Se c:nsecuence c' 23is :rt'if :ly
' ac:ican , er -alfunctiin' of saf te/ rita:ac ecuf:= tnt.
evalus:sd in the Final Safety Analysis Xe:cr., incrtase? .
Yes fNo, lce4 44 %g PSAL t
- 2. Is the ;cssibf1f ty f:r- an ac:idant 'er eemaifuncti:n
.:fnst Saft:y of aLn if ffar sis n:
{* ^
ty;e can any =rtvicusly evalut: Ha, W /%.W Re:cr: crts:st? Yes r- "w ts>
" , F5M'-
N . -
3.. Is :ne argin cf saferf, as defined in the.o, basis82ot f:r any Tc=ricalo M Scecificatien, rtducad7 Yes M' - -
C d .
a./6- ALWL M
- . Anv Ansser - Yes ( )
,s - Ali Ans ers No Recut: Lnc -tesioc nuclesr*
I Esqui1=: / CarniM J cn
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