|
|---|
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
' *_; -*-*:~----* ..-------* *--**--**-----**** ------*-*
EOP .l through 12 - EMERGSI-lCY O?ERATING ?ROCEDURES
~---~~------
Ht:?vision Number Abstract PRC D8.te .1'1.1:roroval 1 .EOP 1 - Change Page 2' 3, and 6/4/80 page 2 of Attachment 1. 5/2/80 EOP 2 - Change page .l 6/4/80 and page 2 and Attach. 2. 5/2/80 Original Signatures EOP 5 - Change page 3, 5/2/80 are on file in EOP 6 - Change page 1 and 2. 6/4/8.o O;perations Clerk's EOP 7 - Change page 1 and 2. 6/4/80 Office.
EOP 8.1 Change page 1 and 6/4/80 page 2 and 7. 5/2/80 EOP 8.2 Change page 3, 5/2/80 EOP 10 Change page 6 and 7. 5/2/RO
.2 EOP 1 - Change page 1, 2, and 3 of Attachment 1. 8/12/80
/ EOP 6 - Change Page 2 of
( Attachr.ient. 7. 7/2/80 F.OP 8.1 Change page 2 of procedure and pase 2 of Attachment 3. 7/2/80
~~ EOP 6 Change page 1 and 2 of Att.achment '( . 8/12/80 EOP 8.1 Change page 1 and 2 of Attachment ...,.) . 8/12/80 4 EOP 6 Change pag12 1 and 2 of Atte.chment 7. 9/3/80 EOP 8.1 Change page 1 and 2 of' Attachment ? ..)*
9/3/80 Add Attachment 6. 8/14/80 5 EOP l Change page 2 ttro11gl1 4. 10/16/80 ~J'~~-i\A>,l.-,,-.- I *'I~'>>
I cJ ;) ..,, -...::-~
F.OP 8.2*change I\ttachm~nt ..L. ,
EOP 1 REACTOR TRIP Revision 0 This procedure applies to a reactor trip initiated from one or more normal inputs to the Reactor Protective System, with standby power available at the time of the trip.
1.0 Syinptoms (1) Any one or moce of the Reactor Protection Trip (RPS) alarms.
>l, (2) Coritrol Rod lower electrical limit lights (green).
(3) Control Rod positions indicate near zero.
(4) Various other alarms may be present, depending on the situation causing the trip ..
2.0 A~tomatic *
( (1) Turbine/Generator trip causes:
(a) . Fast trarisfer of station power to startup power.
(b) Cooling tow~r fans trip.
(c) MSR inlet valves closed. **E-9A **CV-0594, **E-9B
- CV-0595, **E-9C **CV-0596 and **E-9D **CV~0597.
3.0 Immediate (1) Insure the Full Length Control Rods are indicating fully inserted and that* reactor pmver is decreasing.
(2) Verify turbine trip and generator breakers opened; manually trip the turbine, then gererator, if necessary.
(3) Verify both Emergency Diesel Generators have started; (4) Trip one Mai~ Feed Pump if both are running.
(5) Trip the other Hain Feed Pump as T-avg nears 525°F.
(6) If safety injectirin has been initiated, then trip all Primary Cocilant Pumps after insuring that the Reactor has bee11 tripped
> 5 seconds. Follow up with this ~rocedurc anJ Natural
\ Circulation Procedure, ONP 21.'
p.:iov;o-o:)O 1:J-89 1
REACTOR TRIP - EOP I, Hevision 5 (7)
Insure and/or establish Auxiliary Feed\1ater flow to restore normal level in the Steam Generators.
NOTE: Steam Generator refill rate shall be:
Two operable Steam Gen~rators
- I50 gpm for Steam Generator. level ~ 15%
- IOO gpm (or less) for Steam Generator level >15% and < 25%
- unrestr*i.cted for Steam Generator level >25%
One operable Steam Generator
.;,* - 300 gpm for Steam Gener~tor level < IS%
- 100 gpm ( or less) for Steam Generator level >15% and < 25%
- unrestricted for Stea1:1 Generator level >:25%
!. NOTE: A Fecdwater Line Water Hammer ~ill he noticeable from:
i.
I
! - Intermittent banging of the Main Feedwater.Check Valves in Component Cooling Room I
!l Fluctuations in fl.ow on **FI-0736 and **FI-0737
___,./
Should a FeedwJt.er Linc Water Hammer occur, continue Feeclwater addition at the pre~cribed rates. If a Feedwater Line break should occur, proceed to EOP 6 or EOP 7 Main Steam Line Break/Main Feedv:ater Line Brc:ak Insid.e or Outside Containment.
4.0 Subsequent (1) Transfer plant power sources from station power transformers to startup transformers. Observe Sh'itchyard po1.;er conditions closely for instabilities due to the loss of plant output, which could result in a loss of the startup power source.
STATION POWEH BREAKERS OPEN BUS IA **252--101 lB *,';-;',252--20I IC "152--105 lD ;';-;152--203 lE *k,152--302 STARTUP POhER BREAKEHS CLOSE BUS IA **252--102 1B ;'d;-252--202 lC ,;-,*q52--106 )
] I) ;'.;-;152-:-202 IE k:q52--303 pa 0 JfW-000 la-[; 9. 2
REACTOR TRIP - EOP ~Revision 5 (2) Insure Steam Dump(s), ;':;"E-SOA ;',-,',CV-0781 and -:,:,cv-0782, *';;"E-SOB
- '
- cV-0779 and. ;'
- ;°>CV-0780 and/or Bypass Valve '"'"CV-OSll open and are controlling steam pressure to 900 psia.
(3) To restore Pressurizer pressure and level insure:.
(a) Maximum charging and minimum letdown flow established.
(b) Pressurizer heaters on *(proportional).
(c) Pressurizer Spray Valves closed.
(4) If Steam Generator water indication level is lost, close the associated Steam Generator Blowdown control valves (-,'d*E-SOA;
,. " - 7"-
" " / 1
/ ) c**--*-E
" 0
- son *--*-cv 0768 a* nd *"*'*c~1:v - 0770 ) *
- i\ (\ - H ,.
When level indication is restored, the blowdown valves may be reopened.
(S) Insure PORV's and/or P~essurizer Relief Valves are closed by oberving ahd verifying the following:*
(a) PORV Position Indication is closed.
(b) PORV Isolation Valves indicate closed - **MO~l042A,
-.':;':H0-10431\.
(c) Observe Relief Valve Line Discharge temperatures.
(d) Queni:h Tank level, pressure and temperature indicates normal conditions.
(e) Acoustic Monit6r Panel **EC-Sl is clear of alarms.
(6) lnsure Turbine Stop Valv~s and MSR Inlet CV's are closed,
- 'd:£-9A -,'d*CV-0594, .,.,.,*,E-9B -,':-,':CV-OS95, -.':-,':£-9C -:.--,"CV~OS96 and *;':£-9D
(7) Insure Steam Dump Valves, **E-SOA **CV-0781 and **CV-0782,
- E-SOB **CV-0779 ~nd **CV-0780 close propottionally as T-avg is reduced.
(8) On low S/G press of SOO psi insure:
(a) MSIV' s close ;';-.':£-SOA, .,.,,"CV-OS 10, ;';*£-SOB and .,.,*CV-0501.
(b) Feedwater regulating valves close, *-,"E-SOA, ;';;'*CV-0701,
- '**'*E-SOB, ;';-,';CV-0703 (observe valve position indication only). *
(c) Feedwater regulation bypass valves close ;';;'*E-SOA,
-,':-,'*CV-073S and ;';-,';£-SOB, -,';-,':CV-0734 (observe valve position iqdication only). -
pa0380.,.Q0(i};:i-89 3
m:ACTOR TRIP EOP 1, Revisio~
NOTE: Dryout of a Steam General.ot;(s) will be notic:~able fro1n:
- Decrease in Steam Generator(s) pressure below P 5 ~T of \ )
the Prim.'.lry _...**
Abnormal increase in Primary Sys Lem ternpe.rntui_*c _anc'.
pressure Increase in letdo~n flow If dryout should occur, the affected Stearn GcnerJtor ::.s tu be considered inoperable.
(9) Insure all Coc*ling Tower fans have tripped.
(10) If safety injection has actuated, reset only after-all of the following conditions are met, insuring tbat hot and cold leg ter11perature~; ;ire at least 50°F subco1;iled per At.tachr:~ent*ff2-(also posted in the Control Rborn) using all avnilabi~
instrumentation including all hot and cold leg ternpe:catures i several incor~ thermocouples, PCS Pressure.
(a) The cans.~ of the low-pressure cond:i_tinn is known and corrected.
(b) The re.actor is shutdm11n and 1-ii] 1 remain sbntdor.n1.
(c) I'n:ssur:i.zcr level is grec1ter than 20;~ and is !'eturning to norm<ll.
(d) T-avg is stable or inn.-~asing and is less than Sif5°f.
(0) Pressurizer pressure is grcjter than 1700 psia aud i~
returning to normcl.
H after a resP.t of the Safoty Injection System 50°F subcoolin['.
cannot be maintained, restart the High Pressure Safety_
(11) If st:rnctby power is avc;ilabJ.e 8nd st2ble sh1.1td!)hT1 Cliuditions arc: assured, siiutdmm one En:~rgency Diesel Gcnc:rator. Shutd0*.*-'ll the s.:~cond E111ergc~ncy Dies.el Gener.::: tor a Her the Main- T11rbine is on tun1i11g ge2:c.
(12) AfL:.r sc.f f.'.ty injection has been reset anc1 equipment_ returned to post. SlS actu.'.ltion, per Attachment ffl, and plant condi.Lions are stable, restart the PCP:s per SOP 1.
(13) As makeup is -needed to ;'**T-2 (Condensate Storc;ge Tank) for Au:<i.liary I'c:cJ,._;atcr Pumps, .rcfor to SOP 12.
Complete thi!; p1*c1cedu.re by CXf'("U U.ng Emergency si-,1.1LdO\\Ti.
Checklist G CL 10. -
µao:si\Ci-*00(1 l J-89 4
e
- REACTOR TRIP - EOP 1, Revision 5 NOTE: Dryout o!: a Steam GeneraLor(s) will be noticeable £ro1a:
- Decrease in Steam Generator(s) pressure bt~~-o"* :; 5 /:11 ,)f the PrimJry Abnormal increase in Primary System tempe.::atui.-c. anc'.
pressure Increase in .let:lown flow If dryout should occur, the affected Stearn Gt!nerator is to be considered inoperable.
(9) Insure all Coc*ling To-;.:u. fons have tripped.
(10) If safety injection ha~ actuated, reset only after-all of the following conditions are met, iusuring that hot and cold *leg
- teruperature~; !ire at least 50°1:' snbcooled pee A;..:.tachn*ent fft2 (also posted in the Control Room) using all availablE instrumentation including all hot and cold leg tempefature:-;,
several incore ther~ocouples, PCS Pressure.
(a) The cans.~ of the low-pressure COI\d:i.tion is known and corrected. *~
(b) The n>:<ictor is shutdnwn. and 1-iil 1 rerna.in shutdown.
- (c) ?n::ssu1:izer level is greciter 'than 20'1o and is returning to normal.
(d) T-avg is stable or incr~asing and is less than Si1:i 0 f.
( c-) Pressu.rizer pressure, is greJter than 1700 psia *and i~
returning to normal.
H after a resP.t *of the Safoty, Injt:ctfon Sys tern 50°F subccolin~',
canrl'Ot be maintained'* restart the High Press are Safei.:.:r Injection System.
(11) If st:mdby power is available anJ st2ble shutdcv;n Cl1udil:ions arc assured, sliuLdown 0110 l:n;ergecicy Diesel GenCl'.'oltC*r. Shutd0 :.'ll 1 the second Emergency Diesel Generator after ~he Hain.Turbine is on turnirig gear:
(12) AfL:r sc.fety injection has been re~et ancl ~qui.pment_ retumed to post s1s* actu.'.ltion, *per Attachment /fl, and plaut condi.Lions al*c
- stable, r~start the PCP 1 s per SOP 1 .
(13) .4.s makeup is nee.dP.d to i;-1.1-2 (C9ndcnsate Stonge Tank) for Au:<iliary Fc:cdwater Pump.s, refer to sop* 12.
(ltf) Complete thi!> prncec!ure by CXE cut.ing Emci*g~ncy SLr.1tdo\>r1 ChecklisL GCLlO .. * ... ,,
.. ~
