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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18017A9271999-10-21021 October 1999
Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05
ML18017A8531999-08-26026 August 1999
Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations
ML18016B0521999-08-0404 August 1999
Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits
ML18016B0451999-08-0202 August 1999
Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements
ML18016B0101999-07-0909 July 1999
Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants.
ML18016B0131999-07-0909 July 1999
Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10
ML18016A9911999-06-15015 June 1999
Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests)
ML18016A9781999-06-0202 June 1999
Proposed Tech Specs Revising TS 6.5 & TS 6.8
ML18016A8401999-02-26026 February 1999
Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.)
ML18016A7701998-12-23023 December 1998
Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.'
ML18016A9341998-12-15015 December 1998
Rev 11 to ODCM, for Shnpp
ML18016A7531998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs
ML18016A7561998-12-0707 December 1998
Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses
ML18016A7591998-12-0707 December 1998
Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks
ML18016A6571998-10-28028 October 1998
Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors
ML18016A6261998-10-15015 October 1998
Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases
ML18016A6051998-10-0101 October 1998
Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09
ML18016A5941998-09-23023 September 1998
Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut
ML18016A5461998-09-0101 September 1998
Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks
ML18016A5411998-08-27027 August 1998
Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements
ML18016A5381998-08-27027 August 1998
Proposed Tech Specs,Revising Section 6.0, Administrative Controls.
ML18016A5311998-08-24024 August 1998
Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE
ML18016A4301998-05-15015 May 1998
Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants
ML18016A4021998-04-24024 April 1998
Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays
ML18016A3881998-04-13013 April 1998
Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power
ML18016A3481998-03-12012 March 1998
Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months
ML18016A3051998-01-29029 January 1998
Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval.
ML18022B0351998-01-26026 January 1998
Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval.
ML18016A4131997-12-18018 December 1997
Rev 10 to ODCM for Shearon Harris Nuclear Power Plant.
ML18016A2591997-12-16016 December 1997
Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed
ML18016A2241997-10-29029 October 1997
Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS
ML18012A8121997-06-12012 June 1997
Proposed Tech Specs 6.0 Amending Administrative Controls.
ML18012A7991997-05-23023 May 1997
Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators
ML18012A7861997-05-16016 May 1997
Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler
ML18012A6361997-04-23023 April 1997
Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3
ML18012A5811997-03-17017 March 1997
Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances
ML18022B0041997-03-14014 March 1997
Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2
ML18022B0071997-03-10010 March 1997
Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems
ML18012A5361997-02-27027 February 1997
Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes
ML18012A5351997-02-21021 February 1997
Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition
ML18012A5281997-02-21021 February 1997
Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability
ML18012A5311997-02-18018 February 1997
Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves.
ML18012A5101997-02-13013 February 1997
Proposed Tech Specs 3.2.3 Re Rated Thermal Power
ML18012A5011997-02-0606 February 1997
Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability
ML18012A4961997-01-29029 January 1997
Proposed Tech Specs 3/4.0 Re Applicability
ML18012A4641997-01-10010 January 1997
Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements
ML18012A4531996-12-30030 December 1996
Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits
ML18012A4161996-10-31031 October 1996
Proposed Tech Specs Re Ultimate Heat Sink Level & Temp
ML18012A3981996-10-0808 October 1996
Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event
ML18012A3721996-09-18018 September 1996
Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18016A9341998-12-15015 December 1998
Rev 11 to ODCM, for Shnpp
ML18016A3051998-01-29029 January 1998
Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval.
ML18022B0351998-01-26026 January 1998
Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval.
ML18016A4131997-12-18018 December 1997
Rev 10 to ODCM for Shearon Harris Nuclear Power Plant.
ML18011A8031994-08-31031 August 1994
Rev 5 to Odcm.
ML18011A5631994-07-0101 July 1994
Rev 4 to Odcm.
ML18011A1111993-07-0707 July 1993
Rev 8 of ISI Program ISI-203, ASME Section XI Pump & Valve Program Plan.
ML20044G6131993-05-11011 May 1993
Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews.
ML18011A1181993-01-0606 January 1993
Rev 3 to Odcm.
ML18010A8491992-09-23023 September 1992
Change 1,Rev 5 to Vol 3,Part 9 of Plant Operating Manual Procedure OST-1825, Safety Injection:Esf Response Time, Train a 18 Month Interval on Staggered Test Basis Mode 5 - 6.
ML20116D2961992-08-31031 August 1992
Rev 2 to Nuclear Generation Group Manual 305-05, Prioritization Process
ML18010A8361992-08-28028 August 1992
Change 2,Rev 2 to Vol 4,Part 7 of Plant Operating Manual Procedure MST-I0080, RCS Wide Range Pressure P-0402, Reflecting Case Level Change to Case III
ML20044G6141992-07-31031 July 1992
Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations.
ML18010A8371992-05-0404 May 1992
Rev 3 to Vol 3,Part 9 of Plant Operating Manual Procedure OST-1083, ESFAS Train 'A' Slave Relay Test 18 Months Interval Modes 5 & 6.
ML18010A5471991-12-18018 December 1991
Rev 3 to Odcm.
ML18005B0231989-08-29029 August 1989
Rev 3 to Odcm.
ML18005A9061989-03-27027 March 1989
Rev 6 to Vol 6,Part 7 to Inservice Insp Program ISI-203, ASME Section XI Pump & Valve Program Plan.
ML18005A3461988-02-26026 February 1988
Rev 1 to Plant Program Procedure PLP-108, Environ Qualification Program (10CFR50.49).
ML18005A3441988-02-18018 February 1988
Rev 1 to Technical Support Mgt Manual TMM-402, Equipment Qualification Coordinator Responsibilities. Related Info Encl
ML18005A3641988-02-18018 February 1988
Rev 4 to Technical Support Mgt Manual TMM-104, Determination of Technical & QA Requirements for Procurement Document.
ML18005A3521988-02-11011 February 1988
Rev 0 to Ned Design Guide DG-VIII.19, Shearon Harris Equipment Qualification Documentation Review.
ML18005A3471988-02-10010 February 1988
Rev 0 to Ned Design Guide DG-VIII.34, Preparation & Control of Shearon Harris Environ Qualification Master List.
ML18005A3371988-01-29029 January 1988
Rev 14 to Coporate QA Dept Procedure Cqad 80-1, Procedure for Corporate QA Audits.
ML18022A6141988-01-28028 January 1988
Inservice Insp 10-Yr Plan of Shearon Harris Nuclear Power Plant Unit 1, Vols 1 & 2
ML18005A3581988-01-13013 January 1988
Rev 0 to Maint Mgt Manual MMM-025, Maint Environ Qualification Program.
ML18022A7961987-10-31031 October 1987
Master Plan for Wakesouth Regional Airport Phase I.
ML18005A3391987-09-24024 September 1987
Rev 1 to Operations Qa/Qc Procedure OQA-201, Surveillance Program.
ML18005A3431987-09-0101 September 1987
Rev 4 to Administrative Procedure AP-600, Plant Change Request Initiation.
ML20235G5241987-08-28028 August 1987
Revised Plant Emergency Procedures,Including Rev 2 to Change 5 to PEP-101, Emergency Classification & Initial Emergency Actions, & Rev 2 to PEP-221, Technical Analysis Manager. W/One Oversize Drawing
ML18005A3481987-08-24024 August 1987
Rev 8 to Mod Procedure MOD-103, Engineering Evaluations.
ML18005A3501987-06-23023 June 1987
Rev 5 to Administrative Procedure AP-014, Criteria for Qualified Safety Reviewers.
ML18005A3511987-04-24024 April 1987
Rev 0 to Administrative Procedure AP-618, Justification for Continued Operation.
ML18022A5011987-04-14014 April 1987
Rev 1 to Procedures Generation Package. W/Emergency Operating Procedures Writing Guide,Verification & Validation Program & 870414 Ltr
ML18005A3651987-02-12012 February 1987
Rev 1 to Technical Support Mgt Manual TMM-110, Receiving Packaging,Storage & Maint Requirements for Spare Parts,Matl & Components. Equipment Qualification Master List & Other Related Documents Encl
ML18005A3421986-12-18018 December 1986
Rev 1 to Administrative Procedure AP-610, Processing Vendor Recommendations,Vendor Manual Revs & Equipment Technical Info.
ML18022A4991986-12-0909 December 1986
Change 1 to Rev 1 to Emergency Procedure PEP-401, Record Keeping & Documentation, Deleting Prohibition of Use of Felt Tip Pens & Clarifying Type of Facility & Equipment Records to Be Maintained
ML18005A3531986-10-27027 October 1986
Rev 1 to Administrative Procedure AP-609, Review of Incoming Nrc/Inpo Correspondence.
ML18005A3571986-10-24024 October 1986
Rev 1 to Administrative Procedure AP-026, Corrective Action Program.
ML18022A4691986-07-0303 July 1986
Rev 0 to Procedure 1-9103-S-27,Turbine Overspeed Trip Test.
ML18004A2861986-05-20020 May 1986
Change 3 to North Carolina Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Including Revs to Annex E, Emergency Broadcast Sys Procedures for Shearon Harris Nuclear Power Plant Operational Area.
ML20212C0611986-04-0707 April 1986
Rev 2 to Operations Mgt Manual Procedure OMM-006, Emergency Operating Procedure Writers Guide
ML18005A3561986-03-20020 March 1986
Rev 1 to Administrative Procedure AP-031, Operational Experience Feedback.
ML18019A5891986-02-14014 February 1986
Revised Plant Emergency Procedures,Including Rev 2 to PEP-223, Radiological Control Manager & Rev 1 to PEP-103, Site Emergency Coordinator - Technical Support Ctr. W/One Oversize Drawing
ML18019B0451985-12-17017 December 1985
Rev 1 to Plant Program Procedure PLP-610, Equipment Identification & Numbering Sys.
ML18003B2961985-12-14014 December 1985
Rev 3 to Technical Support Mgt Procedure TMM-104, Determination of Technical & QA Requirements for Procurement Documents.
ML18003B2921985-11-21021 November 1985
Rev 2 to Maint Mgt Procedure MMM-020, Operation Testing, Maint & Insp of Cranes & Matl Handling Equipment.
ML18003B2891985-11-20020 November 1985
Rev 1 to Procedure CRC-827, Post-Accident Sample Boron Analysis by Fluoroborate Specific Ion Electrode.
ML18019A5861985-11-0404 November 1985
Vol 6 of Part 7 of Plant Operating Manual,Consisting of Rev 1 to Inservice Insp Program ISI-203, ASME Section XI Pump & Valve Program Plan.
ML18003B2951985-09-0909 September 1985
Rev 2 to Procurement & Matl Control Procedure PMC-001, Procurement & Cataloging of Parts,Matl,Equipment & Svcs.
ML18019A3921985-08-30030 August 1985
Rev 2 to Inservice Insp Program ISI-201, ASME Preservice Insp Program Plan (Except Reactor Vessel).
1998-12-15
[Table view] |
Text
EOPHP3 CAROLINA.POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 3 PART'.
PROCEDURE'YPE':. EMERGENCY OPERATING PROCEDURE'EOP)
END PATH PROCEDURE (EPP)
NUMBER:, EOP-EPP- ~
e.'EACTOR, TRIP'ESPONSE TITLE',
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LIST OF EFFECTIVE PAGES
~Pa e Revision No.
1 through 13. 0 EOP-EPP-4 Rev; 0 Page 2 of 13
EOPHP3 REACTOR TRIP RESPONSE
~"
~
i31.0
~ PURPOSE
.This procedure provides the necessary instructions to stabilize and control the plant folloving a reactor trip vithout k safety injection..
2.0 OPERATOR ACTIONS'.
CAUTION If SI actuation.. occurs't= any. time, immediately go to PATH>>l,, entry point A.
NOTE" Fo1dout= D should: be. open EOP-EPP Rev.. 0 Page 3 of l3
1 1 4 I
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EOPHP3 REACTOP, TRIP RESPONSE
- Instructions Res onse Not Obtained
- 1. Check RCS AT OR TRENDING TO 557 F'F Temperature STABLE S temperature less decreasing, THEN:
t hen 557'F and
- a. Stop- dumping-steam.
b IF'ooldown continues, THEN contro3 total feed flow.
Maintain total feed flow, greater than. 400 GPM or 192 KPPH until level greater than 10K in at'east.
one S/G.
c: IF'ooldown: continues, THEN close MSIVs and bypass valves.
IF: temperature. greater than 557'F and increasing;, THEN:
II o 'ump steam to condenser.
OR' Dump steam. using S/0 PORVs.
EOP.-EPP-4 Rev.. 0. Page 4 of 13
~ ~
~ '
EOPHP3 IC REACTOR TRIP RESPONSE Verify At Least One RCP - RUNNING Perform the following:
o Place steam dump in pressure control mode.
o Dump steam to establish natural circulation.
- 3. Check Feed System Status:
a; Check. RCS'emperature: a- Continue. with step 4. WHEN RCS LESS'HAN, 564'F temperature less than 564'F, THEN do steps.3b and c.'
Verif'y. feed regul'ator va1ves:
CLOSED, c.. EstabTfsh, FR'ypass EXo~ to c. Establish; AFV'low to S'/Gs..
S:/Gs
~
P ~ e EOP-EPP-4'ev, 0 Page 5 of 13
%I i+ t% It R lt' l
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EOPHP3 REACTOR TRIP RESPONSE
- 4. Verify All Control Rods Fully IF two or more control rods NOT fully Inserted. inserted, THEN emergency borate as follows:
- a. Start a boric acid pump.
- b. Align boric acid to CSIP suction (listed in order of preference).
o Open 8104 (Emergency'oration)
OR o Open FCV-113A (Boric Acid to Blender) and..open FCV-113B (Blender Outlet to CSIP suction)
OR 0 ~
Open. FCV-113K (Bpric Acid to Blender) and open FCV-1.14A (Blender, Outlet to, VCT) c;. Verify boric. acid. flow to CSIP
~
suction;.
Verify CSIP flow to RCS.
EOP-EPP-4 Rev. 0 Page 6 of 13
~ ~
@type ~t a P
k
~ 'OPHP3 REACTOR TRIP RESPONSE
- 5. Check PZR Level Control: ,'
a., Level GREATER THAN 17K a.. Perform .. following:
- 1) Verify letdown isolation.
- 2) Verify PZR heaters secured.
- 3) Control charging to restore PZR level greater than- 17K.
b Ver'ify charging and. letdown.
IK SERVICE.
c.. Level STABLE AT OR; TRENDING c., Control'harging and letdown to TO 25K maintain PZR level at 257.'.
6: Check PZR Pressure. ControT a Pressure GREATER THAN'881. a Verify SI actuation. AND go to PSIG: PATE-1:, entry- point A.
EOP-EPP Rev 0 Page 7 of 13
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EOPHP3 REACTOR TRIP RESPONSE
'b., Pressure STABLE AT'R b. IF pressure LESS THAN 2235 PSIG TRENDING TO 2235 PSIG and decreasing, THEN:
- 1) Verify PZR PORVs closed.
IF. any PZR PORV can NOT be closed, THEN close its block valve. ~
- 2) Ver'ify PZR spray valves closed~
/
IF valve(s) can NOT be closed, THEN stop RCP(s) supplying failed spray valve(s).
- 3) Verify'ZR heaters energized.,
IF- pressure greater. than 2235 PSIG and. increasing;. THEN:
- 1) Verify PZR heaters off.
- 2) Control pressure using-normal'ZR. spray IF NOT available: AND letdown, in service,, THEN use. auxiliary spray IF'OT, THEN use one PZR; PORV; EOP-EPP-4 Rev. 0 Page 8 of 13
4
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4
I EOPHP3 C
REACTOR TRIP RESPONSE Ig 7.. Check S/G Levels:
- a. Narrow. range level GREATER a. Maintain total feed flow greater THAN 10X than 400 GPM or 192 KPPH until narrow range level greater than 10X'n at least one S/G.
b.- Control. feed flow to maintain. b. IF narrow range. level in any S/G narrow: range; level'etween.. continues to increase, THEN stop 10X'nd, 50X; feed flow. to that S/G.
EOP-EPP-4 Rev; 0 Page 9 of 13
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~ EOPHP3 REACTOR TRIP RESPONSE 0,
- 8. Verify All AC Busses ENERGIZED Perform the fol3owing as necessary:
% ~
BY OFFSITE POWER
- a. Verify EDGs have started.
- b. Verify EDGs have assumed the proper loads.
c., Verify turbine DC lube oil pump and air'ide seal oil backup pump are: running.
'.. Verify adequate EDG capacity and load the following equipment on the. EDGs:.
- 1) One instrument air
.compressor 2') Battery chargers
- 3) PZR. heaters,. as needed.,
e., Determine the cause of the loss of offsite power., If due to a failure- of the: startup transformer,. request; assistance from. maintenance crews to restore 4
power from: either the main or spare startup transformer.. If the loss'f power is the result of a loss, of; grid, obtain assi'stance-.from. the Load Dispatcher..
$)
9.. Transfer C'ondenser steam, Dump to IF condense< NO+" available,. THEN use ~
le Pressure Control Mode. S/G-'ORVs'.
EOP-EPP-4 Rev. 0 Page 10 of. 13
Ap 4 ~+<a ~ ~ M II
i'EACTOR gOPHP3 TRIP RESPONSE e,~C~'
CAUTTON On natural circulation, RTD bypass temperatures and associated interrocts will be inaccurate..
NOTE: RCPs shoul'd be run in order of priority to provide normal PZR spray.
10.. Check. RCP Status AT LEAST ONE Try to start one RCP:
RUNNING a Establish conditions for running RCP(s) using OP-100, "REACTOR COOLANT SYSTEM," while. continuing with. this, procedure..
b 'tart'CP(s)
IF at. least one- RCP can NOT be stamped., THEN verify natural c&culation from; trended values:
o RCS'ubcooling GREATER THAN 25 F o Steam; pressure. - STABLE OR DECREASING ..
o RCS: hot, leg temperature STABL'E OR DECREASING;
- o. Core exit T/Cs STABLE OR DECREASING o RCS.cold: leg- temperatures TRENDING'O OR. AT SATURATION TEMPERATURE FOR'TEAM PRESSURE.
~ 4w.
IF natur~ circulation THEN increase. dumping NOT'erified, steam.
EOP-EPP Rev.. 0 Page. Ll of 13
C II7ICE 4
. ~
EOPHP3 REACTOR TRIP RESPONSE I
- 11. Check If Source Range Detector Should Be Energized:
- a. Check intermediate range flux a. Continue with step 12. WHEN flux
- -10 LESS'HAN 10 AMPS less than 10 AMPS, THEN do steps 10b and c.
- b. Verify source range detector's ENERGIZED c.. Transfer nuclear recorder'o source. range scale.
- 12. Shutdown. U Equipment=
0: Stop; bottr. heater drain. pumps
- o. Stop.. condensate pump, condensate. booster pump and:
EW'ump='as; required.
o Isolate BTRSerify turbine generator goes.,
on-. the turning: gear; one-minute after zero, speed. alarm.
is: received-:
o, Secure. the. MSRs o Stop DEK pumps EOP-EPP-4 Rev.. 0 Page 12 of 13
Cigar
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\
REACTOR TRIP RESPONSE
- 13. Maintain Stable, Plant Conditions:
- a. PZR pressure - AT OR TRENDING TO 2235 PSIG b.. PZR level AT OR TRENDING TO 25X' S/G'arrow.range levels BETWEEN 10X: AND 50X'.
RCS average temperature- AT'R TRENDING'O 557'F 14- Go: To Appropriate Pl'ant Procedure:
I As; Determined'. Below."
a Perform:
OMM-004-"POSZ'RIP'/SAZEGUARDS-REVIEW" b 'heck plant. status RCS b.,'o to GP-'04, "RECOVERY FROM' COOLDOWN: REQUIRED REACTOR'RIP," and return to power operation..
c Check RCP'tatus A'Z LEAST'NE c.. Go to EPP-5, "NATURAL CIRCgLATION RCP AVAIMKE. COOLDOWN," step 1..
d'tart= RCP(s)'sing, OP-100'.
"REACTOR COOLANT: SYSTEM ."'
Go to. GP'OT"NORMAL
" PLANT'OOLDOWN n 0- FINAL PAGE Pane 13 of 13
' ~ ~
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~
i II
EOPHP3 FOLDCUTS FOLDOUT D
'c(
- a. SI ACTUATION CRITERIA detente SI end go to PATH-1, entry point A f ElTHER co"..d-.'or. lie."'c belov occurs:
- 1) RCS Subcoollng LESS THAN 25'F [30'F]
- 2) PZR Level CANNOT BE MAINTAINED GREATER THAN 10'~ [45X]
- b. LOSS OF EMERGENCY'OWER Go to EPP>>.1, "LOSS OF AC POWER TO lA-SA AND 1B-SB BUSSES," step 1 'f emergency busses 1A-SA and 1B-SB are deenergzied.
EOP-FOLDOUT Rev. 0 Page 7 of 13
0
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A.
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4p
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D G PATH 1 4 I I IGVZSICN
~ MARCH HA>>II~ MICLSAR MSGR PLANT W IV stfaurua I I ~
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~I I M 0 I FOLDOUT R 4 RCP TRIP CRITEIIIA TRIP ALL RCP IP OOTN CO>>II TIIMS LISTED OELolt AIM IRT I CSIP AT LEAST ua HlatilMI
- 2. Rcs pREsslAM - LEss THAN 1500 psla c lsoo psliD 0 Sl TuailNAT ION CR! TERIA ao ro Epp-0 si vsRI owvNM lr ALL cctofrfcfa LISTED SZLI>> occur IIM - fatrATER ftfAN a P cso rr I I I 2 NARRON RAMM LEVEL IN Ar LEAST Ofa IHTACT S/0 " SIMATER IWI loa C40Xl fl 4 M TOT>>. PEEO PLOU To INTACT 0/0 . OREI TEli TWIN 400 OPtl 102 RPPH
- 5. RC5 PRE55UHE - STASLE CR INCREASII43 OR 4, I'ZR LEVEL MKIITEN THAH lait I4010 t>> C COLO LEO RECIRCILATIIM SIIITCHOVPZI DUTEIIION 00 To ZPP I 0 TRANSI'ER To COLO LES IMCIRCIEATICN ~ STEP I IP RitST LEVEL OECREIISES To LESS THAH LATER 0 SECotOARY INTESRITY CRITEIIIOH
~ I 00 To EPP 14, PISLTEO 5TEAII 0ENEIIATOR ISOLATICN, STEP I OECIIEASES IN AN LliCONTIEELEO IIAMMR Oi HAS COHPLETELY OEPIMSSLRIZEO It'NY 5/0 PRESMIM wia 'of OEEH 150uiTES ZZZZ E LOSS CP EtERSENCY POIIBI 00 To EPP 1 LOSS CP AC POIIER To IA.SA A141 IS 50 SUSSES STEP I Il ENEROTNCY SIMSES iA.SA>>D ia-sa>>M CEENERarzso Hvlrl/0 SSTR ISOLATlaa 00 To EPP-10 SOTR ISOLATION, STEP I H ANY S/0 LEVEL INCREASES IH AN UNCONTIIOLLEO IIAtosa OR ANY 0/0 HAS A!MOMIAL IIAOIATICN LEVELS nt Hi I~ I E 14 N
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IM EP 12 10 II IM I IHI
~4 THIS PROCEDURE CLRRENTLY DOES NOT CONTAIN ALL NECESSARY INPOIOIATTON, REOUIRED IHPOISMTION MIST OE TILLED IN PRIOR TO PLANT TUEL LOAD G
