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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction RBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 1999-07-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20076K9161994-10-27027 October 1994 Updates to IST Pump & Valve Program Manual ML20059A8501993-12-23023 December 1993 Near-Term Performance Improvement Plan ML20128D9221993-01-29029 January 1993 Rev 6 to Pump & Valve Inservice Testing Plan for River Bend Station First 10-Yr Insp Interval ML20045E0311992-08-19019 August 1992 Change 92-01 to Rev 3 to RSP-0008, Odcm. ML20114D0711992-08-19019 August 1992 Rev 3 to Odcm ML20086G8411991-10-0202 October 1991 Rev 5 to Inservice Insp Plan for River Bend Station - Unit 1 ML20082M0061991-08-0909 August 1991 Rev 4 to RWS-0204, Radwaste Processing Control Program RBG-35-380, Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl1991-07-26026 July 1991 Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl ML20029B7841991-03-0606 March 1991 Station,Inservice Insp Plan,Summary Rept Refuel Outage RF-3 Second Period,First Interval, Vols 1 & 2 ML20070U7721991-02-26026 February 1991 Rev 4 to River Bend Station Inservice Insp Plan (First Interval) ML20245F0101989-04-24024 April 1989 Rev 2 to Offsite Dose Calculation Manual ML20114B7411989-03-0808 March 1989 Rev 5 to Procedure RWS-0304, Radwaste Handling & Control ML20245F0041989-02-14014 February 1989 Rev 3 to Offsite Dose Calculation Manual Procedure ML20154C9851988-08-16016 August 1988 Rev 3 to Inservice Insp-First Interval ML18053A7101988-03-22022 March 1988 Rev 5 to Pump & Valve Inservice Testing Plan,First 10 Yr Insp Interval. W/880422 Ltr ML20238C3651987-08-13013 August 1987 Rev 1 to Station Operating Procedure RSP-0008, Offsite Dose Calculation Manual Procedure RBG-26506, Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid1987-07-29029 July 1987 Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid ML20235Y0591987-07-16016 July 1987 Rev 2 to Radwaste Processing Control Program RBG-26044, Rev 2 to Inservice Insp Plan - First Interval1987-06-0202 June 1987 Rev 2 to Inservice Insp Plan - First Interval ML20114B7281987-05-14014 May 1987 Rev 3 to Procedure RWS-0307, Radwaste Segregation RBG-25841, Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual1987-04-30030 April 1987 Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual ML20114B7311987-03-16016 March 1987 Rev 2 to Procedure RWS-0207, Radwaste Shipping Criteria ML20209G3121987-01-0202 January 1987 Rev 3 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20214T6231986-09-11011 September 1986 Revised Emergency Plan Implementing Procedures,Including Rev 5 to EIP-2-007, Protective Action Recommendation Guidelines & Rev 4 to EIP-2-024, Offsite Dose Calculations Manual Method ML20214N6811986-08-0606 August 1986 Rev 2 to Pump & Valve Inservice Testing Plan,First 10-Yr Insp Interval ML20207E8711986-07-0202 July 1986 Vol 1 to Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20206J1501986-06-20020 June 1986 Rev 4 to River Bend Station Unit 1,Preservice Insp Plan, Final Update ML20238C4141986-05-18018 May 1986 Rev to Nonradioactive Oil/Hazardous Matl Spill Prevention, Control & Countermeasure Plan ML20155G5391986-02-26026 February 1986 Station,Emergency Response Exercise Manual, Evaluated Exercise RBG-22-117, Rev 3 to Offsite Dose Calculation Manual1985-09-16016 September 1985 Rev 3 to Offsite Dose Calculation Manual ML20135A6331985-06-27027 June 1985 Revs to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan, Replacing Pages 4 & 5 & App F RBG-21363, Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program1985-06-21021 June 1985 Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program ML20135A9211985-06-17017 June 1985 Rev 1 to OSP-0007, Preparation of Operations Sections Procedures ML20125D2751985-06-10010 June 1985 Updated Rev 1 to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan ML20129E9531985-06-0606 June 1985 Rev 2 to Station Operating Procedure ADM-0022, Conduct of Operations ML20117P4831985-05-30030 May 1985 Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval RBG-21545, Rev 2 to River Bend Station Offsite Dose Calculation Manual1985-05-27027 May 1985 Rev 2 to River Bend Station Offsite Dose Calculation Manual ML20128E8881985-05-17017 May 1985 Revised Program Plan for Tdi Standby Diesel Generators ML20117P1431985-05-13013 May 1985 Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage RBG-21-165, Rev 1 to, River Bend Station Offsite Dose Calculation Manual1985-04-24024 April 1985 Rev 1 to, River Bend Station Offsite Dose Calculation Manual ML20129E9591985-03-27027 March 1985 Rev 1 to Station Operating Procedure AOP-0001, Reactor Scram ML20112G4641985-01-0707 January 1985 Offsite Dose Calculation Manual ML20112G4491985-01-0707 January 1985 Rev 0 to Procedure RWS-0204, Process Control Program 1999-01-08
[Table view] |
Text
" , *f4- ?
o RIVER BEND STATION I
, t r- APPROVAL SHEET j l STATION OPERATING PROCEDURES i
NO. A0P-0001 TITLE REACTOR SCRAM ~-
l
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SAFETT RELATED TES X NO] 1 TECHNICAL REVIEW REQUIRED TES X NO ,.: .- l REV. , PAGES INDEP. TECH.
~
NO. ' ISSUED REVIEW REVIEW APPROVED BT
. .EFFECT
]{'1 SIGNATURE /DATE SIGNATURE /DATE SIGNA'ITJRE/DATE ~~! DATE 0 1 THRU 5 8I Md 10/18/84 v 4..
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1 1 THRU 6 7-24 8 03/27/85 l p- 3/22/95 Z97W .%$
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RECEIVED
. MAR 281985
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C'!RC 8507170132 850709 (DR ADOCM 05000458 PDR !
r I i SON-003
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l REACTOR SCRAM l
l 1
8l l TABLE OF CONTENTS l
l l SECTION PAGE NO. l l-l l 1.0 PURPOSE / DISCUSSION 2 l 1
l l 2.0 SYMPTOMS 2 l 1
I
.l 3.0 AUTOMATIC ACTIONS 3 l l
1 3 . .. l . 4.0 IMMEDIATE OPERATOR ACTIONS 4
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.l 5.0 SUBSEQUENT OPERATOR ACTIONS 5 l 1
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I I l 1I I I I i N/A l N/A ll A0P-0001 l REV - 1 l PAGE 1 0F 6 l 1 I ll l l l
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' J. I I l 1.0 PURPOSE / DISCUSSION l
.l 1-1.1 To provide instructions for the operator in the event of a 8
l ' l l reactor scram. I I l l
1.2 This procedure may interface with the Emergency Plan and l I Emergency Operating Procedures. l I I l 1.3 A reactor scram results in the rapid, simultaneous insertion of I l all withdrawn Control Rods. The Reactor Protection System I I automatically initiates a Reactor Scram if an unsafe plant i I condition exists. I 1 I i 1.4 The Operator. "At-The-Controls" will manually initiate a reactor I l scram whenever: I
- I l- 1.4.1 A scram setpoint is exceeded and an au.omatic scram did l l not occur or l l I
, l 1.4.2 It is determined that the plant is in a Unsafe Condition l l not covered by Automatic Actions and a manual reactor l l scram will allivate the consequences of this condition. l
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l l' l 2.0 SYMPTOMS l l I I 2.1 Reactor scram trip annunciator. l .
I I l 2.2 Eight white scram solenoid valve lights are out. I 2.3 Indication of rods inserted.
I I l 2.4 Reactor power rapidly decreasing. I I I l 2.3 One or more of the following scram setpoints are exceeded: l
. I l
] 2.5.1 CRD instrument volume high water level trip (equal to or l l less than 36% of full scale). I i l I l 2.5.2 Main Steam Line High-High Radiation (3 x normal). I I I I 2.5.3 Main Steam Line Isolation Valves Closure (equal to or less l I than 8*. closed). I i l i 2.5.4 Reactor Vessel High Pressure (1065 Psig). I I I I 2.5.5 Reactor Vessel Low Water Level (LEVEL 3). I I I I 2.5.6 Reactor Vessel High Water Level (LEVEL 8). l l .
l l 2.5.7 Turbine Stop Valve Closure Trip (equal to or less than 5% l l closed). I I I l 2.5.8 Control Valve Fast Closure Trip (equal to or greater than I 8 l I
I 530 Psig). I I
I I I il l I I i l N/A I N/A ll AOP-0001 1 REV - 1 I PAGE 2 0F 6 l l l l ll l 1 I !
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I l 2.5.9 Non-CoincidInt; SRM's High-High (5 x 10ES) or INOP. '
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'l 2.5.10 Intermediate Range Monitor Neutron Flux-High (120 l l
divisions of full scale) or INOP. l l
1 l 2.5.11 Average Power Range Monitor Neutron Flux-High and not in l
.l Run mode (15% of Rated Thermal Power) or INOP. l l I l 2.5.12 Average Power Range Monitor Thermal l'ower Trip in Run mode l 3
l (.66W + 48%) or (118%) or INOP. l l
l l 2.5.13 Drywell High Pressure (1.68 Psig). l l
I 4
l 2.5.14 Manual Scram or Mode Switch in SHUTDOWN. l l
l l 3.0 AUTOMATIC ACTIONS
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l l 3.1 All control rods insert to position 00, scram valves de-energize, l l backup scram valves energize and scram discharge volume vent and l l drain valves close.
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l 3.2 I If reactor water level decreases to Level 3 the Reactor Feedwater l l Level Controller will automatically increase its setpoint by 50% [.
l to approximately 54" for 10 seconds. The setpoint will then be l l automatically reduced to 50% of normal to approximately 18"-and ~l l stay there until the SET POINT SETDOWN RESET pushbutton is l l pushed. ,
l l
3.3 I The Recirculation Pump.s.will. shift to low speed and the loop flow l l
l controllers will shift to manual on any of the following signals: l @.
l l
l 3.3.1 Less than 30% Feedwater flow (15 second time delay).
l 1
l l 3.3.2 Reactor water level below level 3. l l
3.3.3 I l- Main Steam Line to Recire Pump Suction differential l l temperature less than 8*F (15 second time delay). l l
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l 4.0 IMMEDIATE OPERATOR ACTIONS l
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CAUTION l l Steps 4.1 and 4.2 must be L l l l done sequentially per IEN l l l l 83-42. l l l 1 I I I I l 4.1 ARM and DEPRESS all four manual scram pushbuttons, RPS Div 1, 2, l l 3, 4 on panel 1H13-P680. l l
1 l 4.2 Place the Mode Switch to SHUTDOWN. l l
I l 4.3 Verify all control rods are fully inserted by depressing RAW DATA I l and ALL RODS pushbuttons. If all rods are inserted, the core
' l l display for all rods will be blank and a full-in green light will l l be displayed. l l
I l 4.4 Verify power decreasing as indicated on the APRM's. l l
l 4.5 l Verify the Feedwater System is operating to restore reactor water l l level. . -
l l
1 l 4.6 Verify reactor pressure is being maintained by either the turbine l '
l bypass valves or safety relief valves. l 8
l -
l l 4.7 Manually downshift the'.reacior.recire pumps by simultaneously l l depressing both " TRANSFER TO MG" pushbuttons. l l
- 1 l 4.8 Verify Turbine / Generator trips en reverse power or trip manually. l l
I l 4.8.1 Verify Generator Output Breakers open 1WC-20635 a*.td 1WC- l l 20640.
l 1
I l 4.8.2 Start Turning Gear Oil Pump and Motor Suction Pump.
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. -l 4.8.3 Verify Exciter Field Breaker open. l
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I I ll 1 1 I l N/A l N/A ll AOP-0001 l REV - 1 l PAGE 4 0F 6 l 1 I ll l l 1
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5.0 SUSEQUENT OPERATOR ACTIONS '
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5.1 Select and drive in the SRM and IRM detectors. Switch IRM/APRM l 3*
. recorders to I2M's.
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5.1.1 Downrange IRMS' as necessary to verify reactor power l l ,
decreating.
l l I g 5.2 If any control rods have position indication greater than 04, l l enter AOP-0021 " Anticipated Transient Without Scram".
l 5.3 Verify reactor water level stabilizes at +18" or higher on narrow l g range level indication.
l 1 I y 5.3.1 Switch to single element control and secure operating l l pumps and level control valves as necessary to maintain a [
g stable water level. Leave at least one reactor feed pump l l
running.
l
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5.3.2 As Condensate /Feedwater flow is reduced secure the number g of on-line Condensate Polishers per SOP-0093 to maintain l g flow rates through operating polishers between 1250 Gpm l g and 2350 Gpm. This should correspond to a differential l.
" g .
pressure of between 20 Psid and 30 Psid as read on [lH13- l g P680]. --
l l I ..
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l I l I g l CAUTION l <
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g l Do not attempt to reset the scram l l g l for at least 10 seconds after the l l g l scram to prevent CRI7 damage. l l l l I I l
.j g 5.4 When the scram signal has cleared, reset the scram and return the l l
CRD System to normal. l l
l
- g 5.5 If any control rods have position indication between 00 and 04 l l
l individually select and drive these rods to position 00. [
l I
l 5.6 Restart the Reactor Water Cleanup System, if tripped, per SOP- l g 0090.
~ l l
l 5.6.1 Reject water as necessary to maintain level. l l
l l
l 5.7 To reestablish normal water level perform the following: l 1
5.7.1 I l Line-up Startup Level Control Valve by placing the l g controller in " MANUAL" and set at 0*;. Open the LVL CONT l
g BYP ISOL [lFWS-MOV105]. Slowly open the startup valve l g until the MASTER LEVEL CONTROLLER fully closes operating l g level control valves. l l
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l 5.7.2 Whtn opsrating 1sval control valvas ara full clostd, pitcs l I
the Master Level Controller in " MANUAL" and decrease l l controller output to zero. Verify Startup Level Control l .
' l .
Valve is maintaining reactor water level. l l
l l 5.7.3 When operating level control valves are full closed and l l Startup Level Control Valve can safely handle feedwater l l demand isolate u;se valves by closing [1FWS-MOV27A, 27B l
-l and 27C]. l I
I l 5.7.4 Depress the SETPOINT SETDOWN RESET pushbutton. Null out l l auto setpoint deviation meter on Startup Level Controller l
} and place controller in "AUT0". Slowly increase RPV level l l to approximately 36" using aito/setpoint tape. I I
I l 5.8 If reactor recirc pumps are operating in slow speed, place the l 1
- l. flow control valves to the maximum open position. I I
I l 5.9 Notify Radiation Protection of reactor scram for investigation of l l existing radiological conditions throughout the plant areas. l I
I l 5.10 Perform Subsequent Actions of A0P-0002 " Main Turbine and l l Generator Trips".
l.
I I
l 5.11 Implement Emergency Operating Procedures and Emergency l
l Implementing Procedures as directed by the Shift Supervisor. l ,
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l 5.12 When all parameters have stabilized enter GOP-0007 " Scram l l Recovery". _
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" l l END l
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I lI l 1 I II I I I l N/A l N/A ll A0P-0001 l REV - 1 l PAGE 6 0F 6 1 1 I II I I I 9 - w. y .,7 - - - +e - - - - -